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i MAR 2 0 8811 Docket No. 50-315 Docket No. 50-316 | |||
( | |||
American Electric Power Service Corporation , | |||
Indiana and Michigan Electric Company ATTN: -Mr. John E. Dolan Vice Chairman Engineering and Construction 1 Riverside Plaza Columbus, OH 43216 Gentlemen: | |||
We have received the attached Federal Emergency Management Agency (FEMA) {{letter dated|date=February 25, 1986|text=letter dated February 25, 1986}}, and associated evaluation of the Alert and Notification System for the Donald C. Cook Nuclear Power Plant in Stevensville, Michigan. | |||
The evaluation states that, based on the engineering design review, and the results of the demonstration of the system conducted on August 3,1985, FEMA has determined that the Alert and Notification System installed around the Donald C. Cook Nuclear Power Plant, meets'the guidance of NUREG-0654/ FEMA-REP-1, Revision 1, and FEMA-43 (now published as FEMA-REP-10), and that there is reasonable assurance that. the system is adequate to promptly alert and no.tify the public in the event of a radiological emergency at the site. The caveat on l the Alert and Notification System contained in the 4_4 CFR 350 finding of September 28, 1983, is now removed. | |||
In accordance with 10 CFR 2.790 of the Comission's regulations, a copy of this letter and the enclosure will be placed in the NRC's Public Document Room. | |||
Sincerely, | |||
; " Original signed by W.D. Shafer* | |||
W. D. Shafer, Chief I Emergency Preparedness and Radiological Protection Branch | |||
==Attachment:== | |||
As stated l | |||
l See Attached Distribution l RIII III RI) db | |||
#Df hnell/jlk P 11 ips r U 8603270097 86032 b 1 PDR ADOCK O g5 | |||
1 o-American Electric Fewer Service 2 MAR 2 0 RYi Corporation Distribution cc w/ attachment: | |||
W. G. Smith, Jr. , Plant Manager DCS/RSB (RIDS) | |||
Licensing Fee Management Branch Resident Inspector, RIII Ronald Callen, Michigan Public Service Cornission EIS Coordinator, USEPA Region 5 Office Nuclear Facilities and Environmental Monitoring Section L | |||
* Taylor Letter enly: Stallo l Federal Emergency Management Agency $$m ! | |||
*k | |||
'k [ | |||
Washington, D.C. 20472 h" n J eppler l | |||
oteept gis ,_.-, GCunningha FEB 25 999g l | |||
,. fc T | |||
W f Mr. Victor Stello, Jr. ;1% | |||
Acting Executive Director for Operations '' 4' U.S. Nuclear Regulatory Ccmnission FIL Washington, D.C. 20555 | |||
==Dear Mr. Stello:== | |||
1 he Federal Emergency Management Agency (FENA) has empleted an analysis of ' | |||
the prmpt alert and notification system for the Donald C.. Cook Nuclear Power l Plant in Iake Township, Michigan. %is review has been empleted pursuant to FEMA rule 44 CFR 350; selected evaluative criteria and Appendix 3 in NUREG-0654/ FEMA-REP-1, Rev.1; and FENA-43, the " Standard Guide for the Evaluation of Alert and Notification Systes for Nuclear Power Plants" (now published as FENA-REP-10) . he enclosed report entitled " Donald C. Cook Nuclear Pcwer Plant Site-Specific Offsite Radiological Emergency Preparedness Alert and Notification System Quality Assurance verification" sumarizes the engineering design review, incorporates the results of the telephone survey of the public conducted ime-diately following activation of the alert and notification syst e on August 3, 1985, and confirms the adequacy of the applicable evaluative criteria frczn NURED-0654/FENA-REP-1, Rev.1, and FENA-43. | |||
Based on the engineering design review and the results of the telephone survey, FEMA has determined that the alert and notification syste installed around the Donald C. Cook Nuclear Power Plant satisfies the requirements of NUREG-0654/ FEMA-REP-1, Rev.1, and FEMA-43. herefore, there is reasonable assurance that the system is adequate to prmptly alert and notify the public in the event of a radiological emergency at the site. %e caveat on the alert and notification system contained in the 44 CFR 350 approval dated September 28, 1983, is now re-noved. Governor James Blanchard of Michigan has been advised of this approval. | |||
Sincerely, 80 e Samuel W. Speck- | |||
' Associate Director State and local Programs and Support Enclosure MAR 3 1986 f)l 0 ! ^ | |||
DONALD C. COOK NUCLEAR POWER PLANT , | |||
, SITE-SPECIFIC OFFSITE RADIOLOGICAL' EMERGENCY PREPAREDNESS ALERT AND NOTYFICATION SYSTEM QUALITY ASSURANCE VERIFICATION il - | |||
l. | |||
Prepared for | |||
, , Federal Emergency Man &gement Agency Washington, D.C. 20472 Under Contract No. EMW-83-C-1217 4 | |||
l ll January 29, 1986 | |||
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3 | |||
TABLE OF- CONTENTS i | |||
I. INTRODUCTIO'S 1 4 | |||
A. Identification 1 | |||
: l. Site Information 1 | |||
: 2. Governments Within The 10-Mile Emergency Planning Zone 2 B. Scope Of Review 2 ll 1. Emergency Plans For Offsite Response Organizations 2 | |||
, 2. Alert And Notification System Design Report 3 | |||
: 3. FEMA Evaluation Findings 3 s II. FINDINGS FOR EVALUATION CRITERION E.6 4 A. Administrative Means Of Alerting 3 (E. 6.1, FEMA-43 ) 5 B. Physical Means Of Alerting (E.6.2, FEMA-43) 5 | |||
: 1. Sirens (E.6.2.1, PEMA-43) 5 | |||
, 2. Special Alerting (E.6.2.4, FEMA-43) 21 ll III. FINDINGS FOR EVALUATION CRITERION N.1 22 i | |||
IV. FINDINGS FOR EVALUATION CRITERIA E.5 , F.1, N. 2 , N. 3 , AND N. 5 31 REFERENCE LIST. 32 4 | |||
APPENDIX A: OSPM Topographical Profile Charts OSPM Topographical Input Data OSPM Siren Sound Pressure Level Input Data OSPM Meteorological Input Data OSPM Siren Sound Pressure Level Output Data - | |||
APPENDIX B: Sample Size Determination I | |||
L | |||
I Donald C. Cook Nuclear Power Plant Site-Specific Offsite Radiological Emergency Preparedness Alert And Notification System Quality Assurance verification State Of Michigan Berrien County | |||
^ | |||
j I. INTRODUCTION A. Identification | |||
'! 1. Site Tnformation i | |||
The Donald C. Cock Nuclear Power Plant is located in Lake Township, Berrien County, Michigan, approxi- | |||
.' mately 11 miles south-southwest of the center of l' Benton Harbor, Michigan. The site encompasses about | |||
] 650 acres along the eastern shore of Lake Michigan, l with approximately 4,350 ft of lake frontage, and extends to an average of 1-1/4 miles eastward f rom the lake.1 r | |||
Approximately 50% of the area within a 10-mile radius | |||
; of the plant site is comprised of water. A large 9 portion of the remaining area is devoted to agricul-d' ture. Major agricultural products are apples, cherries, grapes, peaches, feed grains, livestock, l and dairy products.1 Within the Donald C. Cook Nuclear Power Plant's 10-mile-radius emergency planning zone (EPZ) , there are two major roadways, Interstate Route 94 and the Red Arrow Highway. The Andrews University Airport is i approximately 10 miles east of the plant on the 1 | |||
1 l i | |||
t | |||
4 southwest edge of Berrien Springs, and Warren Dunes State Park is located along the lake approximately 6 miles south of the plant site.1 Recreational activities within the Donald C. Cook Nuclear Power Plant EPZ take place primarily in the summer along the beach areas of Lake Michigan and at Warren Dunes State Park. The park is equipped with camping f acilities as well as lake shore f ront beach areas.1 l' | |||
ji 2. Governments Within The lO-Mile Emeroency Plannino irme The EPZ for the Donald C. Cook Nuclear Power Plant is defined by a 10-mile-radius circle with the plant as j the center point. The EPZ is located entirely within the State of Michigan in Berrien County. | |||
An estimate of the- population within the Donald C. | |||
Cook Nuclear Power Plant EPZ is approximately 69,000 persons.2 According to 1980 census data, the largest population concentration within the Donald C. | |||
Cook Nuclear Power Plant EPZ is in the twin cities of Benton Harbor - St. Joseph with a population of 1 . 14,707 persons and 9,622 persons, respectively.3 2 | |||
B. Scone Of Review g 1. Emeroency Plann For Off site Response Oroanf rations All appropriate offs'ite radiological emergency plans and preparedness site-specific to the Donald C. Cook Nuclear Power Plant have been reviewed by the Federal Emergency Management Agency (FEMA) Region V and the Regional Assistance Committee. | |||
2 | |||
~ | |||
l | |||
*.m-- * - - - - , -- - - -g w- e-+ ,e--- + mew ------- - --,-%--v+ - -% i,--a eg--e- -------w* * ''f' '-P'''-*'**-"'"'-r * - "-' - | |||
: 2. Alert And Notification System Desien Report The physical means established for alerting the | |||
- public within the Donald C. Cook Nuclear Power Plant EPZ are documented in the following: | |||
. Indiana and Michigan Electric Company, " Donald C. | |||
Cook Nuclear Plant Prompt Public Notification | |||
~ | |||
System, FEMA-43 Design Report," November 1, 19844 (hereinafter referred to as the Design Report). | |||
! 3. FEMA Evaluation Findinas The offsite radiological emergency plans and preparedness site-specific to the Donald C. Cook l Nuclear Power Plant received FEMA approval under Title 44 of the Code of Federal Reculations, Part 350 (44 CFR 350), conditioned upon verification of the adequacy of the public alert and notification system, | |||
, as documented in the: | |||
i ' | |||
. Letter to the Honorable James J. Blanchard, ' | |||
;(- | |||
1 Governor of Michigan, signed by Louis O. | |||
Giuffrida, Director, FEMA, dated September 28, 1983;5 and the i | |||
. Letter to William J. Dircks, Executive Director for Operations, U.S. Nuclear Regulatory Commission, signed by Dave McLoughlin, Deputy i | |||
Associate Director, State and Local Programs and Support, FEMA, dated September 28, 1983.6 3 | |||
II. FINDINGS FOR EVALUATION CRITERION E.6 l | |||
The Design Report describing the alert and notification | |||
) | |||
system for the Donald C. Cook Nuclear Power Plant was reviewed against evaluation criterion E.6 and Appendix 3 of NUREG-0654/ FEMA-REP-1, Revision 1, " Criteria for Pre-paration and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" | |||
, (hereinaf ter ref erred to as NUREG-0654/ FEMA-REP-1, Rev. | |||
~ | |||
1). This evaluation criterion states: | |||
l p Each organization shall establish administrative and physical means, and the time required for | |||
; notifying and providing prompt instructions to 1 the public within the plume exposure pathway I | |||
Emergency Planning Zone. (See Appendix ~3.) It-shall be the licensee's responsibility to demon-strate that such means exist, regardless of who a' implements this requirement. It shall be the p' responsibility of the State and ments to activate such a system.gocal govern-l i The bases for review against this evaluation criterion were l the corresponding acceptance criteria of FEMA-43, " Standard | |||
-l Guide for the Evaluation of Alert and Notification Systems | |||
.for Nuclear Power Plants"8 (hereinafter referred to as j! FEMA-43). This quality assurance verification review was I | |||
performed to make a determination of alert and notification system adequacy prior to conducting a demonstration of this | |||
' ~ | |||
system for.the Donald C. Cook Nuclear Power . Plant on August i | |||
3, 1985. | |||
Based upon this quality assurance verification review and public survey results, International Energy Associates Limited concluded that the design and implementation of the alert and notification system for the Donald C. Cook Nuclear Power Plant and its supporting procedures conformed 4 | |||
l sufficiently to the acceptance criteria, as stated in l FEMA-43, for evaluation criterion E.6 of NUREG-0654/ FEMA- l REP-1, Rev.1, to support a FEMA finding that the alert and notification rystem is adequate. | |||
This portion of the quality assurance verification review evaluates the Donald C. Cook Nuclear Power Plant's alert and notification system against FEMA-43 acceptance criteria | |||
~ | |||
in the following areas: the physical means of alerting and 7 the special alerting methods. | |||
7 A. Administrative Means of Alerting (E.6.1, FEMA-43) | |||
,. The administrative means of alerting for the Donald C. | |||
Cook Nuclear Power Plant were evaluated by FEMA and the Regional Assistance Committee in their determination of adequacy under 44 CFR 350.5,6 B. Physical Means of Alerting (E.6.2, FEMA-43) | |||
As described in Section 2.2.2.1 of the Design Report, the physical means of alerting for the Donald C. Cook i | |||
Nuclear Power Plant EPZ consist of 49 fixed siren units. | |||
: 1. Sirens (E.6.2.1, FEMA-43) l The Donald C. Cook Nuclear Power Plant siren alerting system, as submitted in the Design Report, was evaluated in accordance with the design evaluation | |||
; methodology detailed in " Analysis of Siren System Pilot Test. "9 ' | |||
5 | |||
. _ _ . - . . . = _ . . _ - . .- -_. .. . - . - . | |||
i i | |||
The siren system as analyzed consists of 49 sirens: | |||
9 Alerting Communicators of America (ACA) | |||
Hurricane (sometimes referred to as i Penetrator-50) sirens (130 dBC); | |||
24 ACA Penetrator-10 sirens (123 dBC); and 16 ACA Banshee sirens (116 dBC) . | |||
Anechoic-chamber measured octave band sound pressure spectrums (supplied by the licensee) were used to verify the rated output of the ACA Penetrator-10 and the ACA Banshet sirens at 125 dBC and 115 dBC, respec-tively. The more conservative values of 123 dBC for the ACA Penetrator-10 sirens and the confirmed j' manufacturer's rating of 115 dBC for'the ACA Banshee sirens are used in this evaluation. Test data for the ACA Hurricane sirens were disclaimed by the manuf acturer owing to the physical limitation of the test facility.10 I | |||
Routine siren testing procedures and operability for | |||
: 3. the Donald C. Cook Nuclear Power Plant siren warning system have been reviewed and determined to satisfy | |||
, FEMA-43 operability requirements. | |||
I 1 | |||
The Donald C. Cook Nuclear Power Plant siren alerting system design follows the 10 dB loss per distance doubled attenuation rate as recommended in NUREG-0654/ FEMA-REP-1, Rev.1, for situations in which special conditions are absent. No additional corrections were made' for site geographical features, nor were corrections applied to reflect site meteorological conditions. | |||
6 | |||
- -- - ._ - . - _ . - - .. . - - . - - . - _ - . . - . - - . ~ - | |||
This evaluation is conducted by ascertaining the adequacy of the design procedure -- the 10 dB loss per distance doubled attenuation rate without any corrections -- in the presence of site-specific topographical and meteorological conditions through comparisons with the Outdoor Sound Propagation Model (OS PM) 9 results for specific sirens. | |||
Fourteen sirens,13 of which are depicted on thb U.S. | |||
~ | |||
Geological Survey's Benton Harbor quadrangle map (see Figure 1 of this report), were selected for this quality assurance verification review. This selection (comprised of three ACA Hurricane sirens, four ACA Penetrator-10 sirens, and seven ACA Banshee sirens) is representative of the site-specific topo-graphical conditions around the more populated areas within the Donald C. Cook Nuclear Power Plant EPZ. | |||
Surf ace weather parameters, representativeo ' f site l prevailing summer daytime conditions, were used in the OSPM calculations. Appendix A of this report I | |||
contains OSPM topographical profile charts, OSPM topographical input, OSPM sound pressure level input, OSPM meteorological input, and OSPM sound pressure level output for each of the 14 individual OSPM siren runs. | |||
l To compare the acoustical coverage estimates of OSPM with the design procedure, the output dBC levels along each azimuth of the 14 analyzed sirens were ; | |||
classified into two categories according to terrain profiles : partially hilly terrain (minor obstruc-tions) and relatively~ flat terrain (generally un-obstructed line-of-sight) . In addition, a shadow zone category reflecting the influence of site weather conditions on the siren effective propagation 7 | |||
.c | |||
_. . ___________..____..._____m _ _ _ _ _ . . . _ _ . . _ _m _ _ _ _ _ _ _ _ _ _ _ ____.______m_ _ _ _ _ . | |||
FICURE 1 | |||
.,n se s'a'us . s. a .s a smee D.C. COCK $3REN C 0!stO U R PLOT an.*-=a.a asesen wr** acca6 w si,s t=a .=s*v .8"- | |||
! .r,7 ' t.-_. | |||
p sy: .- - ( *. .. . y r . * * | |||
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i | |||
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70 dBC r . | |||
ar | |||
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u , , . . , e e v .t . = s- ,p s | |||
=, | |||
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e . . . . s P | |||
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: g. . . . . . . , ., | |||
s I | |||
. ... x, ., | |||
i | |||
; . h* . ..o..--. . , | |||
7 | |||
* Y\ 4 | |||
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u... | |||
......s. | |||
'? ... h- ~" | |||
. C:. ;. ' - . - ~ - | |||
~ l g, s- .. .. - . | |||
2..*.u..':'......~. .. ,, - | |||
-~- | |||
[..~ b . * ;- - t . , . :-,..---- .* """''"'***'''' | |||
x . - - - . = :. w.....=. | |||
: 5. g.q.:. ;,. :-~ | |||
=&LGE E==.== | |||
range was used. Regressions of dBC versus the logarithm of distance were performed for the siren types over the terrain and weather categories within 1,000 ft to 10,000 f t of the sirens. | |||
l The regression results of the OSPM siren sound pressure levels are presented in Figures 2 through 10 of this report. Also depicted is the 10 dB loss per distance doubled attenuation rate curve. | |||
Several general observations can be made concerning | |||
] the siren range comparisons. First, the 70 dBC and I | |||
60 dBC ranges for all siren types estimated by the 10 dB loss per distance doubled attenuation rate are l conservative with respect to OSPM results over flat and partially hilly terrains. Second, in the case of | |||
: d. ' | |||
the smaller ACA Penetrator-10' and ACA Banshee sirens (which are mounted at 48-ft to 50-ft heights as | |||
, opposed to the bigger ACA Hurricane sirens mounted 86 f t above the ground) , the acoustic shadow effect | |||
( induced by the wind and thermal gradients is more | |||
:1 pronounced than that of the ACA Hurricane sirens. | |||
This is because the gradients closer to the ground | |||
] surface are typically larger than those higher up within the planetary boundary layer. Thus, the design procedure, when compared to the-results of the OSPM, yielded liberal 70 dBC and 60 dBC. ranges in the cases of the ACA Penetrator-10 and ACA Banshee sirens in the shadow zones and comparable ranges for the ACA Hurricane sirens. The regression results are sum-marized in the following table (which is presented af ter Figures 2 through 10) : | |||
9 | |||
3 FIGURE 2 100 ~~ ~ | |||
COMPARATIVE OSPM RESULTS, SIIADOW ZONE (IlURRICANE SIREN) | |||
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lil !!l Ihll U l'l ll l l ! b' W '''ildb. dM . | |||
! sh, , 'h 13 Y, U ' | |||
: ! Regression Of OSPM Computations, Shadow Zone 's g ![ ..l d i .?: .' | |||
W ..! i. .j en 80 .2 di.1_l_.dl b [n I.I Z fi.i! 1 h; [pg i | |||
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a 70 | |||
!! Ihl 70 dBC Criterion Level For > | |||
i ll .h! ll liI ! Ik I ! | |||
F | |||
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2,000 Persons /Sq Mi 1 l lll1111 ll j ,s h>( | |||
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t i ; i i, l : 70 dBC At 12,800 Ft- ' | |||
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hhIC M ' e d 60 :!. 'll-l l ll :i! illililliliillllil!!;l3!!Ll;Wllll'lBlIl l l ll l[; | |||
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f ' 60 dBC Criterion Level' liForil 5 2,000 Personsl /Sg pMill lllll j - ---- - - - | |||
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30 5'' ' | |||
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! ! .. I t | |||
100 200 500 1,000 2,000 5,000 8,000 Distance From Siren In Feet | |||
. 2._ . | |||
FIGURE 3 100 ._. . ._ _C_.OMPARATIVE ., OSPM RESULTS, PARTI ALLY llILL,Y .(IlURRICANE SIREN) | |||
.7 7 . . . , | |||
ij :i. ' | |||
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i, | |||
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i- i Js , | |||
iji 3 i | |||
';t: | |||
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Lower 95% | |||
f | |||
( f' i l , | |||
lI: | |||
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. i ._ . .. . .. . . | |||
j..;,I' D Ns,d | |||
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I 0 k i | |||
]l h0. - | |||
ji ,, j j]ll | |||
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pt 1 c | |||
, l ll t ih ; | |||
h | |||
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h | |||
!4 h. | |||
7 ali | |||
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4! | |||
2 | |||
{: | |||
j Ii 5 ;ll ll f! ! l l.i . !! l l ll id 1.dh. d Elh ll l l l I | |||
[ ' | |||
l q L | |||
u k<\ 4 i Regression Of OSPM Coniputations, Partially Ililly l ! | |||
ql-L S i L,. q, > | |||
. ui BO | |||
.o il a,.., all ..lj i | |||
. . __ _ __. p ' | |||
I | |||
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.. j,b E ji. 1,]!. | |||
41 kl $ | |||
.- i , ii I j , li 7 A q m i s s. - | |||
,; i c i a | |||
. ... I l' l h! : | |||
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f,i \ ' | |||
l;. ; .l. -l | |||
.: / i f 2 ii lj i j j : . . | |||
n . , | |||
N 1 l i % . i:. ;' ; . ie | |||
; D' p S hc'], | |||
; : : !! n l- l [ 4 Ylf.;; O | |||
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:m i i l i ! (( L I | |||
'n ' .4: '.l :i .p4 [. , Ms [l'' | |||
! c i . ,, | |||
lllli!! | |||
l ll l lil!!h !u !L s\~p 'L .N d | |||
!O | |||
;a70 i i i l d | |||
' 70 dBC Criterion Level For > +fa2 Mi - | |||
- 1 - | |||
p A" 2,000 llii;ll' Pe iliil!ll!Pl?';l!!!Tlill rsons /SglIll i l l I l I I I l \ (1 | |||
}'. | |||
!$ ,I*'. ' | |||
',! I ll l' f i l o I'.I I i 70 dBC At 12,800 Ft' | |||
/l | |||
,;i! I ! | |||
i e ..i F m i i j r< 'l L | |||
'l 1' .h it i I | |||
I:l!,i | |||
! ;t 10 dB/ Dis | |||
,lll M I E I M iIllH!!! ! ''' ' ' -l " /p %iii \0 , | |||
I 1 | |||
M | |||
!! ili !' | |||
$ 60 l il I!llllliloillulil!ilti:tance IHI%llPlfl 1 l lllll Doubled l ,' g i, l1 3 j 'N '' | |||
I , | |||
,5 | |||
'60 dBC Criterion Level For 5 2,000 Persons /Sq Mi | |||
* W Y' | |||
d a - - - - | |||
lilil \ ' | |||
; ., ',illii ll l l | |||
!ill' lI! ll illllllFlillIli'!!l.!lil!'lil.1 I I I I ! l l l l l $ ' | |||
N I ! 60 dBC At 6,400 Ft' ''' | |||
!' l'!i,p!. 'l ll l i i: | |||
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' s | |||
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50 _ | |||
'll | |||
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2, 3 | |||
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40 | |||
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'lli li ' | |||
4 t ,ii . | |||
its si d t,l .l i .. 1 ! t i. i s ,jl f; ; i' i.t ... ;i i .i. J ." : | |||
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.ili .: | |||
9' . | |||
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il i l.. !nr .o s, { 1;, :q, ; . li. | |||
!i 't- | |||
'[ .i i ei ip [; R | |||
, il 'i. .i:. , . | |||
' ' 9 i ; i: 3.- t l., - - | |||
1,i.,.t i i o , 1,;. pij i | |||
ll a, i!l .g .! . , 2 . . | |||
i . .i.I ju ; | |||
il:: | |||
i I o., | |||
,I i i ,- . ,. . an i q' | |||
. .r ! | |||
l E " " | |||
r : ! Iii ! | |||
' ';oh l 3 i i i.i - | |||
.i o, ' | |||
_U!'''! | |||
i 30 I' ' i- ' ' l ' - I 100 200 500 1,000 2,000 5,000 0,000 Distance From Si ren In Feet | |||
FIGURE 4. | |||
100 COMPARATIV8: OSPM RESULTS, RELATIVELY FLAT TERRAIN (HURRICANE SIREN) | |||
! Jyiq | |||
. i. .. | |||
l t | |||
i rp I | |||
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ir p | |||
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_7 FIGURE 5 100 COMPARATIVE OSPM RESULTS, SilADOW ZONE (PENETRATOR SIREN) | |||
T T V ;!p 4 ' ' | |||
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w . .__. _ . ._.. _._ - | |||
FIGURE 6 100~~ '~ | |||
COMPARATIVE OSPM RESULTS, PARTI ALLY IIILLY (PENETRATOR SIREN) | |||
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100 200 500 1,000 2,000 5,000 8,000 Distance From Siren In Feet | |||
j FIGURE 9 | |||
--r--.OMPARATIVEC | |||
:100 3; ; ;, ; OSPM , | |||
g q RESULTS , PARTI ALLY q | |||
IIILLY (BANSIIEE SIREN) | |||
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100 200 500 1,000 2,000 5,000 8,000 Distance From Siren In. Feet | |||
FIGURE 10 100.... . | |||
CoMPanAT1ve osPM nesucTs, aeoarivety FLAT Tennain (Bansiise Siaen) | |||
_. . _. l I il i j li l l i Tii ; r i U li II ,1 Fi g, b. ' | |||
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_.__. . L 100' 200 500 1,000 2,000 5,000 8,000 Distance From Siren In Feet | |||
REGRESSED RANGE (In Feet) | |||
Siren Type 70 dBC 60 dBC ACA Hurricane - | |||
10 dB Rate 6,400 12,800 OSPM Results Flat Terrain >10,000 >10,000 ,. | |||
Partially Hilly 10,000 >10,000 Shadow Zone 7,100 >10,000 ACA Penetrator-10 10 dB Rate 3,900 7,800 OSPM Results | |||
} Flat Terrain 7,000 >10,000 Partially Hilly 6,000 >10,000 is Shadow Zone 3,300 5,200 ACA Banshee 10 dB Rate 2,250 4,500 OSPM Results i Flat Terrain 3,300 6,400 Partially Hilly 2,900 5,400 f Shadow Zone 2,200 3,400 j' The above assessment is supported by a comparison of individual siren coverages in terms of the area within the 70 dBC and 60 'dBC contours. For each siren type located on the U.S. Geological Survey's | |||
. Benten Harbor quadrangle map, the area coverages of j 60 dBC and 70 dBC were numerically integrated. The l results are as follows: | |||
l 4 | |||
l l | |||
19 1 | |||
1 | |||
i | |||
) | |||
i AVERAGE AREA (In Square Miles) | |||
Siren Type 70 dBC 60 dBC ACA Hurricane 8.578 18.477 ACA Penetrator-10 3.845 12.095 ACA Banshee 1.070 3.488 Using these results, the following average effective radii are derived: | |||
1 EFFECTIVE RADIUS (In Feet) | |||
Siren Tvog 70 dBC 60 dBC i | |||
ACA Hurricane 8,725 12,804 ACA Penetrator-10 5,841 10,360 ACA Banshee 3,081 5,563 l | |||
: 1. These results show that the design procedures, namely the 10 dB loss per distance doubled. attenuation rate l without additional corrections, still yielded conser-vative 70 dBC and 60 dBC ranges for the Donald C. | |||
] Cook Nuclear Power Plant EPZ. | |||
The results of the individual OSPM runs were combined to generate a comprehensive. overview of the siren l | |||
. sound pressure levels -over the Benton Harbor area as depicted in Figure 1 of this report. A surface inter-polation and contouring program utilizing the output results of the 14 sirens that influence the coverage in the area was used to generate the sound pressure level contour overlays. These contours account for 1 | |||
site-specific topographical and meteorological l | |||
; 20 l | |||
l l | |||
_ _ _ . .,_ _ _._, . . _ , _ . , _ . ._.,_.__,,,___m., , . , . _ , . _ . _ __ 6,m___, _ . . . _ . _ ,,,_. | |||
effects and the logarithmically additive effect of-the seven omni-directional Banshee sirens. The results confirm what Exhibit B of the Design Report indicates: that each area with a population density l | |||
of 2,000 persons or more. per square mile is covered by siren sound pressure levels of 70 dBC or greater and all other populated areas are covered by siren sound pressure levels of 60 dBC or greater. | |||
~ | |||
In conclusion, the Donald C. Cook Nuclear Power Plant siren alerting system is found to meet the specific ' | |||
design requirements of FEMA-43. j l ! | |||
i | |||
, 2. Special Alerting (E.6.2.4, FEMA-43) ' | |||
Sirens are the primary means of notification for the | |||
! Donald C. Cook Nuclear Power Plant. The Design Report, in Section XI of Exhibit E, states that alert monitor receivers are used to alert schools, hos-pitals, and other institutions. Section XX states that law enforcement and fire services coordinate to | |||
, extend public notification by sector, utilizing public address systems on emergency vehicles. Ac-cording to Exhibit G of the Design Report, parks, beaches, and recreational areas are notified by local authorities. | |||
1 21 | |||
III. FINDINGS POR EVALUATION CRITERION N.1 l l | |||
On August 3,1985, the physical means (sirens) used to alert the population within the Donald C. Cook Nuclear Power Plant EPZ were demonstrated to satisfy the alert and notification aspects of 44 CFR 350.9 (a) . This demon-stration was conducted by using the methods specified in Section N.1 (a, b) .2 of FEMA-43.8 The results indicate that this portion of the alert and notification system evaluation conforms to FEMA-43 and NUREG-0654/ FEMA-REP-1, Rev. 1.7 i | |||
The August 3,1985, demonstration of the Donald C. Cook Nuclear Power Plant siren alerting system consisted of a l double activation of all sirens and a subsequent telephone survey to estimate the proportion of EPZ households actually alerted. The first siren activation was initiated at 1:00 p.m. (Eastern Daylight Time) . The second siren activation occured at 1:10 p.m. All sirens were reported operating during both activations. | |||
The telephone survey of EPZ residences began at approxi-mately 1:13 p.m. (Eastern Daylight Time) and was completed | |||
, within 47 minutes.- This sureey was conducted by 38 telephone interviewers, each with a separate WATS line and computer terminal. | |||
l The universe of households to be surveyed was determined by establishing a 10-mile-radius circle around the latitude and longitude of the plant. The sample incorporated a sorted master list of approximately 2,500 households (addresses and telephone numbers) believed to be'within the Donald C. Cook Nuclear Power Plant EPZ. | |||
22 | |||
A sufficient number of replicated subsamples were developed from this master list to ensure that the required number of telephone calls would be made, i.e. , to establish the pro-portion of households alerted to within a 5% precision at a 95% confidence level. The method for sizing the sample to achieve this result is described in Appendix B of this r eport. | |||
The questionnaires for this telephone survey are included. | |||
as Figure 11 of this report. Although Spanish interviewers were available, no Spanish interviews were conducted. | |||
As part of the telephone survey, a total of 285 households believed to be within the Donald C. Cook Nuclear Power Plant EPZ were contacted, and the responses were collected in an automated data base. Of this group, 71 respondents it stated that they were not alerted. However, before running the final tabulations, all of the addresses and cross streets obtained during the interviews were-checked on maps I | |||
to validate household locations. Of the 285 households, four were found to be outside the EPZ. Therefore, data i were tabulated on the 281 respondent households that were located within the EPZ. Respondents at 29 of these house-holds had been away from home at the time of the siren alerting system demonstration and, therefore, were not i | |||
included in the alerting analysis. Of the remaining 252 I | |||
households, 80.2% (202) indicated that they had heard the siren (s) during the demonstration. By using the estimated i | |||
number of households within the EPZ (21,568 from Reference | |||
., 2) in the confidence interval expression in Appendix B of this report, an estimated 95% confidence interval for the proportion of the total EPZ population alerted that ranges f rom 74.8% to 84.6%' can be derived. In other words, at the 95% confidence level, between 74.8% and 84.6% of the house-holds within the Donald C. Cook Nuclear Power Plant EPZ would have reported being alerted by the siren alerting system. l 23 | |||
l FIGURE 11. | |||
Chilton Research Services Study #9047 Radnor, Pennsylvania August 3,.1985 0$1B#3067-0103'(FEMA 9/85) | |||
FEMA NUCLEAR POWER PIANT ALERTING AND NOTIFICATION SYSTEM: PUBLIC TELEPHONE SURVEY D.C. Cook Time Began AM PM Interview # | |||
(1-3) | |||
Time Ended AM PM Zip Code (6-10) | |||
Sample Type (11) | |||
! RECORD BEFORE DIALING -Telephone # | |||
-l (Area Code) (Exchange) (Number) (12-21) | |||
INTRODUCTION: | |||
Hello, =y name is . We're calling households long distance | |||
, from Chilton Research Services as part of a survey. This survey is sponsored by The Federal Emergency Management Agency (FEMA) of the United States Government. | |||
Your answers are voluntary and will be kept strictly confidential. | |||
t | |||
: 1. First of all, is this (REPEAT # DIALED)? | |||
l Yes 1 | |||
~{ '! | |||
TERMINATE AND DIAL AGAIN No 2 | |||
: 2. As you may or may not know, there was a test of the public warning / alert notification | |||
, system for the D.C. Cook Nuclear Power Plant. Did you, or any other member of this household, hear the sirpn/ warning signal from this test today? | |||
22- | |||
, SKIP TO Q. 4 Yes 1 SKIP TO Q. 4A No 2 Heard from CONTINUE another 3 source ASK IF ANY OTHER HOUSEHOLD *,* 0" MEMBER IS MORE KNOWLEDGEABLE l | |||
24 l | |||
FIGURE 11 (CONTINUED) | |||
: 3. What did you or your household hear? (D0 NOT READ. CIRCLE ALL THAT APPLY) | |||
(23-25) | |||
A siren , 1 SKIP TO Neighbor told me 2 Q. 4 Other family member told me 3 Other (SPECIFY) 9 CONTINUE Don't Know Y | |||
, 3a. Did you hear . . . (RIAD LIST. CIRCLE ALL THAT APPLY) | |||
(30-32) | |||
A Siren 1 From a Neighbor 2 From Another Family Member 3 o | |||
Or by means of something else 9 (SPECIFY) . | |||
1 DO NOT READ Don't Know Y 4 (IF " HEARD EMERGENCY SIGNAL ** ASK Q. 4 BELOW; ' OTHERWISE SKIP TO Q. 4A) | |||
{ | |||
Were you at home or away from home when you heard the siren signal? | |||
37-SKIP TO Q. 5 Away From Home 2 a | |||
25 l | |||
FIGURE 11 (CONTINUED) 6A. (IF "DID NOT HEAR EMERGENCY SIGNAL") | |||
i Were you at home around 1:00 this afternoon? | |||
36-Yes, 1 No 2 Don't Know Y | |||
: 5. Has your household ever received information which tells you what to do in the event of a "real" emergency at the D.C. Cook Nuclear Power Plant. This white booklet with burgundy and grey letters titled, " Emergency Planning in Berrien County" was mailed to you this month f rom the Cook Energy Information Center. Do you remember receiving this information? | |||
41-Yes 1 | |||
, No 2 Don't Know Y | |||
, 4. Because we need to d'eter=ine whether or not you live within the 10 mile Imergency | |||
'' Planning Zone of the D.C. Cook Nuclear Power Plant, would you plesse give me this address? (PAUSE FOR ANSWER) | |||
ADDRESS: | |||
i and the nearest intersection (or cross street) to this house. | |||
Also, what community is this? . | |||
On behalf of Chilton Research Services and the Federal Emergency Management Agency, I would like to thank you for your time and for giving us this valuable information. | |||
t 26 | |||
l FIGURE 11 (CONTINUED) 1 82773Q SPANISH ! | |||
Chilton Research Services Study #9047 Radnor, Pennsylvania August 3, 1985 OMB #3067-0103 (FEMA 9/85) i FEMA NUCLEAR POWER PLANT ALFfTING AND NOTIFICATION SYSTEM: PUBLIC TELEPHONE SURVEY D.C. COOK Time Began AM. PM Interview i (1-5) | |||
Time Ended AM PM Zip Code o | |||
(6-10) | |||
Sample Type (11) | |||
RECORD BEFORE DIALING -Telephone # | |||
(Area Code) (Exchange) (Number) (12-21) | |||
INTRODUCCION: | |||
oj Buenos dias (noches). Estamos llamando residencias para larga distancia de Chilton heaarch Services como parte de un estudio. Esta esrudio es patrocinado por la Agencia Fedaral de Emergencia (FEMA) del gobierno de los Estados Unidos. | |||
Sus repuestas son voluntarias y se mantendran en confianza estricto. | |||
: 1. Primero, llame el numero (RIPEAT # DIALED)? | |||
7' Yes (Si) 1 1. | |||
TERMINATE AND DIAL AGAIN No 2 | |||
: 2. Como, Ud. puede saber o no, habia una prueba del sistema de alerta para D.C. Cook. | |||
Oyo Ud. , o algun miembro de su familia, un senal de alerta de esta prueba de hoy? | |||
22-SKIP TO Q.4 Yes Si 1 i | |||
SKIP TO Q. 4A No 2 Heard from CONTINUE 3 source (de otra manera). | |||
ASK IF ANY OTHER HOUSEHOLD ,* " | |||
MEMBER IS MORE KNOWLEDGEABLE 27 | |||
FIGURE 11 (CONTINUED) | |||
: 3. Como Ud. supo de es ta senal de emergencia? (D0 NOT READ. CIRCLE ALL THAT APPLY) | |||
(23-29) siren 1 SKIP TO neighbor told me i 2 Q. 4 other family membe.r told me 3 Other (SPECIFY) 4 CONTINUE Don't Know Y 3A. De que manera supo . . . (READ LIST. CIRCLE ALL THAT APPLY) | |||
(30-36) de Sirena 1 de un vecino 2 de algun otro miembro de familia (0 de otra manera) 4 (SPECIFY) | |||
DO NOT READ Don't Know (No sabe) Y | |||
( . | |||
4 (IF " HEARD EMERCENCY SIGNAL" ASK Q. 4 BELCM; OTHERWISE SKIP TO Q. 4A) l Estaba en casa o fuera de la casa cuando Ud. supo de esta senal de emergencia? | |||
37-Home 1 SKIP 70 Q. 5 Away from 2 | |||
i home l | |||
28 | |||
.l | |||
FIGURE 11 (CONTIEUED) 6A. (IF "DID NOT HY.AR EMERGENCY SIGNAL") Estaba en casa a la una, esta dia? | |||
Yes 1 No 2 l | |||
Don't Know Y | |||
: 5. Ha recibido Ud. en su casa instrucciones explicandole que Ud. debe hacer en caso de una emergencia "verdadera" a la planta nuclear D.C. Cook? El librito con letras de marron y gris es llamado, " Emergency Planning in Berrien County", y habia enviado por correo a Ud. durante esta mes, del Cook Energy Centro del Informacion. Se acuerda de recibir esta informacion? | |||
: Yes 1 l No 2 Don't Know Y | |||
: 6. Por razon deteminar si Ud. vive o no vive dentro de la limite de 10 millas de La Zona de Planificacion de Emergencia. Por favor decirme la dirrecion de la casa que esta? (PAUSE FOR ANSWER) | |||
ADDRESS: | |||
I y que es la interseccion mas cerca de su casa o calle principal? | |||
i y en que comunidad vive Ud.? | |||
I Por la compania Chilton Research Services y la Agencia Federal de Emergencia, quisiera agradecer a Ud. por su tiempo y para darnos esta informacion importante. | |||
l 29 | |||
P The sample of 281 households was also used to estimate the proportion of households within the EPZ that stated they received information about what to do in a real emergency at the Donald C. Cook Nuclear Power Plant. Of these 281 households, 73.7% (207) responded that they had received the inf ormation, 22.8% (64) responded that they had not received the information, and 3.5% (10) did not know or refused to state whether they had received the infor-mation. Using the approach discussed previously, the following estimates for the entire EPZ population resulted (at the 95% confidence interval): | |||
. Between 68.3% and 78.4% of the households would have reported receiving the information; | |||
. Between 18.3% and 28.0% of the households would have responded that they had not received the information; | |||
{' | |||
and | |||
. Between 2.0% and 6.4% of the households would not have known or would have refused to state whether | |||
, they had received the information. | |||
9 In conclusion, no areas of the Donald C. Cook Nuclear Power l | |||
Plant siren alerting system were identified as needing enhancements. | |||
30 | |||
IV. FINDINGS FOR EVALUATION CRITERIA E.5, F.1, N.2, N.3, AND N.5 Those -aspects of the alert and notification system addressing evaluation criteria E.5, F.1, N.2, N.3, and N.5 of NUREG-0654/ FEMA-REP-1, Rev. 1, have been reviewed by FEMA and found to be adequate to provide reasonable assurance that appropriate protective measures can be .taken | |||
~ | |||
off site in the event of a radiological emergency. This conclusion is documented in letters to the Honorable James J. Blanchard, Governor of Michi@an, signed by Louis O. | |||
Giuffrida, Director, FEMA, dated September 28,1983;5 and William J. Dircks, Executive Director for Operations, U.S. | |||
Nuclear Regulatory Commission, signed by Dave McLoughlin, | |||
; Deputy Associate Director, State and Local Programs and Support, FEMA, dated September 28, 1983.6 In these letters, the Donald C. Cook Nuclear Power Plant received FEMA approval under 44 CFR 350, conditioned on an ultimate approval and verification of the public alert and notifi-cation system as called for in NUREG-0654/ FEMA-REP-1, Rev. | |||
1. | |||
4 I | |||
l 31 | |||
l 1 | |||
) | |||
REFERENCE LIST | |||
: 1. Indiana and Michigan Electric Company. 1982. " Donald C. | |||
Cook Nuclear Power Plant updated final safety analysis report." July 1982. | |||
: 2. Donnelley Marketing Information Services. 1985. "American profile." July 11,1985. | |||
: 3. U.S. Department of Commerce, Buretu of the Census. ' 1983. | |||
1980 census of population. Volume 1, Chapter A, Part 1, | |||
" United States summary. " April 1983. | |||
: 4. Indiana and Michigan Electric Company. 1984. " Donald C. | |||
Cook Nuclear Plant prompt public notification system, FEMA-43 design report. " November l',1984. | |||
: 5. Federal Emergency Management Agency. 1983. Letter to the Honorable James J. Blanchard, Governor of Michigan, signed by Louis O. Giuffrida, Director. September 28, 1983. | |||
: 6. Federal . Emergency Management Agency. 1983. Letter to William J. Dircks, Executive Director for Operations, U.S. | |||
Nuclear Regulatory Commission, signed by Dave McLoughlin, Deputy Associate Director, State and Local Programs and Support. September 28, 1983. | |||
: 7. Nuclear Regulatory Commission and Federal Emergency | |||
) Management Agency. 1980. " Criteria for preparation and evaluation of radiological emergency response plans and 1-preparedness in support of nuclear power plants." | |||
NUREG-0654/ FEMA-REP-1. Revision 1. November 1980. | |||
t 8 .' Federal Emergency Management Agency. 1983. " Standard guide for the evaluation of alert and notification systems f or nuclear power plants. " FEMA-43. September 1983. | |||
. 9. International Energy Associates Limited. 1983. " Analysis of siren system pilot test." IEAL-333. November 2,1983. | |||
:t 10. Biersach and Niedermeyer Company. Letter from James E. | |||
Biersach, President. Subj ect: Manufacturer of ACA Penetrator-50 siren disputes test result interpretation by Acoustic Technology Incorporated and supplies adjusted test results. (No-date). | |||
i 32 l | |||
3 FIGURE 7 100 COMPARATIVE OSPM RESULTS, RELATIVELY FLAT TERRAIN (PENETRATOR SIREN) | |||
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i Regression Of OSPM Comautations, Relatively Flat i 4 %.i !; m | |||
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d} 1. 3 . | |||
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! f.' L i lh 100 200 500 1,000 2,000 5,000 8,000 Distance From Siren In Feet | |||
~ _ . , .. . - | |||
FIGURE 8 COMPARATIVE OSPM RESULTS, SIIADOW ZONE (BANSilEE SIREN) ' | |||
' ~ | |||
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70 dBC Criterion Level | |||
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d. | |||
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4 | |||
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+ | |||
m ".! ! u im l I j | |||
g!'''.L ' q i s ' | |||
C 30 | |||
' E ' 2- - 2 l '' | |||
100 ' | |||
200 500 1,000 2.000 5,000 8,000 Distance From Siren In Feet | |||
y, 1 | |||
4 . | |||
t APPENDIX A l | |||
OSPM Topographical Profile Charts OSPM Topographical Input Data OSPM Siren Sound Pressure Level Inp.ut' Data OSPM Meteorological Ir.puti Data . | |||
l OSPM Siren Sound Pressure Level Outpul Data | |||
. g :, . . . , . - a < . . | |||
r* | |||
% J e* . | |||
* g -4 | |||
.,,,,4 4 | |||
. -4 s. | |||
. 2.m a:r ,. , m-I | |||
+ # | |||
NE'+',l} _''[** '* 9[] . [* / C . ... s r < | |||
s | |||
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e | |||
;.I [;.y' . . , . 'h",'.*: | |||
5I | |||
, ,,'.4.*#*,,,", ',.,5. | |||
, [ ;., -[f . ., l$ . g ~ ,' ' , | |||
a j 'l ,' , | |||
*r* .. | |||
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i | |||
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p R N e 4 . | |||
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. . . . . . . . , . ~ , . . . . . | |||
,a. ,., .y.a..w, w, .. _ | |||
., pg | |||
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- . 's. ._.y.. . | |||
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p, a , . , .4,..g, , ,, | |||
w | |||
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sw- ra. nf.mm a.; | |||
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c.n? .;. 9 c. .c.k.1 | |||
~* | |||
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*$! $b* 8 | |||
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: f. tar :. phy. ~ ,: .% .& ..* . | |||
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e e'. /* ,e # e . | |||
3.. ' ' | |||
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.h ~ , , k ,,, ,' : '."- | |||
, . l, r ~} _' t's * | |||
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r,'t;, . ' ~. ' | |||
-- - .~ -h l l I t 0 | |||
em l | |||
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uds | |||
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e | |||
.~-g' C b? i wL a 4 % | |||
C' N ,a .bk_ | |||
l t. | |||
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l i u | |||
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b | |||
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97 2000. 180.00 455.00 SOFT 0. 30 0. O. | |||
; 38 4000. 190.00 675.00 SOFT 0. N0 0. O. | |||
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45 2000. 315.00 6 5.00 SOFT 0. ND 0. O. | |||
46 4000. 315.00 635.00 SOFT 0. NO 0. 9. | |||
47 6000. 315.00 625.00 SOFT 0. NO 0. O. | |||
a8 2000. 315.00 620.00 SOFT 0. NO 0. 0. | |||
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52 2000. 292.50 635.00 SOFT 0. NU 0. O. | |||
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1 iO ! w i ssis!EAN ELEC'F! ::.m sr D.C.COOr, ANS SIREN 8202-5ArihEE SIREN 52bND LEVELS IN DEC UN E.; ."ET CCNDII!CN 1 DISTANCE IN' FEET | |||
*II.'!UTH 500. 10v0. 2000. 4000. a000. S000. 12N0. | |||
E 99. 58. 75. 67. 62. 53. 44 | |||
. EhE 99. 58. 75. 67. 42. 49. 49. | |||
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NNE 99. SE. 75. a7. ::. 59. 53. | |||
N 99. S8. 75. 67. 62. 53. 44. | |||
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s5W 99. S7. 75. 60. 42. :2. 23. | |||
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SSh 99. 52. 75. 61. 50. ' 40. 23. | |||
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INDI ANA a clC8isAN ELEC?slC .0MF. ANt D.C. COOL AN5 SIREN 8202-EAN3 HEE j NOIEE SOUSCE F0WER LEVEL INFUT INDEI SOURCE ESA DEC :1.5 3; 125 250 500 10M 2000 40 % E000 :hZ: | |||
1 51AEN XC202 150.s !!!.5 0.0 e.v '). 0 r 0.0 147.0 149.) *i.0 !!b.0 !!!.o 10= 0.0 t0: e0 IS= 564.90 HE!5kT A50VE 5R00hD= 49.00 g, ., . j I | |||
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INDI ANA & MICH15AN ELECTRIC COMPWf 0.C.CD0K AN3 SIFEN 8202-BAN 5 HEE METEORCLCSICAL !NPUT CCNDITIONS fil= 15.24 METERS H2= 45.72 METERS 1' | |||
WIND WIND EFEEDtMFS) TEMFERATURE(C) SELATIVE BAROMETRIC l | |||
REAR SEAECN MONTH DATE HOUR 51RECTION H! H2 H1 H2 HLMIDITY FRE55UREtMM 0F HSs 1 1992 S : 23 12 254.0 1.1 2.2 15.7 21.4 22.0 752.0 l | |||
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SHG 9500C i01!?93 IN!3EA3NINS 0!!!YN03 !O u?94351 F3iiH1 03 d01NI 0151YW03 63 WIN 9 F3I3HI 11d3 d3N31sV110N 0651s02li0NS 035183DION UDd' 50RV33 0351H31I]'N iE Z000* :;'cO 'ZE F S0U O' NO 0* G* | |||
7 | |||
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20M' ZCZ*EO ?ZE*00 S0U 0* NC O' O' 80 81 )000' ZOZ*EC 9ZE*00 S0U 0* Nlf O' O' I | |||
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0* O' i 81 9000' Z0Z'50 9ZE*M 50B O* ND iZ000' ZOZ*EO 9ZE*00 SDU O" NO O' 0* | |||
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i 61 9M0' IEL*M 9tO'00 3031 O' ND 0* O' | |||
!l 6B iZ000* 1 L*EC 990'00 SDU O' 40 0* 0* | |||
66 G00* LIE *00 9!E*00 SDU O' 40 O* O' 100 1000* LIE *00 9 0*00 SDU O' NO 0* 0* | |||
1 101 Z000* LIE *00 ??E 00 SGU 0* NO 0* O' | |||
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[j 109 G00* liZ'GO 9IE*00 SDU 0l ND 0* O' | |||
! iof 1000* 11Z'50 920*00 . 50U 0* ND 0* O' IOB Z000' !iZ*EO oIE*00 SDU 0* ND O' 0* | |||
106 t000* liZ*EO 9IE*00 SDU O' NO 0* 0* | |||
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! liO 9000* liZ*EO 9tE*00 SDU O' ' NO O' O' j III 9000* liZ*M SSE*00 30B O' NO O' A' lIZ IZ000' llI*;0 56E'00 3OU 0- ;35 g000-- ec;- | |||
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* t lit 80!Et* !E*oC ;M* 00 5DU " :35 100* I;M' | |||
* liS IEL;;* Z76';i EM* 00 30B G* 633 !W' iM | |||
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:ni; EECLND FDLIME !NIEst.ENIN9 013'nNCE 'O H!iHEET -iiiU OF F0!NT O!5TA % tlEAR!NS *E!EHT TtFE FENETFA!!29 OB5"LCT!DNS 095TRL*0 TION F90? 30". CE 2EE7;;0**:N' r. | |||
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?! 2NO. !!7.50 625.09 50FT 0. NO 0. O. | |||
,? 40' 9. !;7.50 625.00 : .' O. NO 0. O. | |||
40 3000. 227.50 625.00 SOFT 0. N0 J. 0. | |||
41 3000. 337.50 635.00 SOFT 0. NO 0. O. | |||
42 12000. !!7.50 650.00 SOFT 4 YE3 10950. :50. | |||
43 500. 315.00 635.00 SOFT 0. 30 0. 0. | |||
14 1000. !!5.00 630.00 SOFT 0. NO 0. O. ( | |||
85 2v00. !!5.00 d5.00 50FT 0. ND 0. 9. | |||
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48 SOM. 315.00 d5.M SOFT 0. 40 0. 9. | |||
49 1 000. !!5.00 520.00 SOFT 0. rE5 10300. 360. | |||
50 500. 292.50 6!5.00 SOFT 0. ND 0. 0. | |||
51 1000. 292.50 6:5.00 SOFT 0. NO 0. 0. | |||
52 20iA. 292.50 625.v0 SOFT 0. NO 0. ~ 0. I' 53 2000. 292.50 620.00 SOFT 0. NO 0. 9. | |||
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Latest revision as of 09:28, 19 December 2021
ML20210D941 | |
Person / Time | |
---|---|
Site: | Cook |
Issue date: | 03/20/1986 |
From: | Shafer W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
To: | Dolan J AMERICAN ELECTRIC POWER SERVICE CORP., INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
References | |
NUDOCS 8603270097 | |
Download: ML20210D941 (2) | |
Text
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i MAR 2 0 8811 Docket No. 50-315 Docket No. 50-316 ( American Electric Power Service Corporation , Indiana and Michigan Electric Company ATTN: -Mr. John E. Dolan Vice Chairman Engineering and Construction 1 Riverside Plaza Columbus, OH 43216 Gentlemen: We have received the attached Federal Emergency Management Agency (FEMA) letter dated February 25, 1986, and associated evaluation of the Alert and Notification System for the Donald C. Cook Nuclear Power Plant in Stevensville, Michigan. The evaluation states that, based on the engineering design review, and the results of the demonstration of the system conducted on August 3,1985, FEMA has determined that the Alert and Notification System installed around the Donald C. Cook Nuclear Power Plant, meets'the guidance of NUREG-0654/ FEMA-REP-1, Revision 1, and FEMA-43 (now published as FEMA-REP-10), and that there is reasonable assurance that. the system is adequate to promptly alert and no.tify the public in the event of a radiological emergency at the site. The caveat on l the Alert and Notification System contained in the 4_4 CFR 350 finding of September 28, 1983, is now removed. In accordance with 10 CFR 2.790 of the Comission's regulations, a copy of this letter and the enclosure will be placed in the NRC's Public Document Room. Sincerely,
- " Original signed by W.D. Shafer*
W. D. Shafer, Chief I Emergency Preparedness and Radiological Protection Branch
Attachment:
As stated l l See Attached Distribution l RIII III RI) db
#Df hnell/jlk P 11 ips r U 8603270097 86032 b 1 PDR ADOCK O g5
1 o-American Electric Fewer Service 2 MAR 2 0 RYi Corporation Distribution cc w/ attachment: W. G. Smith, Jr. , Plant Manager DCS/RSB (RIDS) Licensing Fee Management Branch Resident Inspector, RIII Ronald Callen, Michigan Public Service Cornission EIS Coordinator, USEPA Region 5 Office Nuclear Facilities and Environmental Monitoring Section L
- Taylor Letter enly: Stallo l Federal Emergency Management Agency $$m !
*k 'k [
Washington, D.C. 20472 h" n J eppler l oteept gis ,_.-, GCunningha FEB 25 999g l
,. fc T
W f Mr. Victor Stello, Jr. ;1% Acting Executive Director for Operations 4' U.S. Nuclear Regulatory Ccmnission FIL Washington, D.C. 20555
Dear Mr. Stello:
1 he Federal Emergency Management Agency (FENA) has empleted an analysis of ' the prmpt alert and notification system for the Donald C.. Cook Nuclear Power l Plant in Iake Township, Michigan. %is review has been empleted pursuant to FEMA rule 44 CFR 350; selected evaluative criteria and Appendix 3 in NUREG-0654/ FEMA-REP-1, Rev.1; and FENA-43, the " Standard Guide for the Evaluation of Alert and Notification Systes for Nuclear Power Plants" (now published as FENA-REP-10) . he enclosed report entitled " Donald C. Cook Nuclear Pcwer Plant Site-Specific Offsite Radiological Emergency Preparedness Alert and Notification System Quality Assurance verification" sumarizes the engineering design review, incorporates the results of the telephone survey of the public conducted ime-diately following activation of the alert and notification syst e on August 3, 1985, and confirms the adequacy of the applicable evaluative criteria frczn NURED-0654/FENA-REP-1, Rev.1, and FENA-43. Based on the engineering design review and the results of the telephone survey, FEMA has determined that the alert and notification syste installed around the Donald C. Cook Nuclear Power Plant satisfies the requirements of NUREG-0654/ FEMA-REP-1, Rev.1, and FEMA-43. herefore, there is reasonable assurance that the system is adequate to prmptly alert and notify the public in the event of a radiological emergency at the site. %e caveat on the alert and notification system contained in the 44 CFR 350 approval dated September 28, 1983, is now re-noved. Governor James Blanchard of Michigan has been advised of this approval. Sincerely, 80 e Samuel W. Speck-
' Associate Director State and local Programs and Support Enclosure MAR 3 1986 f)l 0 ! ^
DONALD C. COOK NUCLEAR POWER PLANT ,
, SITE-SPECIFIC OFFSITE RADIOLOGICAL' EMERGENCY PREPAREDNESS ALERT AND NOTYFICATION SYSTEM QUALITY ASSURANCE VERIFICATION il -
l. Prepared for
, , Federal Emergency Man &gement Agency Washington, D.C. 20472 Under Contract No. EMW-83-C-1217 4
l ll January 29, 1986 _ O z A pe n , m/ Uv v /V ./ Ld / / /
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TABLE OF- CONTENTS i I. INTRODUCTIO'S 1 4 A. Identification 1
- l. Site Information 1
- 2. Governments Within The 10-Mile Emergency Planning Zone 2 B. Scope Of Review 2 ll 1. Emergency Plans For Offsite Response Organizations 2
, 2. Alert And Notification System Design Report 3
- 3. FEMA Evaluation Findings 3 s II. FINDINGS FOR EVALUATION CRITERION E.6 4 A. Administrative Means Of Alerting 3 (E. 6.1, FEMA-43 ) 5 B. Physical Means Of Alerting (E.6.2, FEMA-43) 5
- 1. Sirens (E.6.2.1, PEMA-43) 5
, 2. Special Alerting (E.6.2.4, FEMA-43) 21 ll III. FINDINGS FOR EVALUATION CRITERION N.1 22 i
IV. FINDINGS FOR EVALUATION CRITERIA E.5 , F.1, N. 2 , N. 3 , AND N. 5 31 REFERENCE LIST. 32 4 APPENDIX A: OSPM Topographical Profile Charts OSPM Topographical Input Data OSPM Siren Sound Pressure Level Input Data OSPM Meteorological Input Data OSPM Siren Sound Pressure Level Output Data - APPENDIX B: Sample Size Determination I L
I Donald C. Cook Nuclear Power Plant Site-Specific Offsite Radiological Emergency Preparedness Alert And Notification System Quality Assurance verification State Of Michigan Berrien County
^
j I. INTRODUCTION A. Identification
'! 1. Site Tnformation i
The Donald C. Cock Nuclear Power Plant is located in Lake Township, Berrien County, Michigan, approxi-
.' mately 11 miles south-southwest of the center of l' Benton Harbor, Michigan. The site encompasses about
] 650 acres along the eastern shore of Lake Michigan, l with approximately 4,350 ft of lake frontage, and extends to an average of 1-1/4 miles eastward f rom the lake.1 r Approximately 50% of the area within a 10-mile radius
- of the plant site is comprised of water. A large 9 portion of the remaining area is devoted to agricul-d' ture. Major agricultural products are apples, cherries, grapes, peaches, feed grains, livestock, l and dairy products.1 Within the Donald C. Cook Nuclear Power Plant's 10-mile-radius emergency planning zone (EPZ) , there are two major roadways, Interstate Route 94 and the Red Arrow Highway. The Andrews University Airport is i approximately 10 miles east of the plant on the 1
1 l i t
4 southwest edge of Berrien Springs, and Warren Dunes State Park is located along the lake approximately 6 miles south of the plant site.1 Recreational activities within the Donald C. Cook Nuclear Power Plant EPZ take place primarily in the summer along the beach areas of Lake Michigan and at Warren Dunes State Park. The park is equipped with camping f acilities as well as lake shore f ront beach areas.1 l' ji 2. Governments Within The lO-Mile Emeroency Plannino irme The EPZ for the Donald C. Cook Nuclear Power Plant is defined by a 10-mile-radius circle with the plant as j the center point. The EPZ is located entirely within the State of Michigan in Berrien County. An estimate of the- population within the Donald C. Cook Nuclear Power Plant EPZ is approximately 69,000 persons.2 According to 1980 census data, the largest population concentration within the Donald C. Cook Nuclear Power Plant EPZ is in the twin cities of Benton Harbor - St. Joseph with a population of 1 . 14,707 persons and 9,622 persons, respectively.3 2 B. Scone Of Review g 1. Emeroency Plann For Off site Response Oroanf rations All appropriate offs'ite radiological emergency plans and preparedness site-specific to the Donald C. Cook Nuclear Power Plant have been reviewed by the Federal Emergency Management Agency (FEMA) Region V and the Regional Assistance Committee. 2
~
l
*.m-- * - - - - , -- - - -g w- e-+ ,e--- + mew ------- - --,-%--v+ - -% i,--a eg--e- -------w* * f' '-P'-*'**-"'"'-r * - "-' -
- 2. Alert And Notification System Desien Report The physical means established for alerting the
- public within the Donald C. Cook Nuclear Power Plant EPZ are documented in the following: . Indiana and Michigan Electric Company, " Donald C.
Cook Nuclear Plant Prompt Public Notification
~
System, FEMA-43 Design Report," November 1, 19844 (hereinafter referred to as the Design Report).
! 3. FEMA Evaluation Findinas The offsite radiological emergency plans and preparedness site-specific to the Donald C. Cook l Nuclear Power Plant received FEMA approval under Title 44 of the Code of Federal Reculations, Part 350 (44 CFR 350), conditioned upon verification of the adequacy of the public alert and notification system, , as documented in the:
i '
. Letter to the Honorable James J. Blanchard, '
- (-
1 Governor of Michigan, signed by Louis O. Giuffrida, Director, FEMA, dated September 28, 1983;5 and the i
. Letter to William J. Dircks, Executive Director for Operations, U.S. Nuclear Regulatory Commission, signed by Dave McLoughlin, Deputy i
Associate Director, State and Local Programs and Support, FEMA, dated September 28, 1983.6 3
II. FINDINGS FOR EVALUATION CRITERION E.6 l The Design Report describing the alert and notification
)
system for the Donald C. Cook Nuclear Power Plant was reviewed against evaluation criterion E.6 and Appendix 3 of NUREG-0654/ FEMA-REP-1, Revision 1, " Criteria for Pre-paration and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" , (hereinaf ter ref erred to as NUREG-0654/ FEMA-REP-1, Rev.
~
1). This evaluation criterion states: l p Each organization shall establish administrative and physical means, and the time required for
- notifying and providing prompt instructions to 1 the public within the plume exposure pathway I
Emergency Planning Zone. (See Appendix ~3.) It-shall be the licensee's responsibility to demon-strate that such means exist, regardless of who a' implements this requirement. It shall be the p' responsibility of the State and ments to activate such a system.gocal govern-l i The bases for review against this evaluation criterion were l the corresponding acceptance criteria of FEMA-43, " Standard -l Guide for the Evaluation of Alert and Notification Systems
.for Nuclear Power Plants"8 (hereinafter referred to as j! FEMA-43). This quality assurance verification review was I
performed to make a determination of alert and notification system adequacy prior to conducting a demonstration of this ' ~ system for.the Donald C. Cook Nuclear Power . Plant on August i 3, 1985. Based upon this quality assurance verification review and public survey results, International Energy Associates Limited concluded that the design and implementation of the alert and notification system for the Donald C. Cook Nuclear Power Plant and its supporting procedures conformed 4
l sufficiently to the acceptance criteria, as stated in l FEMA-43, for evaluation criterion E.6 of NUREG-0654/ FEMA- l REP-1, Rev.1, to support a FEMA finding that the alert and notification rystem is adequate. This portion of the quality assurance verification review evaluates the Donald C. Cook Nuclear Power Plant's alert and notification system against FEMA-43 acceptance criteria
~
in the following areas: the physical means of alerting and 7 the special alerting methods. 7 A. Administrative Means of Alerting (E.6.1, FEMA-43)
,. The administrative means of alerting for the Donald C.
Cook Nuclear Power Plant were evaluated by FEMA and the Regional Assistance Committee in their determination of adequacy under 44 CFR 350.5,6 B. Physical Means of Alerting (E.6.2, FEMA-43) As described in Section 2.2.2.1 of the Design Report, the physical means of alerting for the Donald C. Cook i Nuclear Power Plant EPZ consist of 49 fixed siren units.
- 1. Sirens (E.6.2.1, FEMA-43) l The Donald C. Cook Nuclear Power Plant siren alerting system, as submitted in the Design Report, was evaluated in accordance with the design evaluation
; methodology detailed in " Analysis of Siren System Pilot Test. "9 '
5
. _ _ . - . . . = _ . . _ - . .- -_. .. . - . - .
i i The siren system as analyzed consists of 49 sirens: 9 Alerting Communicators of America (ACA) Hurricane (sometimes referred to as i Penetrator-50) sirens (130 dBC); 24 ACA Penetrator-10 sirens (123 dBC); and 16 ACA Banshee sirens (116 dBC) . Anechoic-chamber measured octave band sound pressure spectrums (supplied by the licensee) were used to verify the rated output of the ACA Penetrator-10 and the ACA Banshet sirens at 125 dBC and 115 dBC, respec-tively. The more conservative values of 123 dBC for the ACA Penetrator-10 sirens and the confirmed j' manufacturer's rating of 115 dBC for'the ACA Banshee sirens are used in this evaluation. Test data for the ACA Hurricane sirens were disclaimed by the manuf acturer owing to the physical limitation of the test facility.10 I Routine siren testing procedures and operability for
- 3. the Donald C. Cook Nuclear Power Plant siren warning system have been reviewed and determined to satisfy
, FEMA-43 operability requirements.
I 1 The Donald C. Cook Nuclear Power Plant siren alerting system design follows the 10 dB loss per distance doubled attenuation rate as recommended in NUREG-0654/ FEMA-REP-1, Rev.1, for situations in which special conditions are absent. No additional corrections were made' for site geographical features, nor were corrections applied to reflect site meteorological conditions. 6
- -- - ._ - . - _ . - - .. . - - . - - . - _ - . . - . - - . ~ -
This evaluation is conducted by ascertaining the adequacy of the design procedure -- the 10 dB loss per distance doubled attenuation rate without any corrections -- in the presence of site-specific topographical and meteorological conditions through comparisons with the Outdoor Sound Propagation Model (OS PM) 9 results for specific sirens. Fourteen sirens,13 of which are depicted on thb U.S.
~
Geological Survey's Benton Harbor quadrangle map (see Figure 1 of this report), were selected for this quality assurance verification review. This selection (comprised of three ACA Hurricane sirens, four ACA Penetrator-10 sirens, and seven ACA Banshee sirens) is representative of the site-specific topo-graphical conditions around the more populated areas within the Donald C. Cook Nuclear Power Plant EPZ. Surf ace weather parameters, representativeo ' f site l prevailing summer daytime conditions, were used in the OSPM calculations. Appendix A of this report I contains OSPM topographical profile charts, OSPM topographical input, OSPM sound pressure level input, OSPM meteorological input, and OSPM sound pressure level output for each of the 14 individual OSPM siren runs. l To compare the acoustical coverage estimates of OSPM with the design procedure, the output dBC levels along each azimuth of the 14 analyzed sirens were ; classified into two categories according to terrain profiles : partially hilly terrain (minor obstruc-tions) and relatively~ flat terrain (generally un-obstructed line-of-sight) . In addition, a shadow zone category reflecting the influence of site weather conditions on the siren effective propagation 7
.c
_. . ___________..____..._____m _ _ _ _ _ . . . _ _ . . _ _m _ _ _ _ _ _ _ _ _ _ _ ____.______m_ _ _ _ _ . FICURE 1
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range was used. Regressions of dBC versus the logarithm of distance were performed for the siren types over the terrain and weather categories within 1,000 ft to 10,000 f t of the sirens. l The regression results of the OSPM siren sound pressure levels are presented in Figures 2 through 10 of this report. Also depicted is the 10 dB loss per distance doubled attenuation rate curve. Several general observations can be made concerning ] the siren range comparisons. First, the 70 dBC and I 60 dBC ranges for all siren types estimated by the 10 dB loss per distance doubled attenuation rate are l conservative with respect to OSPM results over flat and partially hilly terrains. Second, in the case of
- d. '
the smaller ACA Penetrator-10' and ACA Banshee sirens (which are mounted at 48-ft to 50-ft heights as
, opposed to the bigger ACA Hurricane sirens mounted 86 f t above the ground) , the acoustic shadow effect
( induced by the wind and thermal gradients is more
- 1 pronounced than that of the ACA Hurricane sirens.
This is because the gradients closer to the ground ] surface are typically larger than those higher up within the planetary boundary layer. Thus, the design procedure, when compared to the-results of the OSPM, yielded liberal 70 dBC and 60 dBC. ranges in the cases of the ACA Penetrator-10 and ACA Banshee sirens in the shadow zones and comparable ranges for the ACA Hurricane sirens. The regression results are sum-marized in the following table (which is presented af ter Figures 2 through 10) : 9
3 FIGURE 2 100 ~~ ~ COMPARATIVE OSPM RESULTS, SIIADOW ZONE (IlURRICANE SIREN)
. ;I j ^ .j;. ~
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!! Ihl 70 dBC Criterion Level For >
i ll .h! ll liI ! Ik I ! F
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. 2._ .
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.7 7 . . . ,
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p A" 2,000 llii;ll' Pe iliil!ll!Pl?';l!!!Tlill rsons /SglIll i l l I l I I I l \ (1
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REGRESSED RANGE (In Feet) Siren Type 70 dBC 60 dBC ACA Hurricane - 10 dB Rate 6,400 12,800 OSPM Results Flat Terrain >10,000 >10,000 ,. Partially Hilly 10,000 >10,000 Shadow Zone 7,100 >10,000 ACA Penetrator-10 10 dB Rate 3,900 7,800 OSPM Results } Flat Terrain 7,000 >10,000 Partially Hilly 6,000 >10,000 is Shadow Zone 3,300 5,200 ACA Banshee 10 dB Rate 2,250 4,500 OSPM Results i Flat Terrain 3,300 6,400 Partially Hilly 2,900 5,400 f Shadow Zone 2,200 3,400 j' The above assessment is supported by a comparison of individual siren coverages in terms of the area within the 70 dBC and 60 'dBC contours. For each siren type located on the U.S. Geological Survey's
. Benten Harbor quadrangle map, the area coverages of j 60 dBC and 70 dBC were numerically integrated. The l results are as follows:
l 4 l l 19 1 1
i
)
i AVERAGE AREA (In Square Miles) Siren Type 70 dBC 60 dBC ACA Hurricane 8.578 18.477 ACA Penetrator-10 3.845 12.095 ACA Banshee 1.070 3.488 Using these results, the following average effective radii are derived: 1 EFFECTIVE RADIUS (In Feet) Siren Tvog 70 dBC 60 dBC i ACA Hurricane 8,725 12,804 ACA Penetrator-10 5,841 10,360 ACA Banshee 3,081 5,563 l
- 1. These results show that the design procedures, namely the 10 dB loss per distance doubled. attenuation rate l without additional corrections, still yielded conser-vative 70 dBC and 60 dBC ranges for the Donald C.
] Cook Nuclear Power Plant EPZ.
The results of the individual OSPM runs were combined to generate a comprehensive. overview of the siren l
. sound pressure levels -over the Benton Harbor area as depicted in Figure 1 of this report. A surface inter-polation and contouring program utilizing the output results of the 14 sirens that influence the coverage in the area was used to generate the sound pressure level contour overlays. These contours account for 1
site-specific topographical and meteorological l
- 20 l
l l _ _ _ . .,_ _ _._, . . _ , _ . , _ . ._.,_.__,,,___m., , . , . _ , . _ . _ __ 6,m___, _ . . . _ . _ ,,,_.
effects and the logarithmically additive effect of-the seven omni-directional Banshee sirens. The results confirm what Exhibit B of the Design Report indicates: that each area with a population density l of 2,000 persons or more. per square mile is covered by siren sound pressure levels of 70 dBC or greater and all other populated areas are covered by siren sound pressure levels of 60 dBC or greater. ~ In conclusion, the Donald C. Cook Nuclear Power Plant siren alerting system is found to meet the specific ' design requirements of FEMA-43. j l ! i , 2. Special Alerting (E.6.2.4, FEMA-43) ' Sirens are the primary means of notification for the
! Donald C. Cook Nuclear Power Plant. The Design Report, in Section XI of Exhibit E, states that alert monitor receivers are used to alert schools, hos-pitals, and other institutions. Section XX states that law enforcement and fire services coordinate to
, extend public notification by sector, utilizing public address systems on emergency vehicles. Ac-cording to Exhibit G of the Design Report, parks, beaches, and recreational areas are notified by local authorities. 1 21
III. FINDINGS POR EVALUATION CRITERION N.1 l l On August 3,1985, the physical means (sirens) used to alert the population within the Donald C. Cook Nuclear Power Plant EPZ were demonstrated to satisfy the alert and notification aspects of 44 CFR 350.9 (a) . This demon-stration was conducted by using the methods specified in Section N.1 (a, b) .2 of FEMA-43.8 The results indicate that this portion of the alert and notification system evaluation conforms to FEMA-43 and NUREG-0654/ FEMA-REP-1, Rev. 1.7 i The August 3,1985, demonstration of the Donald C. Cook Nuclear Power Plant siren alerting system consisted of a l double activation of all sirens and a subsequent telephone survey to estimate the proportion of EPZ households actually alerted. The first siren activation was initiated at 1:00 p.m. (Eastern Daylight Time) . The second siren activation occured at 1:10 p.m. All sirens were reported operating during both activations. The telephone survey of EPZ residences began at approxi-mately 1:13 p.m. (Eastern Daylight Time) and was completed
, within 47 minutes.- This sureey was conducted by 38 telephone interviewers, each with a separate WATS line and computer terminal.
l The universe of households to be surveyed was determined by establishing a 10-mile-radius circle around the latitude and longitude of the plant. The sample incorporated a sorted master list of approximately 2,500 households (addresses and telephone numbers) believed to be'within the Donald C. Cook Nuclear Power Plant EPZ. 22
A sufficient number of replicated subsamples were developed from this master list to ensure that the required number of telephone calls would be made, i.e. , to establish the pro-portion of households alerted to within a 5% precision at a 95% confidence level. The method for sizing the sample to achieve this result is described in Appendix B of this r eport. The questionnaires for this telephone survey are included. as Figure 11 of this report. Although Spanish interviewers were available, no Spanish interviews were conducted. As part of the telephone survey, a total of 285 households believed to be within the Donald C. Cook Nuclear Power Plant EPZ were contacted, and the responses were collected in an automated data base. Of this group, 71 respondents it stated that they were not alerted. However, before running the final tabulations, all of the addresses and cross streets obtained during the interviews were-checked on maps I to validate household locations. Of the 285 households, four were found to be outside the EPZ. Therefore, data i were tabulated on the 281 respondent households that were located within the EPZ. Respondents at 29 of these house-holds had been away from home at the time of the siren alerting system demonstration and, therefore, were not i included in the alerting analysis. Of the remaining 252 I households, 80.2% (202) indicated that they had heard the siren (s) during the demonstration. By using the estimated i number of households within the EPZ (21,568 from Reference ., 2) in the confidence interval expression in Appendix B of this report, an estimated 95% confidence interval for the proportion of the total EPZ population alerted that ranges f rom 74.8% to 84.6%' can be derived. In other words, at the 95% confidence level, between 74.8% and 84.6% of the house-holds within the Donald C. Cook Nuclear Power Plant EPZ would have reported being alerted by the siren alerting system. l 23
l FIGURE 11. Chilton Research Services Study #9047 Radnor, Pennsylvania August 3,.1985 0$1B#3067-0103'(FEMA 9/85) FEMA NUCLEAR POWER PIANT ALERTING AND NOTIFICATION SYSTEM: PUBLIC TELEPHONE SURVEY D.C. Cook Time Began AM PM Interview # (1-3) Time Ended AM PM Zip Code (6-10) Sample Type (11)
! RECORD BEFORE DIALING -Telephone #
-l (Area Code) (Exchange) (Number) (12-21) INTRODUCTION: Hello, =y name is . We're calling households long distance
, from Chilton Research Services as part of a survey. This survey is sponsored by The Federal Emergency Management Agency (FEMA) of the United States Government.
Your answers are voluntary and will be kept strictly confidential. t
- 1. First of all, is this (REPEAT # DIALED)?
l Yes 1 ~{ '! TERMINATE AND DIAL AGAIN No 2
- 2. As you may or may not know, there was a test of the public warning / alert notification
, system for the D.C. Cook Nuclear Power Plant. Did you, or any other member of this household, hear the sirpn/ warning signal from this test today?
22-
, SKIP TO Q. 4 Yes 1 SKIP TO Q. 4A No 2 Heard from CONTINUE another 3 source ASK IF ANY OTHER HOUSEHOLD *,* 0" MEMBER IS MORE KNOWLEDGEABLE l
24 l
FIGURE 11 (CONTINUED)
- 3. What did you or your household hear? (D0 NOT READ. CIRCLE ALL THAT APPLY)
(23-25) A siren , 1 SKIP TO Neighbor told me 2 Q. 4 Other family member told me 3 Other (SPECIFY) 9 CONTINUE Don't Know Y
, 3a. Did you hear . . . (RIAD LIST. CIRCLE ALL THAT APPLY)
(30-32) A Siren 1 From a Neighbor 2 From Another Family Member 3 o Or by means of something else 9 (SPECIFY) . 1 DO NOT READ Don't Know Y 4 (IF " HEARD EMERGENCY SIGNAL ** ASK Q. 4 BELOW; ' OTHERWISE SKIP TO Q. 4A) { Were you at home or away from home when you heard the siren signal? 37-SKIP TO Q. 5 Away From Home 2 a 25 l
FIGURE 11 (CONTINUED) 6A. (IF "DID NOT HEAR EMERGENCY SIGNAL") i Were you at home around 1:00 this afternoon? 36-Yes, 1 No 2 Don't Know Y
- 5. Has your household ever received information which tells you what to do in the event of a "real" emergency at the D.C. Cook Nuclear Power Plant. This white booklet with burgundy and grey letters titled, " Emergency Planning in Berrien County" was mailed to you this month f rom the Cook Energy Information Center. Do you remember receiving this information?
41-Yes 1
, No 2 Don't Know Y
, 4. Because we need to d'eter=ine whether or not you live within the 10 mile Imergency
Planning Zone of the D.C. Cook Nuclear Power Plant, would you plesse give me this address? (PAUSE FOR ANSWER)
ADDRESS: i and the nearest intersection (or cross street) to this house. Also, what community is this? . On behalf of Chilton Research Services and the Federal Emergency Management Agency, I would like to thank you for your time and for giving us this valuable information. t 26
l FIGURE 11 (CONTINUED) 1 82773Q SPANISH ! Chilton Research Services Study #9047 Radnor, Pennsylvania August 3, 1985 OMB #3067-0103 (FEMA 9/85) i FEMA NUCLEAR POWER PLANT ALFfTING AND NOTIFICATION SYSTEM: PUBLIC TELEPHONE SURVEY D.C. COOK Time Began AM. PM Interview i (1-5) Time Ended AM PM Zip Code o (6-10) Sample Type (11) RECORD BEFORE DIALING -Telephone # (Area Code) (Exchange) (Number) (12-21) INTRODUCCION: oj Buenos dias (noches). Estamos llamando residencias para larga distancia de Chilton heaarch Services como parte de un estudio. Esta esrudio es patrocinado por la Agencia Fedaral de Emergencia (FEMA) del gobierno de los Estados Unidos. Sus repuestas son voluntarias y se mantendran en confianza estricto.
- 1. Primero, llame el numero (RIPEAT # DIALED)?
7' Yes (Si) 1 1. TERMINATE AND DIAL AGAIN No 2
- 2. Como, Ud. puede saber o no, habia una prueba del sistema de alerta para D.C. Cook.
Oyo Ud. , o algun miembro de su familia, un senal de alerta de esta prueba de hoy? 22-SKIP TO Q.4 Yes Si 1 i SKIP TO Q. 4A No 2 Heard from CONTINUE 3 source (de otra manera). ASK IF ANY OTHER HOUSEHOLD ,* " MEMBER IS MORE KNOWLEDGEABLE 27
FIGURE 11 (CONTINUED)
- 3. Como Ud. supo de es ta senal de emergencia? (D0 NOT READ. CIRCLE ALL THAT APPLY)
(23-29) siren 1 SKIP TO neighbor told me i 2 Q. 4 other family membe.r told me 3 Other (SPECIFY) 4 CONTINUE Don't Know Y 3A. De que manera supo . . . (READ LIST. CIRCLE ALL THAT APPLY) (30-36) de Sirena 1 de un vecino 2 de algun otro miembro de familia (0 de otra manera) 4 (SPECIFY) DO NOT READ Don't Know (No sabe) Y ( . 4 (IF " HEARD EMERCENCY SIGNAL" ASK Q. 4 BELCM; OTHERWISE SKIP TO Q. 4A) l Estaba en casa o fuera de la casa cuando Ud. supo de esta senal de emergencia? 37-Home 1 SKIP 70 Q. 5 Away from 2 i home l 28
.l
FIGURE 11 (CONTIEUED) 6A. (IF "DID NOT HY.AR EMERGENCY SIGNAL") Estaba en casa a la una, esta dia? Yes 1 No 2 l Don't Know Y
- 5. Ha recibido Ud. en su casa instrucciones explicandole que Ud. debe hacer en caso de una emergencia "verdadera" a la planta nuclear D.C. Cook? El librito con letras de marron y gris es llamado, " Emergency Planning in Berrien County", y habia enviado por correo a Ud. durante esta mes, del Cook Energy Centro del Informacion. Se acuerda de recibir esta informacion?
- Yes 1 l No 2 Don't Know Y
- 6. Por razon deteminar si Ud. vive o no vive dentro de la limite de 10 millas de La Zona de Planificacion de Emergencia. Por favor decirme la dirrecion de la casa que esta? (PAUSE FOR ANSWER)
ADDRESS: I y que es la interseccion mas cerca de su casa o calle principal? i y en que comunidad vive Ud.? I Por la compania Chilton Research Services y la Agencia Federal de Emergencia, quisiera agradecer a Ud. por su tiempo y para darnos esta informacion importante. l 29
P The sample of 281 households was also used to estimate the proportion of households within the EPZ that stated they received information about what to do in a real emergency at the Donald C. Cook Nuclear Power Plant. Of these 281 households, 73.7% (207) responded that they had received the inf ormation, 22.8% (64) responded that they had not received the information, and 3.5% (10) did not know or refused to state whether they had received the infor-mation. Using the approach discussed previously, the following estimates for the entire EPZ population resulted (at the 95% confidence interval):
. Between 68.3% and 78.4% of the households would have reported receiving the information; . Between 18.3% and 28.0% of the households would have responded that they had not received the information;
{' and
. Between 2.0% and 6.4% of the households would not have known or would have refused to state whether , they had received the information.
9 In conclusion, no areas of the Donald C. Cook Nuclear Power l Plant siren alerting system were identified as needing enhancements. 30
IV. FINDINGS FOR EVALUATION CRITERIA E.5, F.1, N.2, N.3, AND N.5 Those -aspects of the alert and notification system addressing evaluation criteria E.5, F.1, N.2, N.3, and N.5 of NUREG-0654/ FEMA-REP-1, Rev. 1, have been reviewed by FEMA and found to be adequate to provide reasonable assurance that appropriate protective measures can be .taken
~
off site in the event of a radiological emergency. This conclusion is documented in letters to the Honorable James J. Blanchard, Governor of Michi@an, signed by Louis O. Giuffrida, Director, FEMA, dated September 28,1983;5 and William J. Dircks, Executive Director for Operations, U.S. Nuclear Regulatory Commission, signed by Dave McLoughlin,
; Deputy Associate Director, State and Local Programs and Support, FEMA, dated September 28, 1983.6 In these letters, the Donald C. Cook Nuclear Power Plant received FEMA approval under 44 CFR 350, conditioned on an ultimate approval and verification of the public alert and notifi-cation system as called for in NUREG-0654/ FEMA-REP-1, Rev.
1. 4 I l 31
l 1
)
REFERENCE LIST
- 1. Indiana and Michigan Electric Company. 1982. " Donald C.
Cook Nuclear Power Plant updated final safety analysis report." July 1982.
- 2. Donnelley Marketing Information Services. 1985. "American profile." July 11,1985.
- 3. U.S. Department of Commerce, Buretu of the Census. ' 1983.
1980 census of population. Volume 1, Chapter A, Part 1,
" United States summary. " April 1983.
- 4. Indiana and Michigan Electric Company. 1984. " Donald C.
Cook Nuclear Plant prompt public notification system, FEMA-43 design report. " November l',1984.
- 5. Federal Emergency Management Agency. 1983. Letter to the Honorable James J. Blanchard, Governor of Michigan, signed by Louis O. Giuffrida, Director. September 28, 1983.
- 6. Federal . Emergency Management Agency. 1983. Letter to William J. Dircks, Executive Director for Operations, U.S.
Nuclear Regulatory Commission, signed by Dave McLoughlin, Deputy Associate Director, State and Local Programs and Support. September 28, 1983.
- 7. Nuclear Regulatory Commission and Federal Emergency
) Management Agency. 1980. " Criteria for preparation and evaluation of radiological emergency response plans and 1-preparedness in support of nuclear power plants."
NUREG-0654/ FEMA-REP-1. Revision 1. November 1980. t 8 .' Federal Emergency Management Agency. 1983. " Standard guide for the evaluation of alert and notification systems f or nuclear power plants. " FEMA-43. September 1983.
. 9. International Energy Associates Limited. 1983. " Analysis of siren system pilot test." IEAL-333. November 2,1983.
- t 10. Biersach and Niedermeyer Company. Letter from James E.
Biersach, President. Subj ect: Manufacturer of ACA Penetrator-50 siren disputes test result interpretation by Acoustic Technology Incorporated and supplies adjusted test results. (No-date). i 32 l
3 FIGURE 7 100 COMPARATIVE OSPM RESULTS, RELATIVELY FLAT TERRAIN (PENETRATOR SIREN)
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~ _ . , .. . -
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100 ' 200 500 1,000 2.000 5,000 8,000 Distance From Siren In Feet
y, 1 4 . t APPENDIX A l OSPM Topographical Profile Charts OSPM Topographical Input Data OSPM Siren Sound Pressure Level Inp.ut' Data OSPM Meteorological Ir.puti Data . l OSPM Siren Sound Pressure Level Outpul Data
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