Text

Responds to NRC Re Emergency Planning Early Warning Alert Sys.Nrc Must Respond to Util Notification Sys as Outlined in Encl 810109,800828,0401 & 0318 Ltrs.Plan Is More than Adequate Given Accident Scenarios for Facility
	ML20009G690
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/13/1981
From:	Warembourg D; PUBLIC SERVICE CO. OF COLORADO
To:	Seyfrit K; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
	R-81184, NUDOCS 8108040554
	Download: ML20009G690 (1)
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- i July 13, 1981 Fort St. Vrain ypt No. 1

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9 Mr. Karl V. Seyfrit, Director

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g 611 Ryan Plaza Drbe, Suite 1000

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SUBJECT:

Fort S d elin Unit No. 1 Emergency Planning Early Warning Alert System i

REFERENCE:

NRC Letter Seyfrit to Lee Dated July 1, 1931

Dear Mr. Seyf rit:

In response to four letter of July l, 1981, we recognize the position setforth by 10CFR50 Appendix E with regard to an early warning alert system. As yo; are no doubt aware we have resisted and in many cases have taken sp:cific exception to criteria that was developed for water react rs without any justification or-technical basis for applying these same criteria to a gas cooled reactor and in particular' Fort St. Vrain.

The ee-warning alert system has been one of these areas.

As early as March,

1980, in our letter P-80083, we outlined our position on the early warning alert system, and in the submittal of our emergency response plan and the State's response plan our position on the early warning alert system was setforth.

This was followed by several other submittals in response to various letters and NUREG's all of which setforth our position to various requirements and guidance that had been published by the Nuclear Regulatory Commission concerning TMI-2 actions and associated emergency response.

We did not receive any response to these submittals and we finally requested a meeting with the emergency preparedness group and the special projects staff which was held on December 10, 1980, in Bethesda.

This meeting did not result in any resolution of our concerns although we were promised comments on our emergency response plan and the various issues that had been raised. We are still waiting for T fiol those comments.

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, Recognizing the futil'ty of some of our efforts we appealed dirctly to the Commission on Ja jary 9,1981 (P-81009) concerning the early warning alert system wherein technical ~ justification for relief from the early warning alert system was provided.

To date we have received no comments on our position.

It is our understanding that our various submittals have been turned over to Oak Ridge for evaluation, but as of this date we have received no response.

We believe we have been responsive to all Nuclear Regulatory Commission action items, and obviously because of our reactor concept have provided technical justification for various exceptions including the early warning alert system.

We are enclosing herewith a copy of P-81009 which contains several attachments which have been submitted to the Nuclear Regulatory Commission which setsforth our notification system.

The State RERP expands on the various methods which the State intends tc utilize for notificacion, radiological exposure control, and evacuation if necessary. Our public information brochures have been distributed to the population in the 5 mile EPZ, and we have held two (2) meetings for the general public in the EPZ to educate the people on the particulars of our emergency response plan.

We believe our plan is more than adequate given the accident scenarios for Fort St. Vrain, and we are not proceeding with any further activities concerning the early warning alert system until we receive a response to our various submittals.

Very truly yours i

f ho4/YM}

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Don W. Warembourg F

l Manager, Nuclear Production Fort St. Vrain Nuclea l

Generating Station DWW/alk i

cc: Brian Grimes,

Jim Miller George Kuzmycz i

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pumie service company =a c:Er:rsza January 9,1951 Fort St. Vrain Unit No. 1 P-31009 Dr. John F. Ahearne, Chairman U. S. Nuclear Regulatory Commission Washington, D. C.

20555 SUEJECT:

Fort St. Vrain Unit No. 1

(

Emergency Planning Early Warning Alert System

Dear Dr. Ahearne:

In our letter of Acril 1,1930, to Mr. Brian Grimes (P-30066) wnich is included as Attachmeat I,

we set forth our evaluation, ard justification for recucing the !?! and Ingestion Pathway distances from 10 and 50 miles resoectively, to 5 and 30 miles.

Our justification was accepted and tne EPZ and Ingestion Pathway was suosecuently reduced along with tnese of LWR's 250 MW and smaller.

In our transmittal of our emergency resconse plan on March 18, 1930, we took exception to the early warning alert system recuirement on

ne basis that Attach ent I clearly indicates that for a LOFC sccicent (03A #1) at Fort St. Vrain we do not exceed the Protective Action Guicelines (PAG's) at the exclusion area coundary for at least twelve (12) hours and ce not exceec the PAG's at ons (1) mile for at least twenty (20) nours.

These studies were made utilizing a persistent plume trajectory with Pasquill Category F meteorological concitions, and conservative source term estimates. (See excerpt of our res;cn:e from P-300S3 in Attacnment II.)

Following the initial suomittal of our emergency response clan, we su::mittee our revisec emergency response plan on August 23, 1950, and again we referenced tne tecnnical justification for eliminating tne early warning alert system.

(See excerpt of resconse from P-802SS in Attacnment III.)

l On Decemoer 10, 1930, we met with Mr. Brian Grimes along with other memoers of the emergency preparecness group anc NRR staff in an attempt to resolve some of the major issues of our emergency response pian as well as attemot to justify ne major differences in HTGR Tecnnology versus LWR tecnnology. We were unable to resolve any of tne major issues at the Decetter 10, 1930, meeting, primarily due to une fact that our transmittal letter (P-30258) was apparently misolaced and never received a staff review.

From all incications,

however, it was a:carent that Brian Grime's grot.o was not in a position to provice relief from tne early warning alert system.

i Recogniting that our initial evaluations (Attacnment I) were basec on extremely conservative source tern estimates, we performed an I'

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additional evaluation (see Attachment IV). While we removed some of the extreme conservatism of our initial EPZ stucy we have still maintainec a considerable factor of conservatism in our alternate scenario.

Based on this alternate scenario, the following conclusion can be summarized:

1.

The whole body garma dose cumulative over a thirty (30) day period for an LOF; accident at Fort St. Vrain never exceeds the PAG for shelter protection and never anarcaches the PAG for mancatory evacuation.

2.

The maximum whole body gamma dose for a 30 day period at the exclusion area is S00 millirem

ith the conservative eteorological plume trajectory.

(See Figure 2 of Attachment IV.)

3.

The most restrictive PAG, Thyroid Inhalation, is not exceeded at the exclusion area boundary for fifty (50)

hours, (see Figure 3 of Attachment IV), and the PAG for mandatory evacuation is never exceeded.

4 None of the PAG's for the closest population center, Platteville, is exceeded or even approached.

On the basis of the conservative estimates represented by either Attacnment I or Attachment IV, more than acecuate time exists to warn the general public and institute protective action.

Most certainly a 15 minute time limit cannot be justified, in light of the potential doses to the general public.

Based on the characteristics of Fort St. Vrain and the comparison of time for accidents to cevelop, we cannot see the justification for imoosing requirements ceveloped for LWR Technology upon Fort St.

' Vrain. We have been unacle, to cate, to obtain any relief based on the technical justification provided, and apparently the emergency preparecness group is not in a position to jucge the requirements based on technical merit.

Since we have been unable to obtain any definitive guidance from the review groups, we are appealing to the Commission for consideration of relief from the early warning alert system requirements, and maintain that our position set forth in Attacnment III provides adequate protection for the public in the EPZ.

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u Because of the significant delays we have already experienced, in octaining some definitive guidance, prompt consideration of this appeal will be greatly acpreciated.

Should you require any additional information, please contact Mr. Don Waremoourg, Manager, Nuclear Production, (303) 571-7436, Extension 200.

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Very truly yours,

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C. K. Millen Senior Vice Presicent CKM/dk:r.

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!= Reierence (1), ?-79205, we e= pressed our :::cer vi:h :he exten-sien of :he I?". := a ten (10) =11e radius and :he ingestica pathway

= a fif ty (50) =ile radius.

4e did sc: receive any ack:culedge-

=en: cf :his le::er, hewever, c.!anuarv 8, 1980, we ne: vi:h Messrs.

Roe, Ku:=yc:, and Willia =s in 3e:hesda :: discuss cur c::cerns. As a resul: ef :his zee:ing we agreed := evalua:e :he I?2 for Fc : St.

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~he attached evaluatic

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fer ?c : S:. 7:ain would be abou: five (3) si'.es and a c = parable in-ges:10: pathway wculd be abou: hir:7 (20) =iles.

he evaluatic is based c :::serva:ive es:i= aces of seur:e :er= releases, vers: case

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ce:e:::legical :::diti::s and entre =ely e serrative ?CI7 (?res:ressed C :cre:e i:.:.:: 7essel) leakage rates.

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.s. % _ es On the basis of cur evalua:icn i: is reques:ed tha: :he ?cr: S:. Vrain j

E?~ and inges:ica pathway be as:ablished as five (f) and hir:7 (30) niles, respectiysly.

sheuld be no:ei fur:her : hat we have been :hrough our bases vith a ta:a a::ic,a., s, and -e a.an c op_ete a cunens. wa.,a :ne s:a:e con-s cerning :he inherent safe:y of For: S:. Vrain versus a L'iR.

"e have also discussed cur positi:n wi h the local FD R represen:a:ives, and j

again have concurrence tha: :here is no justifica:ica for penali:ing

?ct: S:. Vrain wi:h water reactor cri:eria.

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3 you are aware we are in the pr: cess of finali:ing our Energency Response Plan wi:h the S:a:e as well as the energency planning f : s:a icn. Our i

4 planning is presen:ly based en :he s aller I?" and ingestion pathway expcsure radii and any changes in this cri:eria could have a significan:

i= pact en final acceptance of Our plans, both for the s:a:ica and :he i

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= a : RC let:er :o all reacter licensees da:ed '!cve=ber 29, 1979, a resues: as =ade for infc=atic: regardi=g esti=a:es for..eva.cuatice. of.varicus...

areas arcu=d nuclear pcuer reae:crs. 1;URIG-0296, I?A 310/1-73-016 specified, based upc: s: dies of a 1000 }r4(e) JR, :ha: the ere:gency planning scue (Z?I) for ple=e expcsure pa:hvay shculd be abou: 10 =11e radius abcut the plant and i

about 50 =ile radius for the ingestic: expesure pa:hway. 3c:h design basis accides:e with various active e:gineered safety features, and :he acciden:

release categeries of the Reac:cr Saf ety Study (*Jash 1400) were ec=sidered in de e=ica:1c= cf the specified distances. A fac:c: in establishing the about 50 mile radius inges:ics expcsure pa:hway is :ha: dis:ance has been evalua:ed a:d discussed i= de: ail in Chap:er 2 cf Facilities Safety Analysis Reper:s and i: Invire==en:al Repc::s.

"'he purpose of the evatua:ic: prese :ed herein is :o deter =ine :he app;cpria:e I?" dista=ces for ?cr: St. Vrai: which p cvide che ge=eral public equivalen: pro-tectio: :ha: veuld be afferded by the 10 =ile and 50 =ile I?"s for a sd "ar sited 1000 ET(e) L'JR.

A: the cese: cf :he investiga:ics i: vas believed :he principle differences vould be a s= aller source :er= due :o si:e, 330 ET(e) a: 39~. efficiency i

versus.1000 ir4(e) L'42, 2=d :i=e to perfor: e=ergency actions due to the rela:ively slew hea: p ra:a p cvided by the lar;e grap:ite core of a: h~'OR.

vas cc fi= ed by the detailed study : hat the FS*7 s-'er scurce te== coupled vi:h c 1 cue slev and gr: dual cere heatup characteris:ic cf the plant, did in fac: justify sharply re-duced I?I dis:ances for ?cr: S t. rai: and significantly 1c=ger ti=es :o perfors I

offsite e=erge:cy actic=s.

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Condue: ef Study

his sec:1ca describes the =e:hed=1cgy, pars =eter assign =en:s and assu=p-tices used i :he condue: of this EP study.

Sac:1cn 2.1 describes the acciden:

scenaric used as the basis for 757 I?: de:arsination as well as the description of wha: was assu=ed ec be a ec= parable accident scenario for the L',iR.

See:1cn 2.1 describes :he conserva:1s=s applied :c the accide== scenario.

See:1cn 3 describes :he conservaciva =atacrlogical conditicus assu=ed :o prevail during

he duratics of the I?: decem'-4ng event. Dese ec=putation =ethodology a d t

para =eter af.sig==ents and assu=ptict.J appear in Sections 4 and 5 respectively.

The appropriate I? discarces for 757 are presented in See:1cn 6.

Ccuelusions of this study are presented in Section 7.

2.1 Acciden

Scenario Tsed to Israblish the I?Z for FS7 The 757 Design 2 asis acciden: #1 (OEA #1) which was the only acciden: iden-tified and analy:ed in the ?SAR that results in extensive core da= age, was selected l

as the representa 1re scenario used to establish the plan:'s I?2. This even: is pos:ula:ed c be initiated by a "sen-=echanis:1c" per=anen: loss of forced cir-I culatic: while operating at full pcuer. The reae:c is scra==ed by the plant i

protectics sys:e= and all a::e= pts to res:cre forced circula:ica using the

=ul:1ple heat s # nia, circula: cts, and =c ive pcver for the circula:crs fail. ;ihen it becc._as.ppares: :c the plan: epera:crs :ha: :he loss of forced circula:icn is per=anen:, e.;. when res:cra:ic cf ecoling would cause stes= genersec ds= age, the pri=ary eccian: systa= would be depressuri:ed Oc s:crage in a ec ::clied

-'-ner through the heliu= purifica:ica sys:e=. The reserve shutdown system would r

'1 be cpera:ed af:er :his ini:ial period c assure an adecua:e shutdown argin.

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s 3ecause of tha la qs hea: si=k provided by the graphi:a cere, considerable

i=e is available to ini:ia:e pri=ary coolan depressurication and to res: ore forced d -~' a:100.

he FSV FSA?. specifies :he ti=e available := ini:da:e de-j pressuri:stica :o be 5 hcurs, which was la:e a= ended by PSC le::er ?-77050 1

dated Dece=ber 22, 1977 :s be 2 hcurs.

~he :-due:1on in :i=e was dus :o the re-evaluatic: Of the capability of :he heliu= purificatic: systen to process pr ary eccian: during the planned depressuri:ation and release of :he clean d

pri=ary ecolan: :o :he reae:or building ventila:ica s ack.

hus, the de-t pressuri:a:io cf :he P CV is new iniziated after 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and c:=pleted 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months later (or 9 heurs fr== :he cese: ef the acciden:).

The fuel is slev to heat up due :s the large heat sink provided by the core graphi:e. A peak average ac:ive core :e=pera:ure of 5400 ? is reached 1

abcut 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months after :he c se: of :he acciden:. A: this te=perature, the c re scrue: ural 1 :egri:7 and ge==etry are sc: c =pr==ised since the vaperi:a:1:=

e=rerature cf graphite is 6900 ?.

?cak ac:1vity released to the pri=ary ecolant, cc sidering decay, is reached abcut 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in:o :he accident.

? C7 cc :ai _e t in:egrity is =ain:sised :hrough hea re== val by the liner I

cooling systa= i :he "redis:ribu:ie: =ede" which =a=i=izes coeling in the : p ea> a..e.~.

v.u 1,eakage of pri=ary c olan: frc: :he ? GV is assu=ed to ec:ur a: a conser-va:1vely high leakage ra:e of 0.2~ of the pri=ary ecolas: inve : ry per day.

~he reac:Or building ventila:ien syste= =aisesins cc::inuous ven:ing and processing of the reac:c: building envire==en: a: 1.5 building volu=es/hr during the entire period of the accident.

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2.2 Conse vatis=O Anolied to CI!A Y1 Assu=otions

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"'he ISV FSAR DSA il (appendi:: J, page J.1-56) assu=zd an arbi::arily con-serva:ive and ncn-=echanistic es:i= ate of ?C27 leakage after :he intenzional depressurizaci:n by ass--* g :ha: the liner has failed cc=ple:ely (or does no: exis:) and culy concrete per=eability cen:rols the leakage. An in:ernal 5 psi pressure differen:ial vas assu=ed which purper:ed'.y gave a FC27 leale ra:e of

~5 3.33 = 10 frac:i== per hr (0. Z/ day). Reference was =ade :o ques:ica C.7 r

of A=end=en: No. 9 of :he 757 ISA'.t for the caleala:1cn of the per=ea:ica rate f:: the 737 ?C27 cencrete under these cenditions.

E=a=inatica of Ques:1cn 3.2 revealed si= ply the conclusion : hat a 5 psi positive differenzial pressure led := 0.2~./ day and 2 psi positive differential pressure led to 0.CS~/ day. Question 2.7 also did no p:cvide de:sils of the calcula:i:n of :he 0.3/ day ra:e. Hevever, censiderable detail and a deriva:Los was provided for the analysis cf leakage rate :ests at hi;h pressure.

"'he fol-icving equa:1:n was p:cvided(agn.14 en page 3.7-8):

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c =pressive s:ress in concre:e = 0 A = Face area of concrete, f:~

I = Concre:e :hickness, f:

Per=ea:i:n er high side pressure, psia

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Nu=erical values were inser:ed f== ? = 8!.5 psig 4.:h the assu=pti:n that 1?e 1

l vas appr:xi=stely equal ec ? in the folleving equa:ics (egn. 15 :n ne=: page):

7 l

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10 12.5 10

- 0.43 + 502 = 600 lb/ day (egn. 15)

The firs: 1:en to no:a is tha: the coefficien: for the second (lam {nne flev) :ers is in error which is =es: likely a single error in ::anscribing f:c= equa:1ca 14 :o 15 since equation 13 has the 9.1 x 10 coefficient.

Equa: ion 15 should read:

W = 1.13 x 10 x '000 in

+ 2.2 x 10 0000 (357.5~ - 12.5-)

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= 0.043 + 1445 = 1450 lb/ day (egn.15 revised)

The second i:e= is tha: :he i?/1Pe ter= has been dropped in going fram egn. 14 to egn. 15, which is significan if 1: is assu=ed tha: these equa: ices are appropria:e for evalua:ing :he leak race a: ?

=,5 psig. Including this fac:ct, 7

we find:

LIAK FATI Pressure ? 1 lb/dav

/dav (psig)

Iqn 14 15 15 Revised 14 15 15 Revised Given App Di A=end 9 Ques:ica D.2 l

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Sines ecua:1:n la is the appropriate equatien, ths 0.23/ day leak rate is c:nserva:1ve by a fac:c: of 200.

For purposes of this evaluatics, the historic 0.2 / day is assu=ed :o exis:

as an upper 11=1: ofalbpotentialconta=inatedpri=arycoolant leakag including per=eabili:7 :hrough :he PCRV concre:e. *his is judged to be conserva:1ve since the pri=ary coolan: vith any significan: activity is con:a1=ed within -he PC2V ce heliu= purifica:1cn ce=penents centained in ve11s within the PC2V.

For this study, the PC27 leakira:'e of 0.2 / day is c=nserva:1vely assu=ed 0 hours0 days 0 hours 0 weeks 0 months .

In to apply for :he :ctal acciden duration peried beg

' g a: : =

d actuali:7, this arbi::arily censervative esti= ate of ?C27 leakage would no:

Opply during the period of controlled PC27 depressuri:a:1cs or in the subsequen:

pos: depressurized period pric: :o an assu=ed liner failure. Ecvever, for con-serva:is= :his PC27 leak ra:e vill be applied " d'0:=17 for all :1=e.

2.2.2 Radienuclide Scurce Tens fer D3A-1:

As previcusly s:a:ed, the fuel within :he graphi:e core is sics :o hea:up during D3A#1. After about 7.5 heurs, some portices of the sicvly heating c re i

vill have reached the FSAR fuel par:1cle coa f g failure :e:pera:ure of 1725 C (2137*F).

C=ce reaching the FSAR fuel particle c= sting failure :e=pera:ure, the fission pr:due:s are assu=ed, for purposes of :his evalua:ica, := be released in a :i=e dependen: fashion nor-m ed per :he D -11.al.4 c re release assu=pticus.

For release to :he pri=ary ecolan: vi

d - the PC27, che TO -l!. N c=ndi:1:ns assu=e a release of ICC" cf schle gasea, 50% of the i= dines and 1% others.

Ccesis:en: with O -14344 release assu=ptions, 30" of :he iodines pla:ecut within the pri=ary coolan: sys:e= resulting in a depletica of the iodine to 25%

of core inven:::7 in tha resultan: ?C27 leakage :o the reac::: huilding at== sphere.

m %.ammemy

-

w mamme _

=*.,. e e --.**

e,,,

e,;ge

, t.en

=_4,g.,

,,_,ap_.f.

.___m

,,.._,,,_.y L

-. - - ~ = =

-.m

,~~

,_.,,_-,..,,r,

e Thesa T'J-14844 releases and pla:ecur assu=ptions are very censervative fc: an ETC2 but never :hs less have been u:ilized i :his evaluation.

This censerva:is= in release and pla:ecut assu=ptiens is particularly evident when the halogen release f:sc:icns esti=sted in the FS7 FSM (Appendi:e 3) are ec= pared

c !!D-II.844 values. The FSAR esti=stes a core halogen available leakage frac:1ca of 5.5% which is a fae:c: of 4.5 belev the TID-1/.844 effective core release fractica of 25%. The FS n fuel particle coating failure te=perature of 1725 C is also conservative ce= pared : :est da:s e'-"hting a core hea:up accident.

Figure

-l e

illustra:es :he =argin f: = :he :es: da:a :: :he 1705 C failure :e=pers:ure used I

in this evalua:icn. Aisc shcwa-is a NRC =cdel (%:?2G-0111) fe: ?lSO UC3 particle which is s' #'ar := the FS7 FSAR =cdel.

3.

Metec:c10cv 3.1 Si:e S=ecific Merec:clee-S e For: St. Vrain si:e =e:ecreicgy was descri'aed in de: in the 757 FSAR See:1cn 2.S.

he _ cst likely ecedi:1cn en an annual basis (Table.WII of FSAR) are v-; ds f:c= the N sec:c: cf the vind rose which occur 17: of the ti=e.

~~he =c s: likely stabili:y category is D (Table.Z 7 of FSAR), and the average vind speed a: 200 f:. eleva:1cn averaged ever all directices is 6.51 =ph (2.9 =/s) as gives i: Table !! cf the FSAR. Figure 17 in Section 2.S.3 cf :he r

/

v-11 exceed a given value.

FSAR gives the p:cbabili:y tha: :he dilu:icn fae:c:

1 Using the dashed curve shewn in Fig.17 (FSAR Sec. 2.5.3) which includes the effect of using ec ected a:e=c=eter vind veloci:y indicates : hap a dilutica fac:c:

-3 s/=, a: 590= will be exceeded caly 5" cf the ti=e (:he 5 of abcut 2.5x10 cut-off).

his cc rec:ed cut-off ec :esponds := stabili:y category F vith a vind speed of about 2.4 =/s.

"'hus the dilu:1cn fac:cr for s: ability category F vith 1 =/s vind speed will be exceeded censiderably less :han 5 cf the :1=e and represents a " vers case" type condi:1cn.

~

- - _ ~

3-

~ 32

!."AC S:aff Meteor:le:y fre= SER The ?cr: St. 7:ain Safety Evalua:ie Repor: (SER) (Ref. 4) prepared by cha

hen AIC s:aff includes the folleving =e:eorology and breathi=g ra:e assu=ptiens for acciden: condi: ion calculations a: :he L?': (16,000=)

3 Ti=e ?eriod Dilutien Facecr (s/=3) 3reathing Rate (#- )

s

-o Most Unfavorable S hrs.

7.Sx10 3.47x10~

Ncx: Mes: Unfavorable 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months 3.9x10 "

1.7fx10"

~

I :o 4 days 2.4x10 2.22x10"

~

4 to 30 days 7.Sx10 2.32=10

-7

-4 30 to ISO days 4.6x10 2.30x10

? lot:ing these dilu:ics fac:=r values agains: the ti=e period ever which

hey regrases: an average value (Fig. 3-1), 1: appears that :here is app:cxi=ataly

_L 4 :

ti=e dependence, as vould be expected, when allowing for vind =eander and change cf directics. This can be also be seen f:c= the equatices for averaging o

' OS'

he dila:ies fae::: for vind =eander ever a 22.5 see:or (5 = ~~x aC for ground e

level release) and for.an a==ual average, (Eq. 6, Sec. 2.3.3 cf ?SAR) both of which depend inversely c e, ( the vertical diffusica para =eter).

Since a: long

i=es the diffusics process is de=1:ated by rande= valk effects, c-is expec:ed a

_L

he pre,,:::ic al to :, and sc $ vould be p:Oportic al :s :.

3.3 Extent.icn of :~RC S 4"

W =a-aTeev to Other Dis:ances To derive the ti=e depende:ce of the d"

act: at ::her dis acces,

he ti=e dependence of :he NRC staff =e:ecrolcgy was esti=a:ed f::= a curve drav:

hr:ush the 16,000= points f::= the SIR as show: 1: Fig. 3-1.

his gave a

as,

dependence. Se reference pein: used for the c her dis:ances was the 3 hr. value, which was calculated fre= :(Shr)

_ 0"5 _ vi:h 5 = 1 =/s and

.5 eeu ya

: fc all distances :aken fer stabill:v. ca:ecery 7.

This is ecuivalent c 3

. - - -. - ~ ~ _

~

f

~-.

._.L.-..,

'. -. -... - ~ ~ -

.-a taking :ha shor: tar = dilucien fae:c: for 3:cund level relsass,

$=

'1

.~ : a G y3 h

as :he I hour value, and : hen extrapolating to S hours by :he fac:c g = 0.3.

S 0.493 Table 3-1 gives the values a: other ti=es ob:ained f:c. *(:) = c(3) vhere : is i= hcurs.

he breaching rates used were taken f c= the SIR and are given shove := 3.2.

3.4 Censerrative Metecroloer Assur :".ons Lis:ed belev are the ccuserva:is=s used in ob:aining the dilu:ics fac:c 1:

Table 3-1.

a)

4 ors: case type =e:ec clegical eceditic s (Categcry 7, u = 1 =/s) used are likely :o occur =uch less than 5% of the ti=e.

b)

De.~vash cendi:1cus are assu=ed :o persis: ever the entire ti=e.

c)

The affective stack height is :ake to be care (i.e., g:cund level release).

d) 3cuyancy effects of He rela:1ve to air are neglec:ed.

e)

Dilu:ica by the build.'. g vake is neglec:ed.

4 Oese Cc=uta:10: Methedcicev

? lune e=pesure deses were calculated using the ce=pu:e p cg-a= ~DAC (Ref. 1).

TOAC is a ec=puter p cgra= vhich utili:es analytical =ethods :o calcalate the ti=e-dependen: radiological i= pact due to cu:1:e c: accidental release of radic:uclides f:c= nuclear pcver plants or c hsr pc:ential sources of radicac:ivi:7 release.

~~he basic =edel used by ~JAC is cc= prised of eigh: vele=es which are in-

errela:ed by a sc:verk cf fiev patha.

~he p cg:s= calculates the a=cus: cf ac:ivity i each volu=e a: specified :1=es and deter =ines radiclegical doses are specified distances based c activity entering volu=e 8 and specified =e:ecrclogv.

he calcula:ed deses are ex:ernal whole body gn-2, ex:ernal whcle bcdy beta, and

he internal inhalatica ec 1::en doses te :he skeletal sys:e=, thy cid, lung, gast:c-in:estinal tract and Octal body.

The recuired input data consis:s of

.a.

hree :ypes:

(1) flev :odel da:a such as flev ra:es and fil:e efficiencies, 1,

)

(2) nuclear parac:eters such as decay cens:en:3, b

.hing ra:Los, and disin:egra:1cn j

energies, and (3) radiological dese input such as vindspeed, a:=cspheric dilu:icn 1

fac: ors, distances, and b) sching races.

Se eniculation of ac:ivity in each voluine is based en the assu=p:ica of instantaneous hc=ogeneous =ixing.

Se calcula:1cn of radiological doses is based on :he se=1-infini:e cicud approxi=atien. All cale=12: ices are based on the analytical solu:ica of the coup' led 1inear differen:ial equa:icns governing I

the activity in the cifferen: volu=es.

Se S AC coda, vi:h app cpria:e para =eter assign =ents was also used to 1

a

]

evalua:e the plu=e exposure deses fo: :he Reference L'JK of :his study.

?c :his study, it was observed tha: the dose caregeries of whole body ga==a ex:c:nal plu=e exposure and thyroid 9hm?a:1ca and ingestica dose cont:ci and fo: this reasen other c gan dose categories are c=1tted f:c= chis 4

4 presentation.

i f.

Paramera: Assi:n=ents and Assu=ntices l

able 5-1 p:cvides a 11s:1=g and s-*:7 cf :he para =eter values and ::alysi.s assu=p icts of this study.

"'he characts d.s:1cs of :he 757 si:1=g event, the 03A #1,'and :he reference LL'? even:, DBA/1CCA are dese:1 bed. Sese events i

I are fel: :: Scund the envelope of e=e gency preparedness plac.ing.

1 1

I 1

, ~. -

- ~

~ - --

,__________.__~_-,,__._,,,,.--...,-,_-..,,.-,._.,._-r,,-~

,-,.-,-----m_.-,,.,.n,,

9 6.

.Melicabic E'2 Dis:ances fo-Fer: S:. 7 rain 6.1 Evaluatien of Evaeus:icn E"2.6: TSV The I?: (E=ergency Planning 2cne) deter =ina:icn for For: S:. Vrain is based on the esti=ated acciden: doses in the enviren=en: and their c =parison to the re-cn== ended ProtectiveActien-Guides-(PAGs) cen:ained 'n Ref. 3, Table 5.2.

~hese ?AGs for the general popula:1:n censis: of dose ranges in :he even: of a= c=ergency condi:icn, alcug si:h rec = ended ac: ions to be taken by One k

responsible local au:hord:1es.

Figures 6-1 and 6-2 shev the ce=parisen be:veen FS7 and a referenca 1000 rJ(e)

L*JR of the cu=ulative dose vs. distance..uso shewn en Figure 6-1 are :he 1 and 5 Re= vhole body ga==a ?AG dose levels. 3elev 1 Re=, no prctec:17e action is required according :s the ?AG, while the state nay issue an advisory, and environ =en:21 radia:1cs levels are =c=1:Ored.

For doses of 1 to less than 5 Re=, che general pcpulatica shculd seek shel:er and avait further ins rvetiens, evacua icu of particularly susceptible ele =ents of :he general populatica should be censidered, access shculd be con:: 11ed, and envir:n=en al radia:1cn levels

=cnitored.

For 5 Re= or higher whole body ga=a doses, -"daterf evacuatics of the populatien in predeter=ined areas is rec:= ended. Figure 6-2 is si=ilar ::

Figure 6-1 excep: : hat it is fer inha12:1cn thyroid dose and the ?AG 1evels are 5 and 25 Re=.

Clearly, thyroid dose is :he cent:0111cg fae::: since che dis:ance

s which pro:ee:1ve ac:ica is recuired is larger.

7::= Fig. 6-2, :he 0 :o 30

'100= (2.5 =1.).

day B.hals:ica :hyrcid dose for ?S7 of 25 Re= occurs a: abou:

he above da:a is also s"-arized in Table 6-1.

For a 10 ni. L*JR evacuatien radius (16,000=), :he dese f=

he reference :142 is

(

abce: 11 Re= inhalacion :hyr:id.

~he distance f:r 757 for the sane dose as :he referen:

L2 at 10 =1. is about 7500= (4.7 =1.).

herefere an evacuatien radius of about 5 =1. for FSV would afford a conparable degree of public protec:1cn at i

1

_ - _ _.. _ = _. _

- :hs 10 =1. D2 dis:ance.

here is also a censiderable difference in the time of the ac:ivi:7 released f:cm FSV ce= pared :: :he reference S2 asshew: in Fig. 5-3 for the inhala:1cs thyroid. *his figure shews : hat for the G2 high thyroid doses (100 re=) have already been received a: 1 =1.

in :he firs: hour, while 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months should be avail-able even a 390s for FS7, befors :he icwer PAG (5 ren thyroid) is reached al-lowi=g an orderly and organized evacuatics :o be done if cecessary.

6.2 1 res:10: Fa hwav O* Fvaluatien

(

In addi:1c to direct plu=e expcsure, the population sur cu= ding the nuclear power plan: can be subjected :o pa:hway deses f:c: ces:ani=atics of the sur-rounding c: cps, =11k, and food stuffs subseques: to :he a:=ospheric release of radioactivity in the accident.

he pro:ective actics guides for exposure f cs food 2:uffs or wa e (Ref. 3) define :he guidance to be exercised by :he u:111:7 in 1:e assess:en and ccat:ci of the post accident ingestica pathways.

he most severely rest-ictive inges:1c: pa:hway for ISV and the reference

'a2 acciden: exa-d"ed was found to be the iodine-grass-ccu-silk-infant thy:cid pathway.

~he predic:ed thy cid inhalatics dose vs. distance for both the reference G2 and 757 is displayed in Fig. 6-2.

~he iodine-grass-cow-silk-infant pathway

=ay be related :c -131 plu=e exposure dose by using an apprevd-n=e fac: : of 300 (Ref. 2) and reccgni:ing :he fae: ha: :he thy:cid dese repc::ed in Fig. 5-2 is searly all due :o :- U 1 exposure.*

he plu=a thyroid i=hals:ic dose, which is p cpor:ic 31 :o inges:1cs pa:hway dese, for :he refere=ce G2 is 0.35 Ram."~he dis:::ce at which this dose level is reached for 757 is abou: 30 =iles and is censis:en: with FSAR Chpa:e 2 discussicas of de=cgraphic s:udies at distances up : 30 =iles f:c= the site.

I-131, a: 50 miles, con:ributes 99* of :he reference um plu=a inh:1 :icn dose ce=1:=en: and co; ecpondingly 97* for FSV.

- Ref. 2, able I-2 ex: ended :o 30 =ile radius.

-srme-rm-.--

s+---,-ewe

-,yg-..-.9-7 g

y.--

p_,

,._,_7

,7

,a

__,,7., _,,,,, _,., _ _ -,

'7 C;nelusi:ns I: is concluded f:c

his I?: s:udy :ha: a sign'ifica=:17 s=al',e evacua:1ca radius can be justified for the ?cr: St. 7:ain plant than for a reference 10C0 !f4(e)

L*JR.

A further conchs'ica f::= :his s:udy is tha: :he unique eSaracteristics of :he 737 plan p;cvide a siev gradual heatup ci the core alleving considerable time (en :he order of : ens of hours) for orderly no:ifica:1:n, =cnitoring and eva-cua:1cn :o pecceed. Also, a s aller radius for the controlling inges:icn pathway,

he grass-cow-= ilk-L: fan :hyroid, can be derived which offers :he public the i

sa=e protectica as a sim4'arly si:ed L'a4.

In both cases, thyrcid dose is the li=1:ing cens::ain:.

"'hese eccelusiens are based en siting even: analyses using generally cceservative core release fractices and eteorology. Table T-1 su=-

sarizes the applicable e=ergency planning :enes for :he plu=e exposura pa:hvay a=d :he ingestica expcsure pa:hway for 70:: S:. 7:ain pr:viding equivaler.: pre-

ectica to the general public.

References 1.

"~2AC - An Analytical C.: pu a ? cgran c Calculate the Ti=e Dependen:

Radiclogical Effects of Radic=uelide Release", D. 'J. 3uckley, Ge:fral A::=1c Co. Repc : GA-D13/*76, 1976.

2.

NURIG-0396, " Planning 3atis for :he Developmen of Sta:e and Local GoviF en: Radiclogical I=ergency Response Plans in Supper: cf Ligh: 'Ja:e: Nucles: ?lan:s".

3.

""anual of ? ctectite Actic: Guides and ? ::ac:1re Actiens for Nucles:

ciden:s", T-s --- e=:21 ? c ac:1c: Agency Repc::, I?A-520/1 Col, 1975.

IS'l Safety Ivaluacion Report, Oivisien of Reac::: Licensing, USAIC, Jan. 10, 1972.

a g.,

,>e p.===

-4644w+-e=*e

'N Suu=e ees-F-.=A==#N"**"a-*-*6N**

~

.y-w,=-g-

-my-wy,

-.i..%--

.m

.__g

_g

T511LE 3-1

~

All10SI'llERIC DL LUTI0li FACTORS A FOR FSV DBA 11 AllD ftEFEREllCE LWR DUA/LOCA UASCD-014 ti!!C staff" VALUL5 U5ED til Tite FSV SER

~

l DISTAllCE (ill ~

pitE (llR) 590 1600 4000 8000 16,000 24,140 32,200 48,300 64,400 80,500 8

7.2-4 1.43-4 2 76-S 1.65-5 7.89-6 S.09-6 3.77-6 2.5-6 I.9-6 1.5-6 16 S.1-4 1.02-4 1.96-S 1.17-5 S.61-6 3.62-6 2.68-6 1.8-6 1.3-6 1.0-6

{

24 4.1-4 8.35-5 1.61 S 9.60-6 4.59-6 2.96-6 2.19-6 1.4-6 1.1-6 8.6-7 34 3.5-4 7 03-5 1.35-5 8.09-6 3.87-6 2.50-6 1.85-6 1.2-6 9 1-7 7 2-7 40 3.2-4 6.49-5 1.25-5 7.46-6 3 57-6 2.30-6 1 70-6 1.1-6 8.4-7 6.7-7' 52 2.0-4 5 7-5 1.1-5 6.56-6 3 14-6 2.02-6 1.50-6 9.8-7 7 4-7 5.8-7 i

i 58 2.65-4 S.4-S 1.04-5 6.21-6 2 97-6 1.92-6 1.42-6 9.3-7 7 0-7 S.5-7 100 2.05-4 4.13-5 7 95-6 4.75-6 2.27-6 1.47-6 1.08-6 7.l-7 S.4-7 4.2-7 400 1.03-4 2.09-S 4.01-6 2.4-6 1.15-6 7.4-7 5.47-7 3.6-7 2.7-7 2.1-7 I

720 7 7-5 1.56-5 3.0-6 1.0-6 8.59-7 S.54-7 4.1-7 2.7-7 2.0-7 1.6-7 1500 S.3-5 1.09-5 2.09-6 1.25-6 5 98-7 3 86-7 2.05-7 1.9-7 1.4-7 1.1-7 4320 3.2-5 6.45-6 1.24-6 7.42-7 3 55-7 2.29-7 1.69-7 1.1-7 8.4-8 6.6-8 3

ll>teil in exponential form such that, e.g., 7.2-4 means 7 2 x 10" AValues in units of S/m are n

l i

i y

3' Table 5-1 F.?: Study - Assu=pticas and Pars =e:e Selections Para =ece'r Oescriptien

?SV Sourca Ter=

?cuer level, W( ) design 379 W(:)

Acciden: scenario assu=ed 33A J1 (75V 75AR Appendix 3, page

(

D.1-56)

Release of ffssion products frem Ti=e dependen: release

over a 475 the TSAR fuel particle hour period Release fractica frc= fuel :o TID-14844 frae:icas e= ployed pri=ary coolant system Noble gases 100%

Iodines 50%

Others l'

?la:ecut reduc:1cn fac:cr

I2-14844 reducticn of 50% applied to (Icdine only)

Icdine transper:ed frc= the prinary coolant system to the reae:c con-tain=ent building.

?C27 leak rate 0.2% vole =e/ day

(:c:al duration of accident)

Reze:cr bui ding ventils:icn sys:e= characteris:ics 1.5 velu=es/ hour (en for total Purge ra:e duration of the accident)

?U.ter efficiencies Noble gases 0*

2alogens 90" Particulates 95 Addi:icnal pla:ecu: and gravi:n-Ignored ticnal settling of condensible nuclides in the confinemen building

"~'ine-dependen: source tern identified by desi;; nation 75"TIO*FUEI.REL. and discussed in engineering file C-70-001, F. :i. Dancek.

Table 5-1(Cent.)

?arameter Descristice 7aference L*JR*

4 3curce tars I

?cwer level,1r4(:)

2958.

Accident scenario assu=ed D3A/lCCA Release of fission produe:s f ce Near instan:aneous release cf

he core =a:ria, :o the reacor T!D-14844 core fractions l

building Core inventory, available for C -14844 assu=ptions (including release fre= cen:ain=ent iodise redue:ica due :o pls:eou:)

Noble gas 100%

Iodine 25%

Available for leakage fre= the reactor contain=en: i==ediately Isotoc_es_

after LOCA (Ci)

I-131

1. CM7 i

I-13

2. 7M7 I-133 4.2+07 1-134 4.8+07 4

I-135 3.8M7 Ir-83M 1.3+07 7.-853 3.2M 7 Kr-85 7.34 5 Kr-87 6.347 g:-a8 3.8+07 Kr-89 1.148 Ie-1313 6.5+0i Ze-132M 4.04 6 Xe-133

1. 7+08 Xe-135M 4.5+07 Xe-135

2. 3+07 Ie-137 1.5+08

(

Xe-138 1.5M8 i

7n11e no: specifically identified as the Sun Deser: Nuclear ?cuer Plant, :he reference L*4R of this study has =any charac:eris:1:s si=ilar :o this curren: ?'JR desi:;n.

- e

-..~=wm-

-e mae-m.-

w.wwmm -

o

..,mmm-

._m

-ma-.

+a

l 0.

. Table 5-1(Cent. )

? ara =e:er Ce3ericcion Iodine ce=posi:1cn Elenen:21 91%

? articulate i:

y Organic 4;

Contain=.it building leak rate (

0-24 hours 0.2 / day

>24 hou:

0.1::/ day Contain=ent spray charac: eristics Ini:12:1cn :1=e 150 see Sprayed region 70 0: sprayed regica 30%

.M'v'"g race sprayed to unsprayed 2 hr-1 regica Eler. ental Icdine re= oval rate 10 h -l Particula:a Iodine re= oval ra:e 0.45 h:-l C ganic !cdine re= oval ra:a 0

odine ::7 (ele =en al) 100 Resultant single volu=e L*JR 3.0 hr,'

sprsy rencval cons:an: used this study e

?:sr. LOCA contal.nen: purge i

characteristics (: reduce c:= bus:iole gas cencentration)

?n ge interval 336 :e 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months Purge ra:e 50 SOM Purge fil:e efficiency Ele =en:21 & Me:hyl Icdine 70:

Radionuclide leakage fr:= ESF Ignored area ee.

e c -

m.*

_.w.

,w.--.-

.-r_..-..

~

Table 5-1(Cent. )

Parc=eter 2ascriction Specific Site and Cose ? ara =eters (Used for both FS*/ & Reference U4R dese estina:es)

A:=cspherie dilu:icn fac:::s See Table 3-land Figure 3-1 e= ployed 3:eathing ra:es i

Reference U R 3

0-8 hour 3.47 = 10-" 2 /sec 3

S-24 hour 1.75 x 10-4 m /sec 24-720 hour 2.32 x 10-" =3/sec

?SV*

C-40 hcur 2.32 x 10-" =3/sec 40-52 hour 3.47 x 10-" =3/sec 50-53 hour 1.75 x 10-" =3/sec 3

53-7:0 hour 2.32 x 10-" m /see Average vind speed 1 =/sec Dese cede u:111:ed TDAC - GA-D13476 Decay & buildup esti= ate Considered Fallout deposi:10n enreute :s Considered f:r Icdine only (see dese :ecep:::

Reg. Guide 1.111 Figure 6)

Conversien facter for infan:-

300 (Ref. NCRRG-0396 Append'x I,

' "i thy id Icdine inges: ice page I-19) pa:hvay (rntio of thyroid dose d ~en: facter f=r

k pa:hway :o :he inhala: ice plu=a exposure pathway)

Note: 757 breathing rates and at=cspheric dilu:1cn fac: rs have been pe==uted to -,- #-4:e che off-si:e dese, i.e.,

the ti=es of highes:

breathing ra:e and pocres: at=espheric dilu:ica correspend ec the peak in :i=e dependent release of fission produe:s frc= :he fuel :o :he pr'- ef coolan.

--w

~,. - = =

..-.-,w~

e w

m 7

Table 6-1 Su==ary of Oerived EP" Evacua:icn Jis:an'ces for FS*/ and a Reference 1000 %'(e) L'a 1

' hole 3ed's Ga=:a - Ot ect Flu =e E:ccesure No ?r-..,1ve Action (?AG <1 res whole body)

E?2 Distanes

?SV -

L'a2

< E.G(,)

2.2 Mi.

0-8 Hou:

0-24 Hour

< EA3 2.5 Mi.

0-30 Oay 0.6 M1.

3.0 Mi.

Evaeus:1c= Required (?AG> 5 res whole bcdy)

_ E?2 Distance

?SV L'a2 0-8 Ecur

< EA3 0.9 Mi.

0-24 Hou

< EAB 1.0 Mi.

0-30 Day

< EA3 1.2 Mi.

~h'iroid Inhalatien - Diree: Flu =e E ecsure No ?:otec:ive Ac:ica (?AG <5 re= Thyreid)

I?2 Distance FSV L'a2 0-8 Ecur

< EA3 7.5 M1.

0-24 Hour 1.2 Mi.

9.0 Mi.

0-30 Day 8.1 Mi.

16.0 Mi.

Evacua:1cn Required (?AG 2 25 re= Thyroid)

E?2 Distance ISV L'a2 0-8 Ecur

<EA3 3.1 Mi.

0-24 Ecur 0.5 M1.

3.5 Mi.

0-30 Day 2.5 Mi.

5.3 Mi.

(;)

75'; EA3 (Exclusien Area 3cundary ais:anca) 590 =eters.

=e-,

--+&

+--w.,

,se,e-

.-.%w.,

.e ww. -.,-

w-y

.a-+-

ep

,9-w

&----+y--

m---i+

--m e-y.

er we

.-.ge--

y-e e-T-9g*m-g

l mv.

Table

<t ISV I?: Ois:ance Cenpared to Generic L'a'R EP Dis:ance of NUREG-0396(~)

Acciden: Phase Generic IWR E=ergency Cc= parable IS*.' E=er-Planning Zone Dis:ance gency Fir.ging Zone "JREG-0396 Distance W

?lu=e Exposure Ps:hway About 10 =dles radius Abcu: 5=iles( )

Tncle body (ex err.al)

~hyroid (inhala: ion) i Other or;ans (i=: al2:1on)

Inges:1cn Fa:hway ou 50 =11e radius Abou 30 =iles(

Thyroid, whol.e. body, bene = arrow i_cges:1cn)

(1) NUREG-0396, I?A 520/1-78-016, "?lanning 3 asis for :he Develop =ent of Staca and Local Gover: <n: Radiological E= ergs y Response Plans in Supper: of Light "a'a:er ?:ver Plan:s", Joi== Reper: USZ?A and USERC. Collins, R. I.

et. al., Dec. 1973.

(2)

ISV EF:: dista:ces were eb ained by (1) assu=ing :ha: :he Reference LWR of this study =eets :he intent of '* REG-0396 fer design baris acciden:s, (2) es:i=a:ing :he Reference L;R dose a: 10 =iles (plu=e) and 50 =iles (i=ges:icn) fit :he 03A/10CA od this s:udy and : hen, (3) deter =ining :he correspending ecui-dese distance for :he ?S7-D3A #1 ever2 (3) ny- ' d ' " ala icn c ::::1s vi:h abou: a 5 =ile E?2. EP: dis:ance for whole bcdy is apprev'-':ely 2 _iles and Other organ deses are cegli;ible.

(4) 3.e grass-cew-= ilk-indan: :hyrcid exposure pa:hway de=ina:es for the 757 saviren=e:: ally released radienuclide source cer=.

l I

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i Figure 6-1 2

Cumuis:ive plu=e exposure, whole bcdy gn n dose vs. distance.

n:cg:: tion in:c vais of 3 hr. 1 day, and 30 day:. Comparisen of TSV-UBA '. Event :nd i

1000.W(c) LUK-DEA /LOCA si: ink even:.

SRC ce:corology (f::= 07.'.) for be:h.

(

1 2

3 4 5 6789 I

1 2

3 4 5 6739 l l 9

1 2

3 4 5 6789 '

l

.' 0 - 1 2

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).

l

.w 1

Il

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l FIGuaE 6-2 C$.:c:ula:ive plume exposure innalation thyroid dose vs. dcwnwind distance.

Inte-

~

grat.icn intervals of 3 hr, I day, and 30 days. Com::arison of F;V-03A 1 Event and 1000 $(c) LWR DE*/LCCA siting Cven:.

f4RC ne:ecrology (fron SIR) for ::cta.

t 2

3 4 5 6 ?39 8

2 3

4 S S 781 1

3 3

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31 2

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6

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' - ~ * '

FIGURE 6-3 Cumulative plume exposure inhala:icn :hyroid dose vs. : ice.

Comparison of

. 5V-OSA 1 Event cnc 1000 MV(e) LWR-DDA/LCCA 51:ing Event, f4RC Mc:corology (from SER) for botn.

3 J

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PLATTEVILLE, COLORADO 80651 F. arch 18, 1980

... Fort St. 7:ain Uni: No. 1

?-80083 I

Mr. 3rian K. Gri=es Director E=ergency ?reparedness Task Grcup Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Co==issica Washington, D.C.

20555 SU3 JECT:

Fort St. Vrain Uni: No. 1 Radiological E=ergency Response Plan

'S

Dear Mr. Gri=es:

We are trcns=itting herevich two (2) copies of Radiological E=ergency Response Plan in draf t for=.

"'here are sc=e detailed areas of the

(

plan which have no: been ce=pleted as yet, but the basic plan should be co=ple:e encush for you to begin your review.

~he plan has been developed on the basis of the acceptance criteria published as a part of NUFIC 0654, and generally meets the intent of NUREG 0654 vich the following exceptions.

1.

Near Site Enertenev Oceratiens Center i

I i

l Our near size e=ergency cperations center (Forward Cc=and l

Post) has been designated as the For: Lupten Municipal Building which is located app cxi=ately ten (10) =iles scu:h-scutheast of the plant.

As indicated in our let:er P-79205 our Forward Cc==and Pos: loca: ion was developed vi:h the State / Local agencies and has been ecuipped vi:h necessary co==unicatien syste=s, supplies, e:c.

This facility was utilized during our ce=bined drill vich the State on Febru-ary 28, 1980, and proved to be more than satisfactory in all respec:s in acce=plishing the coordination and direction of

~

emergency ac:ivities.

a

m We can see absolutely no justification f or establishing an e=ergency cperatiens center vi:hin ene (1) =ile of the site as recuired * - NUplC 0654.

In fac: such a center vi:hin the EPZ presents problems of access, personnel control, possibility of evacua:1cn and other prcble=s which are ne experienced a:

the For: Lupten locatien.

We clearly de=enstra:ed during the

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g Mr. 2rian I., Grimes "2

March 13, 1980 3

1.

Near Site E=ertency Coerations Center (continued) j February 28, 1980, drill that an' e=ergency can be bandled at the Fort Lupton facility with a =ini=us of problems, and in our opinion with.far less proble=s.than e=ergency center with.

in one (1) sile of the ' ite. s The services available in For s

Lupton would not be available at a near site center, and we feel =oving the center fro = Fort Lupton would only serve as a de:ri=en: to our overall plan.

f 3ased on the resul:s of our drill and the lack of any justi fication for being closer to the site we feel that adequacy f

o' cur Forward Co =and Pos: location has been justified.

2.

Plant Staffing h*UREG 0654 se: forth cer:ain =ini=al require =ents for plan:

staffing in Table B-1, which in effec' requiras een (10) people on shift and the capability of having an additional twenty-six (26) people on site within thirty (30) =inutes.

As indicated in our previous responses to the TMI-2 Lessons Learned require =ents and as confirmed by Nuclear Fegulatory Co==ission acceptance of these requirements. (undated le:ter fro = T. Speis :o J. Fuller, March,19305, e=ergency situations at Fort St. Vrain develop very slowly as co= pared to a va:er-reactor.

As a result, operator and e=ergency response ti=es are considerably longer.

Our e=ergency plan has been developed on this basis, and therefore, ;he require =ents of Table 3-1, NUREG 0654, are considered inapplicable to For: St. Vrain.

3.

Early Warning Aler: Syste=

As indicated in our recently trans=itted study (see F-80066) concerning the EPZ for For: St. Vrain we do not exceed any of the FAG's fcr cu=ulative whola body ga==a dose for the firs:

l twenty-four (24)' hours following a LOFC accident, and never l

reach the PAG's requiring evacuation.

For thyroid inhalation exposures we do not exceed the FAC for "no protective action required" for up to twelve hours at the exclusion area boundary (22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months at one =ile) and we do no: exceed the "shel:er,

=onitor and con:rol access" PAG for up to :ven:y (20) hours a: the exclusion area boundary (50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months at one mile).

Based on these ti=es more than adequa:e ti=e exists for notifica-tion of the public and for initiating evacuation of the public without the need for an early warning alert sys:e=.

1: should be noted that these exposures are based on ex:remely conserva-tive releases of Iodine and extre=ely conservative reactor l

o More realistic release rates of Iodine would v'essel leak rates.

be a fac:or of ten (10) below those assu=ed for the EP2 study.

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March 13, 1980 Mr. 3rian K. Cri'=as '

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4.

Meteorolotical S'vstems

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Our present plan do'es not meet the require =ents of NURIG 06.54 cencerning backup =eti-

.ogical inst:u=entation nor the re-We are pres-quire =ent for re=ote n.werro.gstiun c.apabilities.

ently investigating other al:ernatives.

1 5.- Iso-Dose Curves -..

The Iso-Dose curves have not been included in the draft plan l

as ve have been unable to deter =ine from the Nuclear Regulatory C==ission jus: hat is required in this area.

6.

Letters of Acree=e'nt

~

Lat crs of agree =ent with various off site support organiza-tiens have not been included at this ti=e as we are still in the process of developing these agree =ents.

In general, how-for j

ever, our State plan is designed as a general agree =en:

all participating agencies, and those agencies that are signa-tory to the State Plan vill not be called upon for separate o

letters of agree =ent.

7.

UUREG 0610 The guidance provided by NUREG 0610 has been =cdified to best The re-fit HTGR technolcgy versus water reac:or technology.

quire =ents for " Unusual Event Notification" are included in an be:veen Public Service Co=pany and the State which i

agree =en:

l vas origina:ed prior to NUREG 0654.

Since this agree =ent =eets the intent of NURIG 0610 and has the concurrence of both Public Service Cc=pany and the State we feel it is adequate :o fulfill the notifica:icn require =ents for unusual events.

of Other than =inor differences we believe the plan =eets the inten:

NUREG 0654 acceptance criteria.

j If you should have any proble=s or questions we would appreciate hearing 1

l fro = you prior to the May 21,1o80, =ee:ing date.

Very truly yours, WzuJw7 Don W. Ware = bourg f

Manager, Nuclear Production O

Fort St. Vrain Nuclear Generating Station DVV/alk

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Mr. 3'rian K. GrM:::ns March 18, 1930 e

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Dave Pr.e=,bindowski 053 Pacific Northwest Lab

' Eutelle Boulevard Richland, b'ashington 99352 Jim Miller :-

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'Jn i: No. 1

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0:er: L. c.se esco, assistant s,trec or c.

Division of Licensing U. 5. Nuclear Reguia cry C ::ission

'a s hi ng :n, D. C.

20555 l

SU5 JECT:

For St. " rain Uni-No. 1 i

ergency r.espense rian

REFERENCE:

NRC Letter July 23, 1930 Oear Mr. Tedesco:

We are transmitting herewith three (3) c: pies of Our revised 2:ergency response pian.

ants revised plan i ncl uc.es c..anges as a result of the May 21,

1930, plant site review meeting as well as certain changes that.resulted frc: c : ents con ained in ycur j

July 23,

1930, letter, In addi; ion to the revised plan, we are eevb.ing our resp;nse as Attachment A to :his letter to actress your r

July 23, 1930, letter.

As we indicated in the May 21, 1930, meeting as well as in varicus correspencence submitted as a part of the TMI-2 Lessons Learned

.t.

,/ rain is a c:ep.ietely di,..eren reac cr 1

i.

he.leve cor e

iasts, we.. is reactor concept coupled wi h tne st:e of

-he reactor concept.

in i

negates many of the requirements se:forth by NUREG's 0554 anc 0610 whicn ere deveicped primarily on the basis of 1,000 MW(e) light water reactor technology.

I:

is imperative, therefore, that our reacter design and Emergency Plan be evaluatec on the basis of cur si:2, and that ceneric requirements he evaluated on.the basis of l

s:ecific technical, saf ety, and envi ronmentai cif ferences'.

e.

Save had to essential.ty caveic: our cwn critaria :.Or cor-St.

l

rain utilicing water reacter criteria setforth by various Niclear l

i Reguia:O ry C:::ission documents.

On this basis our critaria is necessarily different fee: that oubitshed and we have taken justifia le excection

0

-he NLAEG's.

These excep-ions -ere su:portec in various c:rrespondence (see reference list 1; achec) and are further supported by Attach:en: A of this letter-i 1

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In the May 21, 1930, =ee:ing we were informed my the declear Regula:Ory Commission review team that many of the items were a ca::er of =clicy, anc that the review team did net have the aut.'.ority matters regardless of the teennleal to make ex:e::icns en eclicy ~

j usti ficati on.

We cannet acce:: this 00sition, and we recuest sna as s00n as you nave had :ne :::cr: unity :: rev'ew cur revised emergency Oian an: Our res:0nse that we se given :ne :00rtunity ::

meet wi n y0u an: :ner :ersonnel wn: c: nave One autacrity ::

evaluate and/cr ac:ept cur positions en the basis of :ne te:nnical justification previced.

In tne interest of time it is requestec :nat such a meeting me established a :ne earlies possible ca e sc that we may finali:e Our

lans := cee the various ::mmitment ca es se:fer:n. We will e availacle :: mL 2: witn you at your ::nvenience and are looking f:rwar: :: nearing fr:m y,cu snortly.

'Very truly yours, I' W /h th

.o n.,w..,arem: urg w

v Manager, Nuclear Precu :icn Fer St. Vrain Nuclear l

Generatin 5:a:1cn

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0:r-escencence Num:er Cate Su: ject 1.

?-79130 June 15, 1979 Gaseous Effluen: M: nit:rs 2.

?-79205 Se: am:er 10, 1979 Emergency Flanning,.ce:

St. Vrain

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4 P-79249 0::::er 29, 1979' Fellewu: Action Resulting ne c.ardi n c.

N - eviews rre

n. n One TMI-2 A :icen:

5.

P-79290 Novem:er 30, 1979 NUREG-0610 6.

-79293 Decec:er 12, 1979 Fort St. Vrain, Unit Nc. 1, TMI Lessens Learnec r i::c.e.

vecer. er :~~, 2:~~7c.

nevise.

rel ~i ewu: met <. ens s

e r r e m N..,.,

n.

neviews n e s ul t,. n Regarding TMI-2 A::icent

.e :;1ementary Res:ense,

,etem:er,.e, ::/e.

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I em 2.2.1.0, Lessens Learned Task Force, TMI-2 9.

?-79312 Decem=er 25, 1979 Additional Information Rec.arci ne.

June 1,

1980, A::icn Items Resulting fr:m TMI-2 10.

?-E0011 January 29, 1980 Re=ues:

fer Evacuation

_imes i

l i

~ formation l

11.

-30023 Fe:ruary 20, 1930 Ac itional n

trem iMI-2 NRO Resulting_.eam Site Visi,

seview l

Janua ry 21-22, 1950 12.

?-3C0a1 March 5, 1930 Recuest fer Evacuation

.imes i

i II.

F-30053 Mar:n 13, 1930 Fe r St. Vrain, Uni: N=.

1, ercency ciclecical t

na nescense rian l'.

-E0056 A:-il 1, 1950 Fert St. Vrain, Und-N:. 1,

merc.ency ?.t ann t nc.

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ATTACHVENT A.

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NRC Ouestion/Cc= ment 21an mus be revisec Oc estaclish a printical and an alternate EO F.

Ec n facilities snould mee:

ne recuirements of Darrell G. Eisenhut's le er of A:ril 25,

1950, su:Je :

"Cl ari f t :t-i cn of NR" Recuirements for Emergency Res:ense Fa:ilities a: Eacn Site."

t PSu, escense s

prine,.,ie and a. ternate :Or as we n. ave h,e :annet accress the t

never received the A ril 25, 1930, letter whien you reference.

It is ur understancing -hat new =riteria vill be publisned as a

ar: ef NUREG-0696.

U:en recei:: and evaluatien of this cc ument we will =cdify our emergen:y plan.

In the interim we intenc sc con-inue with our cians to utilize One Port Lu::en

~

Municipal Sufiding for tne EO.: as s atec in our le er P-E0053.

As we Oncerstanc the new riteria ceing cevele ed un=er NUREG-0695, a distance of approximately 10 miles frem :ne rea::cr would be acceptable fer the EO:.

Dependin on the criteria specifiec for the EO.: anc an al ernate EC.: we will re-evaluate cur position at :ne time nun- =-0...

is publisnec.

=

2.

NRC Ouestion/Cc= ment Plan mus: ce revised to take into consiceratien :ne plant t

sa le

-1 0,. NUnca-Oc...c*.

Inere must ce seme b.

sta,.fing in augmentation of en-site personnel witnin 30 minutes.

Mus; icen-ify =csitien that will net ce filled and provice rationale for nc: naving 10 personnel en snif a: all times.

-.rS. ses:ense

~m tideration was given to the iant staffing in our A:ril craft cf :ne RERP.

Ficures 5.1-1 :nrcugn 5.2-6 of tne RERP :e:ic:

l Octn :ne normal and :ne emergen:y staffing for :ne clan.

. igure 5.1-2 previces the r.ormal c:erating staff (9 :ersonnel

lus a Lead Security Officer) for :ne :lant anc fulfiils :ne on-sr.ift recuirements cf Ta:ie 5-1, NUREG-0654, with ne exce::icn nat we ce nc have a Rac/ Chem Technician on snift.

The en-snift Health Physics Tecnnician has sufficien training erfer= :ne necessary initial surveys and raciclogical assessments :c rete:: in-clan: ersonnel.

The 0:erating staff I

has suffi:ien training anc :rceecures te evaluate the off-site effe::s. We can see no immediate re:uiremen for the Rac/Cnem.

ie:nnician es:ec;aily since cur at:idents cevele: at a mu:n u,-

siewer rate than Ocm: arable wa er reae::r at:icents (see nn.

1e::er Themis Seeis to J. Fuller, March, 1950, A :e::ance of l

Categcry A TMI-2 Recuirements).

I i

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tne augmented staff callec for in Ta:le 3-1, Witn reference :

NUREG-0554, we have jus.ifiec delaying the resp nse time of :ne Shif: Technical Advis:r (STA) (basec egain on :ne rate i.: whicn cur a::icents cevelep) from 10 ainutes to one (1) hour (see PSC le::ers ?-792a9, 0: Ocer 29, 1979; P-79299, Dece.r.:er 12, 1979; P-793C5, Dece=cer 13, 1979; P-79312, December 23, 1979).

The a :icent time frames and the associated res:cnse times were a :actec Oy :ne Nuclear Reguia cry C:mmission Oy the above referenced le::er (Themis 5:eis :: J..:uller, Maren, 1930) in the Overall at:e::ance of the Categ:ry A TMI-2 requirements.

Since tre Nuclear Regula:Ory C::=ission found :ne res: nse time Of ne STA :: :e acceptacle we maintain na: :ne 30 minute augmented staff

..ie called for in NUREG-0554, Tacle 3-1, is not a;plicable :: F :: St. Vrain. On the basis cf the slew time in wnich a::idents ceveico and ne one (1) hear resense time of the setnnical a,dviser we co==ittec in cue n=a..r (Section 5.2) to have ne emergency organi:ation activated within 90 minu es whien woule intiude an augmented staff ecu1 valent :

Table 5-1, NUREG-055a.

This staff augmentation is

nsistent with Te:nnical Adviser res:ense time and is ter ainly consistent witn a :icent analysis and One ::ident devele: ment time frames.

3.

NRC Ouestien/Cemment The plan must (in addition to other NUREG-05*.0 n::ificatien re uirements) specify that wnen a " general" emergency is

eclared tnat the eff-site autnerities rescensible for im lementation of protective measures will be notifiec Dy the

" Plant Emergency Dire::cr" anc advised of re:: mencec prete: ive actions witnin 15 minutes of ne cirection of :ne emergency concision.

The plan cus s:e ify ne content of this initial message :: include:

a.

Class of emergency 5.

Wnether a release is taking : lace Affe ed areas Pr tective measures NOTE: The prete :ive measures re: =mencec in the initial message off-site may be "g

insice urn en racic" (30 minutes) creviced a f:liowup message incicating mere detail prete: ive measures basec en cose proje::icns.

PSC Rescense Per your re:uest the notift:stien time of fif een (15) minutes after ce erminat en nat a " general" emergency exists has been i

accec to Ta:le a.1-4 of :ne RERP.

Sam:l e netification messages as weil as felicwu: messages have

een in:iuded in Se::icn 5 of the RERP (see Fig.res 5.1-1

nreugn 5.1-3).

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Oc 3-2 NR Ouesjje-/ : ment.

Your Oian cus ces: rite the :ublic notifica:icn system :

incluce:

a.

The initial Off-site contact who will be responsible for noti fying the affected p ulation (either One s:e:ift:

Organi:ation or incivicual).

b.

The ca:asility for 21-neur per-day natification (:: Off-tite autnerities).

c.

The physical alerting system to be used:

sirens. NOAA wea:ner of emergency alert, tele:none aut :atic dialers, air: raft with Icud:peakers (wnien will se used := aler Oublic).

(10 eb above average caytime a= ient backgr und is a target Tor cesign :,. an aceouate siren sys em.)

1 eve.n

~

Distance

% Natified in 15 Minutes 5 miles 100%

c '. The basis for any exce:tions (e.g., for extended a:er areas with transient ::ats Or remete hiking trails) mus: ce documentec.

e.

Eve ry year you =ust take a stati stical sam:le of ne resicents of al. areas witnin the 5 mile... : assess the i

rt

ublic's awareness f: ne premst n::ification system and ne availability f information en what :: d: in an emergency, Plan mus: also in: luce a prevision for :Orrective measures a

previce rea e asie assurance that verage a:Or:acning ne cesign :je::ives is maintained.

f.

The revistens for use of a puoli: media system (radie, TV)

=revice clear instru:: ices :: :ne uuslic.

Twenty-f;ur neur statten

al plume ::verage.

a.

c.

Inciu e in :ne ian :ne cessages :: be transmit:ec

ne :ublic ( :ver a range of : rete :ive a :icns).

It is ne : era:Or's res:ensisility :: ensure :na: :ne means exis for n::ifying an: providic; pr===: instru: icns :: ne

u 110.

It is ne res: nsi:ili y f :ne State and 10:al governments

activa e :ne sys en.

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9 OSC Res:cese a.

The County anc tne State have the resconsibili y for n::ifying ne affected peculation. Acditionai ciarifica:1cn has been a ded to See:fon 6.1 of the RER?.

1 i

s.

-.ine ca:acil,.ty or 2, hour cer cay not,.rication to crr-site authcrities is inclucac in Section 7.2 cf the RERP.

and d.

The rhysical alerting systems :repesed b::n by the

er St. Vrain RERP anc :ne S a:e RERP is ne use of the emergency Or:ad:ast system (radio) anc :ne cis:at:h of County personnel in vehicles and icud s:eakers :: warn :ne general public.

As incicated in our ie er ?-20083, March IS, 1930, we have more than acequa:e time to effect necessary ; rete::ive a::icns prior to exceeding any of the Protective A:: ion Guidelines. During tne Pe:ruary 25, 1980, drill we tes ed the State Emergency Rescense Plan anc determined that the general public in :ne affe::e

cne

ulc be n -ified witnin 90 minutes. As indicated in our le: er ?-5C056 we have u: :: twelve (12) neurs c notify the Ou:lic prior o exceecing the most restri:-ive Prc:ective A:-icn Guiceline (icdine innalation) a :ne exclusion area

uncary. The plan for puoli: no-ifica icn in:iuces the use of several emergency broadcast bancs and tne use of television augmented, of c:urse, witn cis:a : hec pers:nnel.

Cn the basis of -he :: e frames asse isted wi-h our a::icent analyses and the use of radic anc televisien media we can see r.o justification fur an early warning alers system.

e.

As a part of the :ublic information pregram a statistical sat:le of the resicents within the five (S) mile E?Z will be taken to assess the :chli:'s awareness of wna: :: de in an emergency. The details of the public information progran are still being worke: cc: ce: ween PSC anc tne State.

Once this program is cefined Section S.I.1.d Of the RER? will be cevele:ed := cefine ne rogram, f

Use of the cedia systems :: :rovice ins ru::icns to the

ucli: i s tne res: ens.:ility of State, County, and Iccal au neri-ies.

The State F.ERP wni:n is a::-:vec :y ?SC has

revisions for the use f mecia systems na; meet ne recuiremen s Of NUREG-0654 Section 6.4.1.b of ne RERP 10 resses this subjec.

5.

NRC Cuestion/Cemment Uncer ?SC 4 :icns, Table 4.1-1, page 1, tne first i am, ne 2-hour -ice limit for notification Of an :::ur ence of an Unusual Even should be chanced := "as seen as cicc verec" Sicilarly, the four:n i er unter PSC a: tion sncult inciuce a re:uiremen-for a writ en su==ary within 24 hou s.

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ML20009G690

Contents

Text

SUBJECT:

REFERENCE:

Dear Mr. Seyf rit:

Dear Dr. Ahearne:

2.1 Acciden

Dear Mr. Gri=es:

REFERENCE:

-ae.%--

_

--------=-u--

~T=

c3-.;; i w+

. = =

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ML20009G690

Text

SUBJECT:

REFERENCE:

Dear Mr. Seyf rit:

Dear Dr. Ahearne:

2.1 Acciden

Dear Mr. Gri=es:

REFERENCE:

-ae.%--

_

--------=-u--

~T=

c3-.;; i w+

. = =

Navigation menu

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