ML18038A645

From kanterella
Jump to navigation Jump to search
Discusses Calculated Dose Rates Due to Shine from Reactor Bldg Atmosphere to Control Room & Security Bldg Following Design Basis Loca,Per IE Insp Rept 50-220/83-15.Doses Not Expected to Exceed 5 Rem During First 8 H Following DBA
ML18038A645
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 03/19/1984
From: Mangan C
NIAGARA MOHAWK POWER CORP.
To: Vassallo D
Office of Nuclear Reactor Regulation
References
NUDOCS 8403230116
Download: ML18038A645 (6)


Text

REGULATORY FORMATION DISTRIBUTION 'S -EM. ('RIDS)

"ACCESSION ~

NBRg8003230116'OC",DATE 84/03/19 NOTARIZED'O DOCKET FACIf.:50 220,Nine Mile-'Point, Nuclear 'Station< Uni;t i~ Niagara .Powe'5000220 AUTH NAME "AUTHOR 'AFFILIATION MANGANiC",Vs. Niagar a Mohawkr Powei Corp, lRECIP ~ NAME: RECIPIKNT. AFFILIATION VASSALLO~D<B. 'perating Reactors Branch 2

SUBJECT:

Discusses"calculated dose rates due'to,>shine from -t eactorl btdp atmosphereto.control room'.8, security bldg following design basis LOCA per -IE>> Insp Rept '50 220/83<<.15,Doses."not=

expected 'to exceed 5 rem, during first' h following DBA, OISTRIBUTION COOE>>

<TITLED'OR'-'Submi'ttalc AOR'6$ COPIES RECEIVES:L'TR .

TMI'ction j' ENCL . SIZE':

Plan 'Rgmt .NUREG.>>0737 L .NUREG. 0660

,NOTES:'ECIPIENT'D

>>COPIES RECIPIENT, CODE/NAME> C.TTR Er4CL~ ID CODE/NAME>> LTTR ENCL' NRR ORB2'BC -01 INTERNAL::ELD/HDS3>> IK/DEPER DIR 33 IE/DEPER/EPB NRR ERICKSON p P 1

3 1

i RGN1'COPIES IE/DEPER/IRB NRR'PAULSON t H ~,. .1 1

NRR/DHFS DEPY29 1 NRR/DL DIR 10 1 NRR/DL/ORAB 18 l31 NRR/DSI/ADRS 27 1 NRR/DS I/AEB 1 NRR/DSI/ASB 1.

NRR/DSI/RAB 1>> NRR/DST'IR 30 1 00 1 ~

1 EXTERNAL: ACRS >3/ 10 LPDR 03*

NRC PDR 02! 1 I NS CI 05-NTIS ,1,

>>TOTALt NUMBER OF COPIES REQUIRKDe LTTR 41 ENCL 0

t'~,) Ii>>; e l~wt "~,v<<i'k i I k 4 l>~II ~

I ' "<<k lt iv>> g f >>!I<<

>>Q t) vg <<V wl Vv l r<<, >>L li>>t'."O<y<

f r>> <<>n>>>r)<<t gj,w3 f'w<<ww gl >l( t A f f i,il'>II i"i~0(', ~ /I k>h ii lg I I' i'f >> ",

.II.;), ',,

i <<X Iv

,Q'> ~ I

<<'$i >>~ I

'>>gl<

Jl P$ >><<<<><<>>w I fw V I IIf't 1<<>> I, II <<I.) I ~ 'I<<) >

ilj,'$' "$ >I>> I I ) I' '

i l I <<V I~<<f~fji>> II f<<w, y><<<<W>

~>> " 'I;l>lw') I f'<<l<<9i Y )lv<<f <<V>>>>, i 'g I<<w>> li Ii i / l w i ff

<'w>>II,- ~f I>> II <>>>>wf yf r'vwl <<v; j >>>g $ V'0,) << ~ 'f >'Ii'I"'l<'<<e~<<>> I ill I

~i)Pr>> I >laic,,'$>>>>W<<>> ae<< (

f, << 'y'I]' << '<<' I i 'wyw I

) r~ f e i,k 'lIl'<< f ,"" '>6

'r l;,i: ff l<<<< 'lX> l wk'r '4'1 k >>'i r,' << > g y

~

eemasyaw~wg ~ ">AY<'

't j'>> <<VT II", 7 I I' f gwll<<$ i <<>f lyly ~ l

'll II I

"'wg Ii I II l, >'<<rvf>I~i I Q <<>>w Ii I'ew I'l P<<ill WI l'>>f.f.')>i Ivi71 ~ fV ~ k'III'f'l kii>'>'w .'Il<<I ~ 4 ~k f $

~ I i I / iwl I k 'II<< 4 t <<1 L

WW

7 MIIASAIRlA o 0 g IgQog@QK NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 March 19, 1984 Director of Nuclear Reactor Regulation Attention: Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: Nine Mile Point Unit 1 Docket No. 50-220 DPR-63

Dear Mr. Vassallo:

Our September 6, 1983 letter indicated that we would calculate the dose rates due to shine from the reactor building atmosphere to the control room and security building following a design basis loss of coolant accident.

These calculations were to formally resolve questions which arose during your Inspection No. 83-15.

The 30 day integrated exposure to the control room due to shine from the reactor building atmosphere has been conservatively calculated to be 2.85 Rem. When this exposure is added to the 30 day integrated exposure due to other sources of radiation, the total does not exceed 5 Rem. The average 30 day exposure rate due to reactor building shine is approximately 4 mR/hr.

This is significantly less than the NUREG-0737 suggested guideline of less than 15 mR/hr on average for areas requiring continuous occupancy.

Our calculations determined that the 30 day integrated dose to the security building due to reactor building shine wi 11 exceed dose guidelines for areas requiring continuous occupancy. However, continuous occupancy of the security building for 30 days following an accident is not required by our emergency procedures. The security building is the primary assembly area for security personnel, but alternate assembly areas are specified in the event that the security building is uninhabitable.

8403230iih 840Si9 05000220 PDR

,F.

ADOCK

','DR ..

5 M)

'l I *. Il rh t <<'>>

t

~,

I, t,$ ~ ~ M W .SL g<<, lh, I I

~ >>t>>f l lf I't<< ~

I'l II w,l ) Mrf) h" M MW I q>>

I fhl ih* ", I(lft t P,)f.. ) )

W~W, ( I I>>'4V I I" ', ('I li< (, ( (

h

>> ,,I (

I ) I

( M

'I I

~ I "J, f ff.'I i r I M

r" I f'j lf f ~

.t JI h(M".W (<<4

" I'Mr " It<<llf I>>, '(II( ')j(.

. W 'fl'<<

' ((

jl f(

I I I 'J i)

( iff I, fh) II

((M ~ (f,ri',

I t- r lt tl ~ ( W iW) f(

'I Wh, h'I( I 'hft f 'jll L'h Ii) I fll lll ~ Mh, W ill f Mf( M' ((<<3 M W ) ff f,) tl, h

) f <<>>

'lj)f '

'I a j $ ~ I I M ((4 W . W ~

I' I

III W (, ) I ) , y 5((WW (fj<< ~ r h I hr M M, ~ M)l(" I. '

I

~ ')lt jj Ilfh .5 W W

Mr'. Domenic B. Vassallo March 19, 1984 Page 2 Instructions for evacuation of security personnel, if necessary, following completion of a site evacuation are provided in the emergency procedures.

Integrated doses in the security building are not expected to exceed 5 Rem during the first eight hours following a design basis accident, at which time site evacuation should be complete.

Sincerely, NIAGARA MOHAWK POWER CORPORATION C. V. Manga Vice President Nuclear Engineering and Licensing CVM/SMK:slw

I

~ ~

lq Q