ML060670337

From kanterella
Jump to navigation Jump to search
NMC Presentation on Alternative Source Term - Full Scope
ML060670337
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 03/06/2006
From:
Nuclear Management Co
To:
Office of Nuclear Reactor Regulation
beltz T, NRR/DORL/LPL3-1, 301-415-3049
Shared Package
ML060670035 List:
References
Download: ML060670337 (18)


Text

NMC Committed to Nuclear Excellence

§~rtW Y

f.

Full W-..'.-t-N are]

insource Term am L Scope lh 6, 20036 7

S Committed to Nuclear Excellence I/

..~

I 1

I SC

w.wSupportR.O.in ~

Montcell AST',,.

urpose view larch 2007 in January 2007 background related to i

t

1, J..N Committed to Nuclear Excellence 2

p Project Team Manager of Proj ects:

Nclear Licensing M Poject Engineer:

Nuclear Licensing Ei Pat Burke

[anager:

Gabor Salamon Melissa Limbeck rgineer:

Rick Loeffler Kathryn Shriver gineering Support:

e i,

W 4

W-':.. :-

Ff'.:',:

F"':

,. f-
L.

.0..

X."

e;

  • " \\;NMC Committed to Nuclear Excellene 3

s2:

-22r to < Fi i

g Ff' i

.6-.^ ',: '

W§:-".'*,,<: -. ,

t<;C!ffit'3*

. 't' sp W.,, P.,- f

\\e, r kiP.'

,,i i

S.

% es C.'

f W.'S,.'

5L.;t )..b.;
,,,.

r."',ei,

[Er'.H,-'f.".,;: -, _

n

- -- -u -rcope r

.v.... ;....

L

.-X...e... (..

r> 8; C t 1R

  • ffi-;
  • t;

.X..

. e:

?.

Wi s

<,-Technlcal k t..-.:

i l

f

r.. L L

S.

S.<

d

. n r;:

X, v

v- *_r ^

a i__ h l,"i' Agenda AST Accident Analysis lom Configuration Specification Changes I..

0I

,4 II I

I "I,

Ni pi Committed to Nuclear Excellence p

I 4

-sg e -

+

Syss-r rlr. <

.e,.,;

' f;>

ft4,-

C t_.t_

. o { {

ti4z vgea..-.; ;.*

£9.S.,'t.".'

,;.,-=

g.. ;. -i. f., -

>, j, t f ;.. : D

@'"'S' 9

9 A

A A

n acclctent Analysls wource Term L.ei i ' i t :.

rN'X^;' M. *:

.; - ?.::.-

  • Consistent with RG 1. 1 83

- Compliance Matrix included in license

.amentlmpnt rpniiPt 4W J

A.JJIL.

J L. J.

1..

-'Core inventory

  • Full scope core k

calculation revision inventory using ORIGEN e

ss_

II

.NM Committed to Nuclear Excellence

.4-

,I 5

ident Anaysis Dispersion Factors F

tfF eCalculation previously submitted with AST KAddiin A lsdispersion factors for new receptor

[>loation identified during GL 2003-01 test

[BERM

.i Changes to meteorological data and release height identified in AST-FHA Assumptions Results

j

,Committed to NucleaN sr E

e--

r Excellence

'A'..kccident AAssumptions Results AAnalysis - LOCA e s

't ~

W* Standby Liquid Control (SBLC) model

  • Ste'am line deposition model design considerations, schedule "I.

A I.

Committed to Nuclear Excellence

.f 7

j\\.

i*.

I;Acid ent

.*MSIV Leakag(

V.Exemption Add separate Pathway (incl Exemption to requirements:

"'2

'.2,:.

Analysis - LOCA e / 10CFR50 Appendix J TS requirements for Main Steam uding MSIVs) leakage Appendix J, Option B I

3/4 for Main Steam Pathway leakage c

Committed toNuclear Excellence _

8

s.

,t

r_

w. -:-

r -

w.,,

s

_@ :Rl-.,::a,,

rR X,.

..s'.'s.' Sni..'

,5e Hq 4,

..E, k

.ffi..

,,. ;-w.

r,-:= a N

.,'.\\>:..; '.- !s-.

Vt:AccidexIt ?

.2

, K.

W..

- -r..;.

0 Assumptions

tonservatively

..,.i.,>-=<.,;. X TO................. tO Cs a

- 19 V 91 1 91WCthk z A,.

,.-S.+..: -

. _o,

^ Kesu ts

,.X....

nfz

.W,

> > /

:'_'

i'

(,,

t t ;. ;; :.,

4,....

w t-f or= S ;, E.

M

.'.".""''@."t'

'; Z ' _:

  • i+s-

-t 1 i i.;

'i.':

1,.. i.

W.'.-..:

S r Z o * >
  • 0 D o

-t

,..' e J : '

S t q.

wn._;s

f Knalysis - MSLBA modeled as 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ground I

w...

IIII t

r II II I

1.III Committed to Nuclear Excellen c

I8.

9

Accdent Analysis C

  • Assumptions J

operating case assumes ogas S.

a '

a a

a

L ai tre:atmen sysna Analpi~ss gCRDiuAg)i Dir bypassed
  • Isolated condenser case (includes provision fo:
-r MVP trip)

'Results Committed to Nuclear ExcellM 1 0

.F C:

),. $vr en

Accident AnlyisFl mtions hanges from previously submitted o~reviseu source term andci ispersion

  • .-Will supersede previously submitte(

whn approved

-No impact on FHA currently under re's

.,,.Results V

HiA FHA tactor)

I FHA

'S,iew view Commiffed to Nuclear Excellence

,/

li.

I1 I

'*.4,

r.

o:;_

- 0Control Roomi onfilguration H

t'.:.-

,,.t.

', :"o-., X - '

[',iK

  • fl 4
Relationship to AST analysis assumptions

-o to 7 :s.. 4 '

¢,a*,

Si,, {,

'7'iis^;-..,!,;i.. S.

a

j.:,

if K.\\ i.-

Analysis assumptions testing in June 2003 confirmed by tracer-gas 12

Techlical Specification Changes f :Control-Room Habitability instrumentation

MVP isolation instrumentation SnB LC requirements
Control Room Habitability requirqients-
  • Primary Containment Isolation Valves
  • ITS pages submitted as supplement t.

ttdt Committed to Nuclear Excellenc 13

Thank You

,~

IV Ce

Commited to Nuclear Excellence N.,

Accident Dose Summary Table 2.2-4 LOCA CR Operator Dose Regulatory Source TEDE Limit*

(TEDE)

Internal (Inhalation) Dose 2.74 rem External (Shine) Dose 0.66 rem Total Dose:

3.40 rem 5 rem

(TEDE)

EAB Dose*

1.31 rem 25 rem LPZ Dose 1.72 rem 25 rem

  • The EAB dose represents the maximum 2-hour TEDE over the accident period

Table 2.3-2 MSLBA CR Operator Doses Regulatory Source Term Case TEDE Limit*

(TEDE)

Dose with maximum equilibrium 0.33 rem 5 rem radioiodine

.03re 5rm Dose with pre-accident radioiodine I3.25 rem 5 rem spiking 3.25 rem

_5_rem

  • Per RG 1.183 and 10 CFR 50.67 Table 2.3-3 MSLBA Doses at EAB and LPZ Locations (Doses with maximum equilibrium radioiodine)

Regulatory Location TEDE Limit*

(TEDE)

EAB Dose 0.11 rem 2.5 rem LPZ Dose 0.02 rem 2.5 rem

  • Per RG 1.183 Table 2.3-4 MSLBA Doses at EAB and LPZ Locations (Doses with pre-accident radio~iodine sp ing)

Regulatory Location TEDE Limit*

(TEDE)

EAB Dose 1.05 rem 25 rem LPZ Dose 0.20 rem 25 rem

Table 2.4-3 CRDA CR Onerator Dose Regulatory Location TEDE Limit*

(TEDE)

CR Operator Dose (SJAE 1.70 rem 5 rem Operation)

CR Operator Dose (MVP Isolation) 0.56 rem 5 rem

(TEDE)

EAB Dose (SJAE Operation) 1.73 rem 6.3 rem EAB Dose (MVP Isolation) 0.18 rem 6.3 rem.

LPZ Dose (SJAE Operation) 0.79 rem 6.3 rem LPZ Dose (MVP Isolation 0.08 rem 6.3 rem

  • PerRG 1.183

Table 2.5-3 FHA CR Operator Dose Regulatory Location TEDE Limit*

(TEDE)

CR Operator Dose 4.29 rem 5 rem

(TEDE)

EAB Dose 1.61 rem 6.3 rem LPZ Dose 0.31 rem 6.3 rem