ML19309C641

From kanterella
Jump to navigation Jump to search
Corrections to Revision 1 of Renewal Application for License SNM-1227.Corrections Include Editorial Changes,Addition of Scale to Site Plan Figure D-3-2 & Incorporation of Addl Ref Info Attachment P
ML19309C641
Person / Time
Site: Framatome ANP Richland
Issue date: 03/13/1980
From:
SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
To:
Shared Package
ML19309C637 List:
References
XN-1, NUDOCS 8004090108
Download: ML19309C641 (6)


Text

m.

??..

t ATTACitMENT

SUMMARY

OF CilANCES IN DOCUMENT NO. XN-2 Page No.

Section No.

Change 3.20 3.1.4.5 Inserted several words that had inadvertently been left out of the first line of the last paragraph on this page.

3.32 3.2.2.5(c)

Changed "0.50" percent to "50" percent.

(d)

Deleted Section (repeated (c)).

3.34 3.2.2.6(E)

Added the word "to" after the word "accordin'g" in the first line of the second paragraph.

D-3.3 Figure D-3-2 Added scale.

P-1.3 1.1.1(d)

Added reference to recent submittal.

k O

9 I

l j

9 t

15779

-800409'0108'

{'

ERON NUCLEAR COMPANY, loc.

xn-2 SPECIAL fluCLEAR MATERIAL LICEilSE fl0. if1M-1227, flRC DOCKET fi0. 70-1257 Section/ Appendix / Attachment ID:

Application - License Conditions Rev.

shall be performed in accordance with criteria set forth in Figure 2 of the same Guide.

g) If an unployee nuy have been exposed to greater than 40 ST-hours of plutonium in air in any consecutive 7-day period, or if routine urinalysis exhibits > 0.2 dpn of Pu per 24-hour specimen, additional urinalysis shall be required within one workinJ day following detection. If confirming urinalysis exhibits > 0.2 dpn of Pu, then an in-vivo examination shall be performed within one week.

h) The following action guides and actions sh111 apply:

1) For transportable uranium canpountis, an individual whose urine specimen exhibits a concentration in excess of 25 pg U/t is required to subnit another urine specimen on his first work day following the company's receipt of the result, and at least weekly thereafter until a concentration of less than 25 pg U/t is reached.
2) For nontransportable uranium and plutonium, should the future dose cannitment to an irrlividual's lung (based on in-vivo exanunations) exceed 7.5 ran for the following 12 nonths, that individual will receive in-vivo examinations at least bi-nonthly as long as he continues to work in Oantamirution Control Arcao,' and until that time when the future dose cannitment to the lung for a subsequent 12-nonth period is less thm 5 ran.

Any time that a dose evaluation is necessary, an investigation le as to tJie possible source and cause shall be jointly conducted by the Radiological Safety Supervisor and the IIcalth Physics Can-ponent of the Licensing & Compliance, Operating Facilities Section.

Amendment Application Date:

turch 1980 page No.:

3.20 e

%F14 (N

  • 4

E(ON NUCLEAR COMPANY,Inc.

xn-2 SPECIAL NUCLEAR MATERIAL LICEflSE fl0. SfN-1227, flRC DOCKET NO. 70-1257 Section/ Appendix / Attachment ID:

Application - License Cbnditions Rev.

for relatively urall extrapolation of data, k 8}"11 " D U* "*d df 0.95 at the 95 percent confidence level.

b)

If limited experimental data exist for a similar system and relatively large but reasonable extrapolations are necessary the k

of the systan sinll not exceed 0.90 at the 95 pdrcent con-ggg fidence level.

c) For multi-unit arrays where k is not used as a insis, the number eff of units in the array shall not exceed 50 percent of the calcu-l1' latal critical, number.

l1' The mechanical design of equiprent or storage arrays in which defomition or rearrangonent could result in the loss of a con-I tingency, slull be reviewed by a person ccupetent in mechanimi engineering.

3.2.2.6 Criticality Safety Parameters A) Criticality Data Critical parameters used to establish primary criticality safety limits shall be tused on one or nore of the fol.tcuing (see Section 3.2.2.7 for sources of data currently acceptable to D:xon Ntclear):

1) Criticality parameters obtained directly frcm exrmrimental nmsure-ments.

Amendment Application Date:

March 1980 Page fio.:

3.32 i

mmM --

~ ~ ~ -

EQON NUCLEAR COMPANY,Inc.

xft-2 SPECI AL fiUCLEAR MATERI AL LICf flSE f40. Sf;M-1227, fiRC DOCKET ti0. 70-1257 Sec t i on/ Append i x /A t ta c hriien t ID :

Application - License Conditions D) Reflection Critical values slull be based on full water reflection unless less-tlun-full reflection can be assured under both normal and credible abnormal conditions, consideration slull be given to other reflectors in the immediate vicinity which could result in a reactivity greater than that for a water-reflected systcm.

E) Neutron Interaction Neutron interaction (exchange) between individually subcritical units shall be considered. Consideration of the interaction between units or arrays of special nuclear m1terial truy be arvrm-plished through the use of cmpirical methods such as the Solid Angle and Surface Density methods.

The Solid Angle method is applied according to the constraints in l l' the " Nuclear Safety Guide." TID-7016, Rev. 2, except for the use of the nmunally reflected solid angle acceptance criteria.

The nominally reflected solid angle acceptance criteria is used to limit the allowable solid aryle for arrangenents of individually subcritical units provided tlut:

1) Bourxlary conditions for the spacing between concrete walls and the array are as stated in Table 1 of Reference (b), except that a minimum separation of six (6) inches shall be required;
2) Concrete walls are < seven (7) inches in thickness;

~

Amendment Application Date:

ourch 1980 Page fio.:

3.34

.m., :

_-.m

_ --- r ;

h~

l-r

+

ERON NUCLEAR COMPANY,Inc.

IM.2 p

SPECIAL N'JCLEAR MATERIAL L!CE!5E fio. 52-1227. NE 00CKET h0. 70-1257 sectionnsseedis/Attace cat ID: Attadrumt D - Site Infeatic" g v.

3g~

u.

- Figure D-3-2 Site Plan i

gs

  • n p<

i G

l %

O s

i J4

-J l

J h

i t...._

D'

\\

gM.

O 3

' ?- '

O I

~

d b

h*j3 N

h-I

~R2 y

2' s

x e

E Db #

N

E zu is sa

-a

7 22 3

s a

E!

1; i

{1~

ss y

R

,14 5a; 3::

o

~

[

g gN\\

5%

a

=

r

'l g5 3

y2 g

5 A

s

?

e ES if '

~$f

_[5 553E!

e

$ @f I Ef A I

e

, l

  • E@E g

z a

E

ss x

p s

2 t

F. --

p

,i -

3 c 4

5 E6 c

e

)

~

I 7

o :

E E:

-s:jr Dm Et E

5"!$s;

(

uN

.OE

  1. 8 kh

..3 3*[

U5 j$,d

~

E 1

, 14 E

EE E3

~~

l

, S **

a

\\

D c

e

.t$..

u-

.E

$a

,M m

<n

.a

.h I* I 8

E jj h~$

,S e c J8 e,

!! {p*

bL i

4 l'

E555

~

RE, t"

'\\,

.-I s

.,4 e

,~~~

y (

L.

r

.../

.g

\\.,@

y

=

e c i s

s Es>

T2 R

lg 7

((#

g;5 s

5' C

lj:j er x x :. \\.

E' I

..k

~

m g

O I

o

\\e c===

\\L v Do

5;

~

m a

c2:3 Ej*j M

n s

N b-M N

\\ h-\\.N.

P b

sN th \\

.N Ar ene.ent Application Datei March 1980 P**' "' '

l

EQON NUCLEAR COMPANY,Inc.

xtt-2 SPECIAL itUCLEAR MATERI AL LICEflSE f40. Sf4M-1227, ?!RC DOCKET fi0. 70-1257 Section/ Appendix / Attachment ID:

Attachnent P - Criticality Safety Evaluations Rev.

p)

Intter, W. S. Nechodan (DC) to W. T. Cnow (tmC), dated April 5, 1976, with attachment as stated.

q) Intter, W. S. Nechodan (DC) to W. T. Croa (?HC), dated August 5,_

1977, with attachnent, "Isnendment Application tb. 16 - 8/5/77".

r) Intter, W. S. Nechodan (DiC) to W. T. Crow (?aC), dated September 8,1977, with attachnenti "icendment Application ?b. 16 - 9/8/77".

s)

Intter, W. S. Nechodan (DC) to W. T. Crow (NRC), dated October 18, 1977, with attachnent as stated.

t) Intter, W. S. Nechodan (DC) to W. T. Crow (NIC), dated February 10, 1978.

t 1.1 New Infornution 1.1.1 References a) letter, II. Paul Estoy (DC) to W. T. Crow (IEC), dated tbva&cr 19, 1979, with enclosure (Amendment Application tb.

18, Sections I-5.2.2.4,11-2.15.5 and II-4.6.13).

b) Ictter, Ibbert L. Stevenson (tmC) to II. Paul Estoy (DC),

dated Jarnuy 24, 1980, with enclosure.

c) Intter, !!. Paul Estey (DC) to W. T. Croa (NEC), dated Febnnry 21, 1980, with enclosure.

l d) Letter,11. Paul Estoy (DJC) to w. T. Croa (tHC), dated lurch l'

12, 1980, with enclosure.

i Amendment Application Date:

March 1980 Page fio. :

P,,l r3 %

_a

~~

- - - - =

____