ML20217J578

Summary of 971008 Meeting W/Util in Rockville,Md Re Licensee USAR Rebaselining Project for Plant.List of Attendees & Licensee Handouts Encl

ML20217J578
Person / Time
Site:	Cooper
Issue date:	10/15/1997
From:	Hall J NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9710210184
Download: ML20217J578 (34)

Text

.

@ Houq Gb -Mg g

t UtflTED STATES s

,j NUCLEAR REGULATORY COMMISSION C

't WASHINGTON, D.C. Sh666-0001 k,,,,, j/

October 15, 1997 LICENSEE: HEBRASKA PUBLIC POWER DISTRICT FACILITY: COOPER NUCLEAR STATION

SUMMARY

OF OCTOBER 8, 1997, MEETING WITH NEBRASKA PUBLIC POWER DISTRICT REGARDING THE COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT REBASELINING PROJECT A meeting was held on Wednesday, October 8, 1997, between the Nuclear Regulatory Commission-(NRC) staff and the Nebraska Public Power District (NPPD, the licensee) to discuss the licensee's Updated Safety Analysis Report (USAR) rebaselining project for the Cooper Nuclear Station (CNS). The meeting was held at the request of the licensee at NRC headquarters in Rockville, Maryland. A notice of this meeting was issued on September 25, 1997. is the list of attendees. Attachment 2 is the licensee's handout i

used during the meeting.

l The licensee described the organization, scope, and goals of its USAR rebaselining 3roject for CNS. The entire USAR will be reviewed as part of the project and tie current format and level of detail will be retained. The licensee's goals for the project are to:

improve USAR accuracy; add l

information, as appropriate; ensure consistency of discussions throughout the USAR; and to develop an electronic presentation of the USAR that can be cross-linked to related databases for ease of reference. The licensee's review 4

includes all docketed information related to CNS dating back to the construction phase (prior to 1974). The pro. ject budget is $3 million and it is estimated to require 35,000 man-hours of effort. The current schedule calls for completion by October 1998.

In response to a staff question, the licensee indicated'that separate audits of the project will be performed by NPPD and contractor quality assurance personnel.

The licensee described three categories of information that it is considering removing from the USAR:

information that is no longer part of the current licensing basis; redundant information; or unnecessary detail.

Examples of each. type were discussed. The staff informed the licensee that the NRC has not yet developed a final position on removal of information from the USAR; a recommenda+ ion is due to the Commission by December 1997. The licensee achnowledged that removal of information from the USAR prior to the issuance of NRC guidance on this subject would be at their own risk. However, the licensee stressed that the industry is anxious for staff guidance, and requested that the staff do what it can to expedite the development of the agency's position.

9710210184 971015 PDR ADOCK 05000298

!EC RE CEiyrg ggpy

^

ll l.l!I.l!I,illi.l l. !I.l!I.I u

t The: staff indicated that the licensee's proposed schedule and level of effort

-appeared to be consistent with-the NRC's expectations for projects of this type.

However, the staff did not approve or deny any aspect of the licensee's program.

ORIGINAL SIGNED BY:

James R. Hall, Senior Project' Manager

= Project Directorate IV-1 Division of Reactor Projects.III/IV Office of Nuclear Reactor Regulation Docket No. 50-298 Attachments: As stated cc w/atts:

See next page DISTRI3VTION:

Hard Cooy E-mail Docket File SCollins/FMiraglia (SJC1/FJM)

RZimmerman (RPZ)

PUBLIC EAdensam (EGA1)

JHannon (JNH)

PD4-1 r/f JP!iall (JRH)

CHawes-(CMH2)

OGC FAkstulewicz (FMA)

TJKim (TJK3)

ACRS TBergman (TAB)

EWang (EYW)

TGwynn (TPG)

TColburn (TGC)

JClifford (JWC)

THiltz (TGH)

Document Name:

C0010897.MTS OFC PM/PD4-1 o u LA/PD4-1 NAME JHall/vwf CHawes6m#

DATE /0//f/97 10//d/97 COPY YES/N0 YES/N0

]fC l 1

~

0FFICIAL RECORD COPY

_l a

s' b

~,

e l

.(

2-The staff indicated that-the licensee's proposed schedule and level of effort appeared to be consistent with the NRC's expectations for projects of this type. However, the staff did not approve or deny any aspect of the licensee's program.

4 mes R. Hall, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket.No. 50-298 Attachments: As stated cc w/atts:

See next page l

4 9

i

- - - -. - ~ - - -., -.. ~. -.., -

w_

LNebraska'PublicLPowerCompany-Cooper Nuclear Station cc:-

Mr. John ROMcPhail, General Counsel Lincoln Electric System

• Nebraska Public Power District -

ATTN: Mr. Ron Stoddard P. 0. Box'499 lith & 0 Streets

Columbus, NE 68602-0499 Lincoln, NE 6850B

-Nebraska Public-Power District MidAmerican Energy-ATTN: Mr. P. D. Graham ATTN: Dr.-William D. Leech, Manager-Nuclear-Vice President of Nuclear Energy 907 Walnut Street P. O. Bnx:98 P. O. Box 657 Brownville, NE 68321 Des Moines, IA 50303-0657 i

Randolph Wood, Director Nebraska Department of Environmental-Nebraska Public Power District-Control-ATTN: Mr. B. L. Houston, Nuclear P. O. Box 98922 Licensing & Safety Manager Lincoln, NE 68509-8922 P. O. Box 98 Brownville, NE 68321 Mr. l.arry Bohlken,-Chairman Nemaha County Board of Commissioners Mr. G. R. Horn Nemaha County Courthouse Sr. Vice President of Energy. Supply 1824 N Street-Nebraska Public Power District Auburn, NE 68305 1414 15th Street Columbus, NE68601 Senior Resident inspector-U.S. Nuclear Regulatory Commission P. O. Box 218-Brownville, NE 68321 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite -1000 Arlington, TX 760ll-Ms. Cheryl Rogers, LLRW Program Manager

-Division of Radiological Health'

= Nebraska Department of Health

- 301 Centennial-Mall.. South P. O. Box 95007 Lincoln, NE 68509-5007 Mr. Ronald A. Kucera, Department Director of Intergovernmental Cooperation Department of Natural Resources P.O.: Box 176 Jefferson City, MO 65102

MEETING WITH NEBRASKA PUBLIC POWER DISTRICT OCTOBER 8. 1997 COOPER NUCLEAR STATION USAR REBASELINING PROJECT ATTENDANCE LIST i

IL4iE AFFILIATION J. R. Hall HRC/NRR/DRPW/PD41 J. Clifford NRC/NRR/DRPW/PD41 J. Hannon NPC/NRR/DRPW/PD31 T. J. Kim NR.':/NRR/DRPW/PD33 F. Akstulewicz NRC/NRR/DRPM/PGEB T. Bergman NRC/NRR/DRPN/PGEB E. Wang NRC/NRR/DRPM/PGEB J. Pelletier NPPD

8. Houston NPPD

^

R. Wenzl NPPD E. Perkins Duke Engineering Services R. Stoddard Lincoln Electric Systems W. Leech Mid-American Energy D. Lochbaum Union of Concerned Scientists l

1 i

ATTACHMENT 1 I

-d

- -.. - - -.,. - - _ -.. ~ _ _.

4 1

i l

5 i

f

!i

.v h l~

i.

l E

Ow l-O

.9 0%

o-i.

N b

l W

b r

l 0

M O

Q O,O Q

b lt-

~ J.. -

Z m

~"l Q. mammeW Q

j

.c m.

lL

?

y#A o (f)

M.e cA.

W LQ,WS)S

.ac;:,...za

?

t j

i.; ka :%... a gman'

1

..d:

yg l

q

, d^ t men Ir

[9<$k;y.

(. -

,q i l-

.x. -j

,y

.d

,, ;, ~..

.y uey m

c. c W

, a' k;

, y o

<t e i

I.!-

@. :l43 4, O

g) 3 O

3 i,e a.:q Up m

. 2 I.

o i

,1 hv l

M

?"

x m

l u.

.c

-. g ve e

r.

-e,n. 4

.,s.2,,; [&

. n..

x. wrx.

3 m x

_ u,f

.=

w u m,w...

s

.l uj, ~' s-9 % < s

-.. *r t.

{

,x..;w 4,+..

~

i

... r

.;g j

Ik

.'NQI'd; 'Tk I

4

..q. _ c.

g g

i(

i

. +

. 6.. 2.. t.'-#. me, N' 14.4,

' i..

4

' Kgg

' p- - r : _f;_ v 2

., g e

_ L 6 x.: m a

ATTACHMENT 2

j ___

t

• ol

~

c,

• m,~

-"~

c n

,, _ p'. i s.. ur.n

. y c

a

• y; < '

f ';

f w

/

a u

b

,kl'hV' l::.;-

r_

's

[' ;,

i j:)

7 W;%LMeeti~

-Attehdees x

w./. '

=.

+

3

[,',' J', :

". E i..,

• j ',, ;

,f 1

4'

/..T T K i ^:: f.yltyy.* V

'Q:- *~

T N

... y,

/

,,j war A y y+s;W ypy ms

+ James P. Pelletier, Senior Manager of Engineering, 1

l NPPD

+ Brad L. Houston, Manager, Nuclear Licensing &

Safety, NPPD 1

+ Russ L. Wenzl, USAR Rebaseline Project Manager, NPPD

+ Everett (Chip) P. Perkins, Jr., Manager, Licensing and Configuration Management, DE&S 2

.a_

2.4-____eaA 4.34.,sA-e.A4ed.-a._4 ue_.-..._ss. mas d-mana=#.aahab+

suC En-.ho

-e-wh--i.e---.

--a.m-AAWm g-ed+e.i46,

.-mane a J_

aGa.ms-pmoa..mu ia-.ac.,asme_m s a e-.m.s a.m g ummu.m a me ma.m. vain,a_ma-*.

a.m.

-.ess.~a 4

s._-..

I j

1

?

f

_- (.f.

I T

5 d

1

-A

., g 4

s

_y

=

3 i

~

l y

r_

i c

e w

w e -m %,p.n e

+

I=,

n Mm. },r,@ e.c Q%

O

-. - > =

• e "j W Arn

z pf; a44 d ei M,A d

+..w. *s m - -

-w yy ; re

$...M\\ U5

N '

R

.e l

< e.G ;.

Q ~.g:.

• =

d '.,. 5 3 _[

dJA

'+"'#

-.,>.. : ~x.. u m n ~,

Q y

, y?)^M C '

• y Yh W.4 h

~-N((,;f

• p

,, eu. -. a.,.

,e e-

' ?[t' 7;4.,Y,.b *JJ<,-

..% g3,Y

• f

.s r*

. :s,'

..m. ~Q ',.%,,~ssy' ?

,, ;.. ;, j 9

t.

k*;Q v

-E*DY k.

M

.o e

g O

C O

g(,jn[@,f$ :

[

([]

g. 4 r

e 1

y,9 V

k C/)

<A i

3 3

1 O

O O

'O 1

. q c.$

L o.e,.e, o O

.3 q

m

. z,: -

c a

m w

a O

Y D,

Y

"+"#

6 L

O s

o_

l b, %.

+

s. -

n.,

Wpm e.V...T, 4

4 4

4 4

4 a

v

~

vp n,

k rys h -

s.

yg

. ' ~re we

-9

?* N F]

C

- f

/ 4,,; 2

^ -.'; Is ny& spy,a*I I

e s

Im A

.d

3. s%m. n_

t.t.

r..

(m;)m

%(*-[.,g? [ $.

"u-I,1

~A s

g.

.m l

1%m ; '"v.g : Q l

es yn

,lf -}

Q tf.}s.; ~~

w.

i.,

a t._

~

.n.

p=-m'-Am.

w+7d59** ewes W -

gg nymemm es mp p**e---

e-

=er%--

e

4

\\

1 O

.C_

zi o

T.!

O

.i, C

O

)

G G

g

~

O j

r.,

g-,..- -

< a.

[

l M l.

',is.+

[,\\ ]I,~,$Nlfff$;.,

rLiQW)]W. N@

O>wg m

,, a

g,: s

}

MY m;"!'y A$

Q

. D.,

c

-; /

w l

'y:. g,>

3.t."

O w.n. : /.

g...

u

~;.x w y

c.:p D

i w

g O

m m

u c$

s 1

+

D O.>_

... v,,

. c uq, s, 7.,,

D w

j

} l$

[..l Q

.o_ ea c -

s eu

.u..

r c)

O

$a ws,,

a 4

s-

.s.,.,1,

.;v o

,t x

(

);g U.D,.i

a ii O

Q s

. g. 9..

c Q

.s,

N kh$k N.

.5G w Z

{

e'$., a:.@? -lus,.

i C

r%

a.f ve 7

%m #

n.

f qP_

9

• {

3

,.rg,. y j

.q, VM9vr f

(tkg thiy * ' b i ns e

n l,

- - -. + -

i,-,,-....,........ -, ~., -. - -

. - ~ - - ~ ~ --- ~ ~ -

..--.-q-,

-e,+--,--~.-

..-y

...--e,

,.-+.-,,,-,,.,.--.....o.,w,.,

--_.,...,,..m_,,,.

_,,-...w-

~,r.,,-,.

--<,A.

.au, an-

--,----_swa&

-a 4

.we4~

e A-a

'M"- - -

a-

-!+--+---*----+----^*S--'*-'^-----"J-"-'

'^""#^='"-% " - ' ' -""- ' ' ' ' ' ' ~ ' ' ' ' ' * ^ ' ' ' ' ' ' ' '

- =. -

D

=

1

.h. w. h N E,#a C

4 o

E=

Elaj 1

a-nen 4

)

w Og

=

.e.:

a x

en e N

k 4

83 $

'..' r E

e emumme e

y

}.e?

3.

a.. y O

! {,2-e ammmes Ec[

252!

L......y,-@(U ng..

%./

N"'

4 8

- g gg g g w.

s

.j g wS o

w e

.C r4 ;A gise

r..

ao y

v..,

4. " u t. g 'W{/ ' Ib t, l

,i D' l y,.". '

u -

c.

4,y a

E g s.

" O_ TI E_

j$

q

_ m. e.

.. Ejc Q

.{

ex xs

.u*

N q)

,'($ [G..

gc1a

,.g e

w

..t.

=

d[

.3 p/

j

~

M$

ii-o so u

., e a

-a a.8m p.

O

-8 2

g g -

w r,

_. o g tb i

e

- m-r O h,

[-

i 4

a s

koa c4

,)

- oga, s

(

..z;.

- $ = t -2

[

=

\\;.

~

, v, i,,,3, (p,-9,

\\;.

J

.z

\\,

-t "o.

". j

'-a

,j ei 3

o, x

• i{

...4 i

ie

')

, ", A e

f' sg e

.3 i

s II e

6

'N IO

h 4, '

li.'

+f 3

4.

4 u

f-k 7 4

%.. L - 'L w

(g m_.g gg g-n' i-

.-. _.,... -.~

g y

y

-.-m%

%,-gwp wauw.Ms-

@MM W d6#

m a

n

i*

...9 4

~ -'

.9 F

~-

~ ~ ~ '

i a +

g:; c

• T z.

i- ~

DJ"

., n;;p * '

-4~

+;

._4,

'. 'e .} ? [la;4."ggisI'4.,hffoject<De'scription2_ - _s. n: y a,; a x x :: a.= n-eand)c Gdals j p; gg: e ~ +5w f 6. i iiiy;g K Wgpv TV

• -j{dp@g

+ Project Scope i - Perform a complete review - Major focus on safety areas - Maintain the current USAR format and consistent level of detail 1 I 6 I l I

L e-m N F c) v v-( s. D t I o q) a u> + mC o 4 C CObC L1 c.9 l O <c a m ct m u) v-o

• E C

D C) l t C c L Q) l. r=.r g,, g g g to g .. ca o O.

.. (/)W,ctu jgp!\\

+- = 0 O o C.9

• g dsg l

-3 c) c /J i C/) o c

• ") o s

.a :a CU.o nMe (t3 a % g i m -d 1 1 c, +Q. a p.1 O c o o j, o _a)

i o

o m i w CC

/,

m o o c) O9 c 4 u c _o 2 i.n c) 3 Q. i 4 h .) Q.\\,0 2 (n V.a ,5. c)> ~a i ,g c a) Om .c) n m 1 v. -. 3 L.LJ m l. v.a 0- - i4 C ,L 'A 'f y ..s j .a, . m.?%.i,. *-). 2 I I I I 1

• 4<,

? a 3, y-4.

• 3

.c ,n 1 ~ 'l.

1. .. w.

= ,~ ." " ~ ..,_.........._..,U.'_. ~ '~~

[,4 4 _^ i _ ' g f L._ 1i T E, ,, ~. i I y gy i)# 7lc. .,d :- _ l':'_.;'. .N { } ".c" ~. ,)'. ),,., A sB F B IO ect Des tion -{ lal i s 1 cnp t ~~m q

yw.wy

, n.. ' doi 6gy,p .e pyy Aw . : p = I ,&7lf fQ.jiW A7 L + What doeS USAR Rebaseline mean? 4 l3 + Answer: To bring the USAR up-to-date with i respect to Licensing and Design Bas. . format. ion is in i that impacts the USAR, including l - Plant modifications 1 !l - NRC Staff Safety Evaluation Reports I - Licensee Safety Analyses - Certain commitments s 1 1 j t

i t ..F I h ,g. r,- -] l j ., _,s " " ;.;..w L 5 .j y a a' a?w ero ect oescri tion e

z u.

3 m;- doldgyt.. p i ~ f w. ..m f ;$.- l ..i W 's. Kf

^ ', :s

.;.M. 8Wh+Rl;;#} 'Li x 7 ,s. 3. %QhhilL/ l5 ~z ..y C ~ i p J + Multi-facetted approach - USAR accuracy - USAR completeness i - USAR consistency t 4 ~ . m. i r.. [ . 4. ~ c ' w + Multi-task approach v I f. - some tasks in series l'- - some tasks in parallel I + Well-qualified team i i 9 1 l t i

.a.sn ass. s smuse- .w s--.ss m a m om-- r--w.4 ~~ v u s .mx am-~ns w& G i O v l V) i X j i y) C CU C .o W g .;Q:s l O d X W CU W C CU O g Q) ~ (" O Q) a) .C' L .+ e u) . + * ' o T q) v> l. Q\\ 'c7 t CL c i i s. L_,1 n - EC Ce u _e ,\\ C s ..e sY.h .&n ,. ;y eA ~A (Q O w . y )., ,. '[twf % a 4g1 'r8 I-r' o w.q i C ~ + CG O

p. y C

@?? q) .O .l 5

• 3:.3

4.,. n.

C_ (c nn.

y

..vg,,N %,) Q} .C l - ~. _,... .4o G .x, r. e .a. D D C O .N 4e G) q) q) ~ v.2

. g

af a O ;

ny g 0) t /' mi +e C ?g:7 , w > + C CO C q) g _a r >.m 'O Eg E) 3 . OOM u>.~Eox o. o wa Q 4} s .m E1 a ~ 1;;. ~ e .JJ M 3 E O c) E (-) E @< ~ .G, 0 --) o cl. o cd m.-a n Rq, x.a

.a. u o

OO o we av u u u H., n,;w.x q...,, g g l ,o) .# e,4, e.. g f. ,f, g,' w y, h; h*h, .. :. u. 9, i[$ ^ % i: Qa,l,y,; ^ i.. f -t v-a-A3 1 .u. i i 4;. ..-,-r-.m-..e -.-4,t.

.H, 1 r-i 'I 3 \\ ,.p.... , *. i i s ,,; s - - 4, ^ "3 J f,,,. w:- ,o ? _9; l!b,.39L*Bf6ect Desc4 iption:

l J

n[ " C' 1 *. s. r r;,,.j,I -: . d o!l o g j, w... ' V1 3 '7 s. y me y w,.w

n e

9

,. x

r ::4 :..

n-->y

/ .,,a q . py ~=ys L, e s ( + 1. Commitment Identification l - assemble docket 4 - identify commitments - enter into computer database !i I - determine commitment status L - tumover to Licensing & integrate into ongoing l business ( i i i i I

i t p 6 h 'k ll ..,,,{&.kAaA"*# &;'.l l _, j;a - w: ^ ;'. g %]7' jpp',! PJ6 ject Deschiptioni ~ g-. 7,. c &~n n. 'dology, L 1-VM I pv

w y y

jz USAR Rebaseliri~j*. l 1

$S # '

,,,f L A e a r.; i H ~ A. Addition of material to USAR + review of all source documents i + determination of what affects the USAR L B. USAR Accuracy Review - Statement of l Fact Confirmation

l;

+ grouping of statements of fact c + identification of source & implementing documents j ,I + identif.ication of. inconsistencies 12 i i, l l

+ Opp g ~ e,' w',, :,, g ,..?tt lk NT * [ h .n. a is%;n n . :l ggP: a. l' Q ~ m~:,y.g;p_ # 7; -Bt6j~ecttDdscFiption .I ~ r ,m. . d p u.. p ;w..-,-. n;. --- , n, m.. ._.>.e ogo d W "~ " <^ ] ? g T _,gm . !.:n n,,- ...s.._. u'5m'd,'. f. , jk? s' $ <l ~ r + 2. USAR Rebaseline r sp. C. USAR Rewrite Process + Incorporate all updated material - new/ changes from source doc review - changes based on SOF document inconsistencies - revised USAR drawings j + prepare 50.59's i + assemble backup documents + verification and validation l + complete changes ys t

i

f 4

y, 3 3 9 M...;-;;[;r ..,.. ; hh i$ a -+ w k1 ~[

nW1;amBrOject' Des,3cript.iort 4

o. m, m

t q-. w - c. i m 3

q

7..

-;p dologye-j.'.r fg f $U". -

> 1

,L'

lI fqvJ+ USAR Re aseIIr.viijV'/

sphp = id s. r># i y D. Final Quality Check + sampling of plant SSC's in USAR + vertical slice type review l + comparison with existing plant 4 + scope expansion based on results i i E. Enhance Cooper Configuration i Management Processes 1 l + recommend process changes + ensure USAR is maintained 14 1 i 4

J 4 tr> 1... C t. \\ C g u O u O_ a w

i.

3 y V Q l -4 e c ,o_ j O ~ d C~ i V .o @ ~ g m.b e i c D -d d e u O c C O u 4 ai Q,, d O od ~$ @ Z $ u. m;. Q, c %o s, u O t s ' '.g*;. 3 7 ".- T g Q 1 I .H 02 .,N g ag u l <,.g.. .. o,3 o_ . 0_

g... w

.a q) oom i m.,,. w o o, q) j q.g. @f own$@ t" g O. eo ~ o g,,g m a s.l. u o U j 1 -Hc ql g O C r a gono e n+y:o er t -;g D g m pwc

n;

+=8 eg _"O c c) Eg uJ O d o 'g...;c v u

y; w

i. : uf N. /, o'%s 3 $

a).E o [c uZ a_ 8 u ~ e i~ iiF? i G E T5 ~ Sc< 2c 2 s._ m X. zEC jj ,;..i "

• C

o. wo ih= pis..4 n% h,:,. gh, g).O d

m .. %g ~q) .w w (- 'a. Q. O E ~q) = cDE I-dd ~ p. ~ u g g i y,.n .>. v;. _y k, .. ~ w u,? ,.m a.c 4 M- %a

1. w w u %,"':i+ c o.

j g; at + 4 m:u 4g '.m m, 7, q.. t. Mg > N yg ;vj.y { h;fy - ~ ~ -, .,+,m.am.wu.bg+-w esus.y-a ru sm M -'*ee nam - 'Na+*" ' ~ " '

1 3 g

z. :; e ::].

& **'w ;x p P., ar, : 9x;.n% 'Q4t.3 :_u.p g r;.: ~, a2 v ;. .,L'?'4 Lj) 7 "$ . a. $-al ? bi:l' ,2 T- . s ;, p a;; g a} --...v,,n.: .. 3n,.. y- .. 4=$::p sa.-

ike 0p n

y >el;7 7 q y2MtN:.a#*,PJoject'De.scriptio am c -2 3 m. _?;_ gnlog)y;. g p w i <( m y A v

q

. s ww a e .h'd. h;;f* [L[d I NA. c,,. T Ci ~ ' _ %Li.1 'a :# ,x-Ac; ' i I,.s" i FINAL PROJECT PRODUCTS + Revised USAR {available electronically) i + State-of-the-art Linkage Database + Comprehensive Commitment Tracking System and Database (Integrated Electronic Presentation) I. 16 1

-- E. i m ;;. p ; W @ b. u. J m = y ;: n. ;q q ;/ ;; ')$ [ (3:',if xj.- s q :=,: ; p . x,. %p. 3,. n. ' y Aj%j :(['j';,T. 2 f , V M" . e k, :$ T ~ . pf 0.

1. pt : ' %. ?d. ' i5 d

v. sy-)l g.a a:n*Tc: B.:ro. jectDesc:a1 et. w - r. x ptions~..~ iti . B L a. w:.;~;r. w$-' n,L n n', X - ~ ~ '~~' ?,i.. ~~ p-r1 s.-m r s

• m a-and;e,_,s.,
• 3 w, e, _

g_,- w ffs& W Q. $T &[m!.N4?60f ~

MiY

/ #+ Project ProceddEEfW' P-VM5200-004 P -Ag.' + Station Procedure 0.5 (CAP Program? e. + Screened for Operability /Reportability/ Safety Significance + Track all issues in a database + CNS will address all discrepancies prior to i project completion + Identified discrepancies on CNS Web Page 17

F1 t P., F ~~ n s 5

.2 n

.9 M .9 e i .. y;'6..ya ;G= d - ~ 9 5,,. ~ ,J '} , 1, ;J*p'*' ? , g"#j;k ~ ' q; f3 '}~ t L %.,: s&P]oject DescEiption -

a. c j

6 :4 * -cA# - - j 4 s,- - anCIO$n rg.e , =

.yu

, -,h j?i - j;f*" i l; l Q),:',_;; ~ "~ ... u l USAR REBASELEMG PROJECT OPEN ITEMS - ACCUMULATED i f .sr l 400-350-l l sUSAll Discrepancies 300-250 i l aUSAR Review Questions, 200-l Clarifications ~ I i 150-I l 100-DProject Administratie issues 50-Os = x ~ w a ? M s a 4 a = 2 4 25. l 18 i l l t

F 3 9 6 1 M i -n nB n o oL o a.. C i s t i .i t 1 tn e a 2 r po ^ le e m i t .i e p r ,l D o r 32t c ey o o D f l ^ . s R y.)bW, iaC n n o eA i t n ei 1 t . 2.e t al h ~ D_ . i l i _t n a a a; a ~ r t c ~ t. ', ;s ofo r e D ir c_ aP t od Mr,,e_.vli ~ r f o n f ai vJ t r s opt a c m. ,. j i , o _.P s r n s h e e a s a_.J, P :' y i g d e t 5 c t r n n c h f" s o o u e g + u 4: Mm._w,umft J, 93, gl d n i l eo e n h NRU g a 37y6 i k H 7 ; Y' a.sr,f#[C 4 + 3 . 1rma7^ V' .N b. ,k* '/, . i. 4il !! .I , i;, l\\ l

,u. . m a_,.. ._,j g. i ., g_.h.ONI ^^ ^ % h;, 5.,[.*jh)[d*' e ;; /, m p. -{-e. t x-v m ~. j*, a. ;!:;:_.. ~;;

n.. a.

~ ! r ws* Broj. ect De. son. tion""A p. a, ;; nw s,: ~ e; .;g. 'I4Co ..-.:-:. U+SARL Figures y Qpp,j.:. 3w

ggp semp*y ge-r....

= s.: %, 2. + m.f j 22 fi * + Replacing existing USAR figures with i simplif. d drawings ie + level of detail commensurate with USAR text + Improved legibility j + Drawings controlled under 10CFR50.59 q' drawing control program) + Figures will not be deleted 20 ~

l i i 6 .m..~ r: 4 i ,t'., I hAE *o "' 4 ;--, -j-

1. Qa-P.:.<>ro'ec.t.:Schbdule 2

, ' ~..,.... ' ' r. 2 m+. - j r W. ,vr .n i ..v u-

g y3 4: v

p ~ ~ 'f. g -

,i '

J .,-u,q l3 %g,;',. - q ). ifJ J ; <./ ~ y: ,.. _,, ~. - i' p ,m_ 1997 1996 l f4 Took Nome Stort Fkesh N) D Jl Fl Ml Al Ml Jl Jl Al Sl Gl Nl D Jj Fl Ml AlWl Jj Jl AlSlOl Nl D JlFj ~ ^ PHASE 1: Admin & Planning 3G7. 4/109 PHASE 2: USAR Robesellne 4/2*K 1W1/98 i

1. Commitment Dotatsse M21E 1/30 9 m

g I

2. USAR Rewrite 5f29&

1W1/98 i I j 2a. Ase Secr.on Upd, ses7 774 s um l 2b. Train Updaters 7/147 7/1&7 [ i 2c. Source Document Re 7/28 E Oft 9M g [ 2d. Review USAR Sectior 7/21 E 9f12& g 2e.SOF Confirmation 7/28 7 1001/9 gg 2f Pilot Program 7/28E 10/31/9 g 2g. USAR F.ev'sion Frocr 11/3E 359 gM I l 2h Drscrepency ident & I 7/4 E. 10f1/9i l 2L10CFR50.59 Preparati 1/2 6/91 4/17 S ff 23.Distric Rewbw & Corra 2/9/9t 713/95 m 2k. Final USAR Compa & 32/96 7/3 1/91 m i l issue Robeoehnod USA BG9 8G9 4 Sf3 1 t 3.QualRyCheckof Rebaselir SGr96 9f119 g j

4. Process improve Eval

&G9 E'2&9 g L I f I \\ 21 i

.n \\

g.,, e r j i; g M O M --- ( ] n-.. :e 7, U. ' ?.i :6,;Q p '*gp43,p -

. =: a .. 1.J f,. o. e ,;t;tk' a ,. ~! ~. y ', i[c M [.'f ?,# " A '~,'- j i s-- s y - Q W, __ l% , ? < l ~ ;, * '..?.g { i g , J +4 e+ 54s t. l g;,..

• j s,

2 m, *

g M E M; y y % ~*"'E C _o B j Q g i d n S 37 r

( ~ na . s,., ... + .s,.. .pfs.t g:.. .,1 ,prAnLv r y,w. 4q... j a. s t ist@r...tt addresses . #ggr m oj.e ..~,;.- 1 1*. commitments to the NRC

~

t***. L + Project will meet NPPD goals:

i

- ensure accuracy of USAR rg - add information following 10CFR50.71(e) - improve consistency and clarity :.. text - provide electron.ic presentat. ion 22 I

hftAM USAk . ~ - - - - - theting Boilers One oil-fired and two electrode heating boilers provide auxiliary steam and heat to the plant. They are separated such that a missile should not destroy all three units; however, in event all three units were destroyed, steam would not be needed for an extended period of tine. A portable auxiliary boiler could be brought to the station. -L A A 2.5 Power ceneration Evaluation The following abnormal operational transient analyses have been made for a component failure in the turbine-generator r.ystem and are included in the Station Safety Analysis, Section XIV and the Nuclear Safety Operational Analysis. Appendix C: l. Generator trip (turbine control valve fast closure) 2. Turbine trip (turbine stop valve closure) Turbine trip from high power with bypass n. b. Turbine trip from high power without bypass 3. Pressure regulator nalfunction 4. Closure of the main steam isolation valves a. All valves b. One valve 5. Loss of main condenser vacuum. 9 4 9 6 e e e XI-2-6 07/22/84 m=. ,..w,,ei.>erue.e wwe -.**r-

G. ~ - ~ ~ ~ - ~ ^ ^ l* Bath of the above illustrations are based on very conservative 1, assumptions and ignore additional sources of dilution. Nevertheless, they demonstrate that tritium contributions to the discharge canal from liquid waste releases will be smal.1 e, {* regulatory limits. compared with naturally occurring concer.trations and 2.6 Safety Evaluation i he radwaste-building is located on the north side of the reactor t uildins, abost 600 feet from the tilssouri River. i j in this structure are located below ground level. All the radweste tanks contained The clean up phase separators, which.are part of the radwaste system, are in the reactor building, which will contain their contents in the event of their failure. In the remote event of an 2 earthquake of sufficient magnitude to damage the tanks in the radwaste building the tank liquids are located below gra6e to minimize the effects of such an event (see ] Chapter XII). Since the radweste building and tanks are designed to ' withstand a j Class I seismic occurrence, the possibility that the water may escape the building and run out into the ground through cracks is remote. h Some of the tanks, condensate P ase separators and waste slud e tank are contained in vaults so escape paths would S only be through floor drain piping. retained unless cracks develop in the mat.Thus, the contents of these tanks will be t Even then, the solids will be retained. j Additionally. - there is a 40 mil plastic membrane that completely encloses the radwaste building walls and t ] liquids. is intended to prevent loss of radioactive + 1 I Table IX4 6 shows the maximum capacities of the various radw e tankage and the radioactivity content at design basis fission produc l concentrations. Although Ihose tanks are normally only partially full and a concentrations less than indicated, the ic11owing analysis assumes them to be fu and at design basis concentrations. It rise assumes all liquid contents are lost. i If J11 the waste liquids escape from the radwaste building and enter the river over a period of an hour without absorption by the intervening ground, then 4.4 x 104 i pCi could enter the river. He minimum daily river flow in winter is currently i maintained at 6,000 cubic feet per second. The average concentration of the radioactivity discharged into bli flow in an hour would be - 7 x 104 pCi/ml. Assuming the maximum permissible torcentration o' this mixture is the most limi one of Table 1K.24, i.e.,1.4 x 10** pCi/al, the maximum contribution to annuai radiation dose to individua!9 due to this event would be three area. Actua contribucion due to lesser volung, higher river flow, or lower radioactivity conten j would be less. The annual radiatfin dose permitted by 10CIR20 is 100 mrom per year, j The maximum of three area contributed by an event such as described would amoun3 o 5 % that permitted. Thus, it is concluded that the safety objectiv' h =t'. i 2.7 -Inanection-a d N stina 1 l l' basis during operation of the nuc1rar plantt ite liquid redwaste system is normally -[ thereby demonstrating operability without any special inspections or testir.3 2.8 Nucinar Enferv Onerational Reauir-nts NOTE: Limiting. Conditions for Operation and Surveillance testing requirements stated and listed in this subsection are based on analyses performed -l, at the time of original license application.. For current information refer to the 1. -Technical Spectfications. A station wide BWR systems analysis (Appendix C) indicates that limits must be observed during operation of the liquid radwaste system in any operating state to insure that the releases of radioactive lignid effluents are maintained within the limits established by 10CFR20. The most limiting conditions-for opert? ion are indicated on the matrices of Appendix C. IX.2 18 07/22/96 j[ _ _ECE,. - rm go.e g 4m ?*GM O *" - ~ ~

h.# USAR If tha structurcl int cgri ty of the Radvaste Building valls and mat were postulated to fail in the event of liquefaction, such failure would be manifested by cracks or small fissures in the concrete. Since the entire building structure located below ground is completely enclosed by a forty-mil membrane material, the passage of any radioactive liquid through cracks _ot t~ mall fissures would be prevented. ~ g Additionally an analysis was performed to determine the amount of radioactive release to the Missouri River in the event that gross structural f ai}ttre of the Radvaste Building and contained systems were to occur. This analysis indicated that the activity released vop1d be less than the maximum 4 peruissible concentrations for unidentified isotopes specified in 10CFR20. The data and assumptions used in this analysis are found in ble 11-5-1. i A ^-- The c.haracteristics of the selected design carthquakes are given in Table 11-5-2. 5.2.4 Response spectra for structural Analyses Response spectra are recommenNd for both the maximum probable design earthquake and the hypothetical maximum possible design earthquake. A dynamic analysis vill be made for the major structures. The major structures are designed to respond elastica 11y, using normal allovable stresses without one-third increase and the response spectra, shown in Figure 11-5-7 and 11-5-8 which have been developed from the selected maximum ~ probable design earthquake. The major structures vill be designed using an ultimate strength design and the response spectra, shown in Figures 11-5-9 and 11-5-10, which have been developed from the selected hypothetical maximum possible design earthquake. The response spectra presented in Figures 11-5-7, 11-5-8. 11-5-9, and 11-5-10 vere developed af ter the accelerogram of the N69W component of the July 21, 1952 Kern County earchquake recorded at Taft. California, as reported by the USC&GS (page 100 Murphy and Cloud, 1954). This accelerogram was selected in preference to any other, e.g., one of the 1940 El Centro accelerograms, for reasons of geology, geometry, seismology, and comparison with other response spectra. The July 21, 1952 Kern County earthquake had a Richter magnitude of ).? and an epicentral intensity of HM XI. It was caused by a dip slip (vertical action) along the White Wolf Fault. The depth of focus var estimated at 10 miles, plus 4 miles. The accelerogram used was recorded at Taft, at a distance of 30 miles plus 2 miles from the epicenter. The intensity at Taft was + )M V11. The strong-motion scismograph was located in a tunnel between two buildings. The subsurface conditions consist of 50 feet of recent alluvium (clayey silty sands) overlying sof t sedimentary rocks. The May 18, 1940, El Centro earthqucke had a Richter magnitude of 7.1 and an epicentral intensity of MM X. It was caused by a strike slip (horizontal motion) along a fault. The depth of focus was estimated at 6 to 10 miles. The accelerograms were recorded at a distance of approximately 27 miles from the 11-5-5 su.m -w. A a

L3 E,. v P usa [ In calculating the allowable time required for cooling water flow to the area unit coolers, the following assumptions are made: a. All heat generated by the ECCS pu p motors is convected into the corner room. (This is a conservative assumption since, as the temperature rises, heat will flow into the walls, ceiling, and floors.) b. Assume 2.5 minutes as the time for notora to heatup before l discharA ng heat to the room. i c. Components are maintained at 104*r during normal operation and at .+ '148'r during a LOCA. d. All heat transferred through the insulation of the HPCI turbine ~ steam syste vetted 7nto gey ronm The following equations were used in the analysis: Q-vc At (Eq. 1) l p Where Q - heat required to rais.e. air temperature, BTV/hr v - Vp Weight of air, lbs. i V - volume of compartment 2 p - Density of air, 0.063 lbs/ft At - temperature change, (148 104) - 44*F l c,- specific heat of air, 0.24 BTU /lb 'F Q' - HP x 2545 S.Ill x (1 eff) (Eq. 2) g hr HP eff Where Q' - heat generated by pump operation, BTU /hr HP - rated HP of pump, 1250 HP \\ j eff - motor efficiency of 94.11 (N i Q" - kA (6t) j x (Eq. 3) / 2 Where Q* - heat transfer through insulation, BTU /hr/ft 2

• r k - thermal conductivity of insulation, BTU /hr/ft A-1ft2 At - temperature difference, pipe to ambient, 'T x - insulation thickness, ft.

Q" ' - Q', 1 S + Q", A + Qf 1 S (Eq. 4) / ~ 7 Uhere Q"' - heat transfer to surroundings, BTU /hr / 1 - length of insulated pipe, ft S - external surface of installation, w D 2 A - surface area of turbine, 188 ft A X66 07/22/92 +so--**=-.--g> ,m.,,,,p .4 e m -s-

==+4s

r typicci centin2ntc1 with roletively vsra cummers cnd cold, dry winters. It is situated midway between two distinctive climatic cones, the humid east and the dry west. Fiuctuations between these two zones produce weather conditions for periods that are.:haracteristic of either zone, or combinations of both. I., is also affected by most storms or " lows" that cror.s the country. This causes Omaha period: and rapid changes in weather, especially during the winter months. + Host of the precipitation in Omaha falls during showers or thunderstorms. Of the total precipitation, about 75 percent falls during the six-month period. April to September, mostly as evening or nighttime showers and thundgrstorms. Although winters are relatively cold, precipitation is light, with only 10 percent of the total annual precipitation falling during the winter months. Sunshine is fairly abundant, ranging around 50 percent of the possible in the winter to 75 percent of the possible in the summer. The average date for the last occurrence in the spring of temperatures as low as 32*F is April 14. and for the first occurrence of 32*F or lower in autumn is October 20. The longest freeze free period on record is 219 days in 1924, and the shortest period 152 days in 1885. The average length of the f eeze iree period i.s.188 daya. The 1.incoln and Omaha annual climarological data (Tables 11-3-1 and 11-3-2) give the total number of days of heavy fog / year plus the three months during which the most snow fell, the day on which the asst snow tell and the total amount of snow for that year for the years 1952-1980. \\f J'. A_ A The Aubur_n' Department of Koads has informed the District that the Auburn-Brownville Highway 136 has never been snow blocked for more than two days and that specific incident has only happened once since 1974 l Site accessibility from Brownville is by m.aans of a county road and according to the County Commissioner, this road has never been blocked by snow for more than da 7 With regards to rainfall within the site vicinity, data from the U.S. Department of Connerce - Weather Bureau, climatological summary from 1931 to 1960 for the Tails City. Nebraska, area indicates a maximum 24-hour rainfall ( 1.incoln. Nebraska, areas substantiate this value. Values obtained from total of 6.00 inches. I These areas are north and/or est of the plant site. x From the aforementioned reports, which are summaries of recorded rainfall rates, a rainfall intensity of three inches per hour is indicated as being appropriate for this area. The following documents were also reviewed to determine the rainfall 1. National Standard flumbing Code as suggested by National Association ci Plumbing - 3 eating - Cooling Contractors (PHCC) 1971 edition. Table A which suggests as the maximum rate of rainfall for the Lincoln. Omaha. Nebraska, area as 7.0 inches / hour for a five (5) minute duration for a ten (10) 11-3-2 07/22/87

L EOP0264342 TP.2 l+e V PRV I. l M' T.AUxtuART l STEAti LO ADt mm ggggy d DitTRISLfTION HE ADER h d' D ~ m - N oo-+ -Noo-* ELECTRODE ELECTRODE SolLER BOILER U 1C 1P 10 pg ab db + h, ls=, hs,, lW NW r e Pay Froen AUL STEAM LOAD ? AAINS X hww CONDEWSATE 1 DUPLEX PUMP 4 UNIT WI ~ TANK d DEAEAATOM R Te WASTE M /\\ Prom DEMIN. W ATER BolLER FEED PUMP 8 [ = HEATING BOILER SYSTEM ATTACHMENT A i CXA03959 Y \\ ~ ~ ~ ~ ~ ~ - ~ ~ ' * " * * - ~ " ~ ~ ~ m--

gf.V71" M \\ $DQSt,09 ). I i.I e i. i e

9. )i,1[.$}

1 ,y,,, p, y 1 l !fd N ,.I':=um... n0 I ~< li i swg3. as 11 t.nglin, M, q..y o, y 3s a g 1 e dth1 4 !'7

r. -.

_',pH grep;ti p).id. '(. i I ll..., j!! o .L a =Ii.7 I d L o

ce c.

C n e

4.,j p%,.

j r r (T, [ I,: 1 n L f f h r,5 7 = m % s a. rm.cu pH: j b"-9 9 ,h iN_ (- l 1 p kt 1<, yyan-o r -"I ] j I tbs' r w[][I h a u g:lm'1NIdy,,w ~ p p t e a c e an f g u_g i j i Jp-l n o d J e i "{\\ P ( g jg (O[i~' [ rpj pr$-Ni,mf* ) qMr ~ h ~ lc ! r" g Vr i i. qg! . r. F-ijh u; .tgp i i k5. f 3 vg i L l,I 9 pn

n

~ ,e f;; _ _IR: IE: Er t-* t~ I : t : 1.: t-~ ta t.1 n n t-1 r7 nnn .... -}}