ML20117N711

Proposed Tech Specs,Consisting of Change requests,234 & 107, Modifying Section 5,design Features,To Include Improved STS Requirements of NUREG-1431

ML20117N711
Person / Time
Site:	Beaver Valley
Issue date:	09/09/1996
From:	DUQUESNE LIGHT CO.
To:
Shared Package
ML20117N708	List: ML20117N705 ML20117N711
References
RTR-NUREG-1431 NUDOCS 9609200061
Download: ML20117N711 (33)

Text

.. - -. _ _. _ _ _ _ -

s*

ATTACHMENT A-1 Beaver Valley Power Station, Unit No. 1 Proposed Technical Specification Change No. 234 The following is a list of the affected pages:

Affected Pages:

XIV XV XXI 5-1 5-la 5-lb 5-id 5-le 5-2 5-3 5-4 5-5 5-6 4

I i

)

i l

i j

l i

f 9609200061 960909 PDR ADOCK 05000334

?

PDR i

F DPR-66 l

INDEX BA'S ES SECTION pAGE 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.5 Gas Storage Tanks B 3/4 11-1 3/4.11.2.6 Explosive Gas Mixture B 3/4 11-1 i

DESIGN FEATURES SECTION PAGE 1

5.1 SITE L6CMYl6Al 1

5.1.1 Site Boundary for Gaseous Effluents 5-1 l

5.1.2 Site Boundary for Liquid Effluents 5-1 l

l 5.1.3 Exclusion Area.

5-1 1

5.1.4 Low Population Zone 5-1 5.1.5 Flood Control.

5-1 h

5.2 CONTAINMENT y

4#

l 5.2.1 Configuration.

5-1 l

l 5.2.2 Design Pressure and Temperature 5-4 (5.2.3 Penetrations.

5-4 l

r.1 l

5.

REACTOR CORE

[5.3.1 Fuel Assemblies.

5-4 5.3.2 Control Rod Assemblies.

5-4 l

5.4 REACTOR COOLANT SYSTEM i

,a 4J 5.4.1 Design Pressure and Temperature.

5-5 A

(5.4.2 Volume.

5-5 BEAVER VALLEY - UNIT 1 XIV Amendment No. +66-hNyttY hl0 fYI

o DPR-66 INDEX l

l l

DESIGN FEATURES i

SECTION pAgg K/SFf(5.5 EMERGENCY CORE COOLING SYSTEMS 5-5 l

l r.7 0

FUEL STORAGE

~

l l[5.6.1 Criticality.

5-5 5.6.2 Drainage.

5-5 lbGLGTG 5.6.3 Capacity.

5-6 5.7 SEISMIC CLASSIFICATION 5-6 5.8 METEOROLOGICAL TOWER LOCATION.

5-6 1

ADMINISTRATIVE CONTROLS I

SECTION PAGE 6.1 RESPONSIBILITY 6-1 l

i 6.2 ORGANIZATION 6.2.1 Onsite and Offsite Organizations.

6-1 6.2.2 Unit Staff.

6-2 6.3 FACILITY STAFF OUALIFICATIONS.

6-5 6.4 TRAINING 6-5 6.5 REVIEW AND AUDIT 6.5.1 ONSITE SAFETY COMMITTEE (OSC) 6.5.1.1 Function.

6-5 6-5 6.5.1.2 Composition.

6.5.1.3 Alternates.

6-6 6.5.1.4 Meeting Frequency.

6-6 BEAVER VALLEY - UNIT 1 XV Amendment No. -te9-(hfejkrs& LAlHbh

DPR-66 6

Fiaure Index FIGURE TITLE py g 2.1-1 Reactor Core Safety Limit - Three Loop 2-2 Operation 3.4-1 Dose Equivalent I-131 Primary Coolant 3/4 4-21 Specific Activity Limit Versus Percent of Rated Thermal Power with the Primary Coolant Specific Activity > 1.0 gCi/ gram Dose Equivalent I-131 3.4-2 Beaver Valley Unit 1 Reactor Coolant 3/4 4-24 System Heatup Limitations Applicable for L

the First 16.0 EFPY 3.4-3 Beaver Valley Unit 1 Reactor Coolant 3/4 4-25 System Cooldown Limitations Applicable for the First 16.0 EFPY t

3.6-1 Maximum Allowable Primary Containment Air 3/4 6-7 l

Pressure Versus River Water Temperature l

l B 3/4.2-1 Typical Indicated Axial Flux Difference B 3/4 2-3' l

Versus Thermal Power at BOL.

B 3/4.4-1 Fast Neutron Fluence (E>l Mev) as a B 3/4 4-6a l

Function of Full Power Service Life l

l B 3/4.4-2 Effect of Fluence, Copper Content, and B 3/4 4-6b f0F Phosphorus Content on ARTNDT Reactor Vessel Steels Per Reg. Guide 1.99 B 3/4.4-3 Isolated Loop Pressure-Temperature Limit B 3/4 4-10a Curve l

5-lb f5.1-1 Site Boundary for Gaseous and Liquid l

f Effluents for the Beaver Valley Power l

Station

(

5.1-3 Exclusion Area - Beaver Valley Power Station 5-id i

5.1-4 Low Population Zone - Beaver Valley Power 5-le/

Station f

5.1-5 Gaseous Release Points - Beaver Valley Power 5-2 Station 5.1-6 Liquid Release Points - Beaver Valley Power 5-3 /

i Station MikTE a

BEAVER VALLEY - UNIT 1 XXI Akendment No. t$t-OPCf'C3ett' lab,Tb

4 5.0 DESIGN FEATURES q

5.1 SITE SITE BOUNDARY FOR GASIOUS IFFLUENTS 5.1.1 The site boundary for gaseous affluents shall be as shown in l

Figure 5.1-1.

Release paths are shown on Figure 5.1-5.

gg SITE BOUNDARY FOR LIOUID EFFLUENTS M/7//

5.1.2 g g j j Figure 5.1-2.The site boundary for liquid effluents shall be as shown in Release points are shown on Figure 5.1-6.

EXCLUSICN AREA 5.1.3 The exclusion area shall be as shown in Figure 5.1-3.

4

'.74 POPULATION ZONE 5.1.4 The low population zone shall be as shown in Figure 5.1-4 FLOOD CONTROL 5.1.5 The flood control provisions (dikes, levees, etc.) shall be designed and maintained in accordance with the original design pro-visions contained in Section 2.3.2.2 of the FSAR.

5.2 CONTAINFENT CONFIGUR.CION 5.2.1 The reactor :enta1=ent building is a steel lined, reini:::ed concrete building of cylindrical shape, with a dome roof and hari..g the following design features:

MNb a.

Nominal inside fiameter = 126 feet.

5.

Nominal inside het;ht = 135 feet.

Minimum -hickness of cencrete valls =. 3 feet, d.

Minimum thickness of :encrete roof = 2.5 feet.

I IA*.T R. AL L EY f."***

Amendment 'lo. CC Ip) ff[dM

1. /

s' INSERT 1 l

l Ss1 SITE LOCATION The Beaver Valley Power Station Unit No. 1 is located in Shippingport Borough, Beaver County, Pennsylvania, on the south bank of the Ohio River.

The site is approximately 1 mile southeast of Midland, Pennsylvania, 5 miles east of East Liverpool, Ohio, and approximately 25 miles northwest of Pittsburgh, Pennsylvania.

The exclusion area boundary has a minimum radius of 2000 feet from the center of

(

containment.

l~

l i

l l

I l

l l

5.2 CONTAINMENT (Continued)

CONFIGtTRATION (Continued) e.

Minimum thickness of foundation mat = 10 feet.

hEL E7E i

f.

Nominal thickness of vertical portion of steel liner = 3/3 inch.

l l

g.

Nominal thickness of steel liner, dome portion = 1/2 inch.

i k

0 h.

Net free volume = 1.8 x 10 cubic feet.

I l

l l

l 3?.A'.~:.R 'IA;;IT

.7:: ;

i-;s amendment."o. 'O Oroposeof v)or ll )

ey

i SITE BOUNDARY FOR GASEOUS AND LIQUID

• EFFLUENTS FOR THE BEAVER VALLEY POWER STATION 9

\\

ml3 4

\\

g g

r.! I i

E Midland i..*..*.9.!

1 i

K m

.N-

?e 8

p f.

~l Y

f; V ff:

y

+, %. l'y[,c \\

4"* :ji N

j y

g

^

g.

m sg

9. 8,

• h.

2 Q

?

<OHlO RIVER' k"

s p

9;.

g x

,,,, u e......... -

e

~m.i lj Yh 4

7 W

5 MILES

...../

- ~ ~ ~ /

4 1

\\

\\

y

,m, i

s s

x 3"

Shippingport

%s%g

% e * * *,,,,

?

A

%g%

g

• The Site Boundary g

for Liquid Effluente does

%g not include the areas over g

the Ohio River.

W i t h t h i es g

r ai ept t on, the Site bou nsl.a r l e s for I.I go escou as and 1Iquid eiiluents are E W m 3 Site Bourutary-Elliuents

-DitGClion Of Dtalpage-LN

i 4

4 I

~-

i

.r!!

c li

)

t l

'!j j

!s

%T l

i b, \\%* ~ #

• y 8

9 l

1. 'f j '

y ff2 f

.~

2 Y%

5

-~

l I

l l

9 1

=

0 0?'

XP.

l o

1. s f

A

=

K N

j f

2

,y l

l\\

b kt

bidA.s

/

i

~

l f

h lli

.i l

s h

\\[';l q~'.;.

$l

'sN;'l e

.s;.\\ \\ $

~

N

.I;

]ljy'}

M$

i i

i T.00377. 5.1-3 3-.;._, m.,;,- -

5

.'s Amendment "o.

C.'

g Dtht e

e ao e e e

e me e

-. ~ -. -.. -.

2 i

. w r-

.a.-.

)

'~ '

'.g l

*( )\\ 1 i,

.l

~

11

.\\

l

_ A r -- b

'--~. \\

'}

l.'

/-

--/.,/.N

~;%

h,t j t - /, <; %

2

"?

1

~

s 8

y%,

outor:LLt

\\

l.s. -

. - r 3.__.

g.

s

\\'C~PcQ,.[sl4-,i i

l 9

12 _ _ '

i,,.

i a,

x.

3 b

.f1 L

s

- nl N

Li

'f*

\\._,s

,_. d= -

\\

-.~

4 t.

2

\\

f/

{

\\

m

,{

=

i 1,

f.

8",_-' '

)

's.,,

t i

1

,/'

0 L

=

g g

N /;

i

.e M

\\

---Q

\\[

J.p-.

. A

,s,,-

f-G

'e z, g, AJC t ; -

'Q*%g (

'-4.,,,'

• ' j CfDggTxt m,

s j

j Sc

'/

h,

^

. RCN

\\

ant,.4xk l

(, #/.

~ pr

/ s.

\\

4s o

.v-h fl

%- a.=:

't

\\

_h h, ' )

k Q,

~

l'%

N<

)

. {

/

~- :

$lttPM.1CPct? - (

)

)/

N q

.s

/

.f

~M N_ C_

j.,f f e d

c- ' k..

.u e c;:.: ; I' li-

's 1

N.cn x(SE:d"r 4 y-

!/

N.)Q)%QAh4$.

i s

s,

..w n.,

s. -

t s.

1' s

i i

\\

. usc:.w, l

II g'

y ['

C'.2 ; '.s r' %

D,, ~^{/ /

w;%

4 ;. s 4

4 g.

i ys N, ' s

'__ }\\, I

t..

-s g%

g /C, li

~

,,22,.

i 3

l

-ls.,.',,,.f~' '., \\

,).,'ys

' %. t.

N ' ':i-i

" ~ ~ ~

1

\\

1 F

e, j

s s

j'

//

s %)

,g; 4-ij

.( \\

l

.. g "

_ l

, IM,1 )

14A$3 V' ~-

,s

' I"I'i3 -

'. _ ~ ' '

u i

I h

@ 3 tecreati:n,teta J.

I d

.,, /

($ c fe ce!

8 8

t 8

.,;w 7cr;.;. ::n :::.T

,~ i i

m.,,,,,,w r::::?.I !.N 1

3-5 4,

4 q

7 TJRI 5.1-4 g

3, e

3I./s*/IR 7 d.:.IY

'.3:!.

5 *. e eneeM "0. "

Geleh)

I i

l T GGI 5.'-5 i

DISCHARGE POINTS - CASEOUS '4ASTES i

30'

\\

V.:nt ilation V ent

}l

[

Reactor 31dg./SLC15 Vent 15h 5' l

~

/

/

i

/

j

/

di C

V

~7 l

a Containment Ventilation Syst em (Containment Air Normally recirc.-not vent ed) f Auxiliary Building

/

l Ventilation Syst em - /

4aseous.astas ta i

Exhausts Cooling Tower; Air Ejector i

t CASECUS RELEASE POIY:'S - 3EAVER VALLEY PCVER STATICN Tig2:e 3.1-5 l

t E

i 4

l 3I.i"IR 'a.LLI? - 7'!! *.

3-

.orendment

~

(Deleh )

\\

\\

i is Ej

.)8

9 s.

av

=2 s.:

"2 E I "..

i%

2"!

2W"3 2 2 d

s!s i

=2

==

==-

1;s

=:g:t as-

=;

~3 da!

r d._

3-E-

I

i

J

.si ma a

ssx:

sse l I]

~.m.

snw

-ww s a-s.

en w ~ ~,.

3 E

==y

=

i f

a.

U g.

-in

$W fI

$. 5 ja3 a52 z

l

{

"3 y

3:.

v l

IIS Ck

$53 w

=

=,

l,;

a 5

g

"$l %

g 3

~

i J

,f

'5 1 222 3

3 l

a.

=

y2 i

g 18.s i ll t

l ll

=

1 III I L

I J

=

2!

2 2l j-3

S

)I h.g s-

=

4 L8 i

a ed-g O

U f

.E-t

.33 3

)

n J-23..

\\

si

.l

-2 a

s.g.

N af r-

• • l B

!8 232

., l u

++

<j e

gnm

)

c:

y

/E&'

{

m u,

~'

w N

N si IIct Q

d. S \\

il l

I Q

' i t;I s.;

s O

Iy' en-t

)

x i

s2 Ar endment "o. 9 1.. ' 7

'.:n.

Dt)t,h)t)

DPR-66 DESIGN FEATURES

'[DESIGNPRESSUREANDTEMPERATURR 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 45 peig and a temperature of 280*F.

PENETRATIONS 5.2.3 Penetrations through the reactor containment building are

' designed and shall be maintained in accordance with the original design provisions contained in Section 5.2.4 of the FSAR with l allowance for normal degradation pursuant to the applicable (Surveillance Requirements.

b anCTOR CORE D.l FUEL ASSEMBLIES

-5 2_i The reactor shall contain 157 fuel assemblies.

Each assembly shall consist of a matrix of aircaloy clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO ) as fuel material.

Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases.

A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

f,2,2 CONTROL ROD ASSEMBLIES

" 2.0 The reactor core shall contain 48 full length and no part length control rod assemblies.

The - full length control rod assemblies shall contain a nominal 142 inches of absorber material.

The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium.

All control rods sha11 be clad with stainless steel tubing.

BEAVER VALLEY - UNIT 1 5-4 Amendment No.

f UropndukJ.y)

~

DPR-66 i

DESIGN FEATURES 5.k REACTOR COOLANT SYSTEM DESIGN PDMSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:

4 a.

In accordance with the code requirements specified in Section 4.2 of the

FSAR, with allowance for normal degradation pursuant to the applicable surveillance Requirements, b.

For a pressure of 2485 psig, and e

D&LETE c.

For a tsaperature of 650*F, except for the pressurizer which is 680*F.

4 f

VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 9370 cubic feet at a nominal Tavg of 525*F.

5.5 EMERGENCY CORE COOLING SYSTEMS 5.5.1 The emergency core cooling systems are designed and shall be maintained in accordance with the original design provisions (contained in Section 6.3 of the FSAR with allowance for normal Megradation pursuant to the applicable Surveillance Requirements.

5". 3 4,4 FUEL STORAGE f,3,l CRITICALITY I".0.1

[f/d66 I The spent fuel storage racks are designed in a three region configuration.

Region 1 racks are of the poisoned flux-trap type 4u/77/

with the storage celle arranged at 10.82 inch pitch.

The Region 2 IA/St.g and Region 3 racks are of the poisoned non-flux trap construction with a call-to-cell pitch of 9.02 inches.

The fuel will be stored in accordance with the provisions described in UFSAR Sections 3.3 and 9.12 to ensure a kaff equivalent to 50.95 with the storage pool (filled with unborated water.

DRAINAGE f.% 3

. 0.2 The spent fuel storage pool is designed and shall ce maintained to prevent inadvertent draining of the pool below elevation 750' - 10".

BEAVER VALLEY - UNIT 1 5-5 Amendment No.

hepth NOMt

)

INSERT 2 5.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a.

Fuel assemblies having a maximum U-235 enrichment as set forth in Specification 3.9.14; b.

K.gf 5 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in l

UFSAR Section 9.12; I

l l

c.

A nominal center to center distance between fuel assemblies l

placed in the fuel storage racks of 10.82 inch for j

Region 1, with 9.02 inch for Regions 2 and 3; l

l d.

Fuel assembly storage shall comply with the requirements of l

Specification 3.9.14.

l 5.3.1.2 The.new fuel storage racks are designed and shall be maintained with:

l

[

a.

Fuel assemblies having a maximum U-235 enrichment of 4.5 weight percent; b.

K gf 5 0.95 if fully flooded with unborated water, which l

includes an allowance for uncertainties as described in i

UFSAR Section 9.12; c.

K.gg 5 0.95 if moderated by aqueous foam, which includes an allowance for uncertainties as described in UFSAR Section 9.12; l

d.

A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.

l t

l 5

i

_. _ ~

DPR-66 DESIGN FEATURES U3 CAPACITY 5.'.

The fuel storage pool is designed and shall be raintained with a storage capacity limited to no more than 1627 fuel assemblies.

5.7 SEISMIC CLASSIFICATION 5.7.1 Those structures, systems and components identified as I maintainedCategory I Items in Appendix "B" of the FSAR shall be designed and to the original design provisions with allowance for normal degradation pursuant to the applicant Surveillance MLETE Requirements.

5.8 METEoRoLocIcAL TOWER LOCATION 5.8.1 The meteorological tower shall be located as shown on (Figure 5.1-1.

)

BEAVER VALLEY - UNIT 1 5-6 Amendment No.

l OtoposdJedQ)

ATTACHMENT A-2 Beaver Valley Power Station, Unit No. 2 Proposed Technical Specification Change No. 107 l

The following is a list of the affected pages:

Affected Pages:

XIII XIV 5-1 5-2 5-3 5-4 5-5 5-6 5-7

l l*

NPF-73 INDEX l

BASES 1

SECTION PAGE l

3/4.9.12 AND 3/4.9.13 FUEL BUILDING VENTILATION SYSTEM.

B 3/4 9-3 l

3/4.9.14 FUEL STORAGE - SPENT FUEL STORAGE POOL.

B 3/4 9-4 3/4.10 SPECIAL TEST EXCEPTIONS 1

3/4.10.1 SHUTDOWN MARGIN.

B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION l

LIMITS.

B 3/4 10-1 3/4.10.3 PHYSICS TESTS B 3/4 10-1 3/4.10.4 REACTOR COOLANT LOOPS B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM-SHUTDOWN.

B 3/4 10-1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS.

B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS B 3/4 11-1 DESIGN FEATURES SECTION PAGE 5.1 STTE LMAT}AA

['5.1.1 Site Boundary for Gaseous Effluents.

5-1 5.1.2 Site Boundary for Liquid Effluents.

5-1 5.1.3 Exclusion Area.

5-1

! 5.1.4 Low Population Zone 5-1

%i k

5.1.5 Flood Control.

5-1

%J k

5.2 CONTAINMENT 5-1 5.2.1 Configuration 5.2.2 Design Pressure and Temperature 5-6 k,5.2.3 Penetrations.

5-6 BEAVER VALLEY - UNIT 2 XIII Amendment No. 70

$f0f6Sh N0Y6 b

l I

NPF-73 INDEX DESIGN' FEATURES SECTION PAGE

, l T. 3-HHHH REACTOR CORE

[5. 3.1, Fuel Assemblies.~.............

5-6 5.3.2 Control Rod Assemblies.

5-6 l

1

[

g 5.4 REACTOR COOLANT SYSTEM h 1' 5. 4.1 l

Design Pressure and Temperature 5-6 y

5.4.2 Volume.

5-7 i

l

( 5. 5 EMERGENCY CORE COOLING SYSTEMS..........

5-7 f.3 4,4-FUEL STORAGE

'[5.6.1 Criticality.

5-7 5.6.2 Drainage.

5-7 5.6.3 Capacity.

5-7 44 5.7 SEISMIC CLASSIFICATION 5-7 A

(,5. 8 METEOROLOGICAL TOWER LOCATION.

5-7 I

ADMINISTRATIVE CONTROLS SECTION PAGE

'6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS.

6-1 6.2.2 UNIT STAFF.

6-1 6.2.3 INDEPENDENT SAFETY EVALUATION GROUP (ISEG).

6-2 l

6.3 FACILITY STAFF OUALIFICATIONS.

6-6 l

BEAVER VALLEY - UNIT 2 XIV Amendment No. at-(fhf& Y0tYoSh

l 5.0 DESIGN FEATURFS l

.1 SITE 1

l SITE BOUNDARY FOR GASEOUS EFFLUENTS 5.1.1 The site boundary for gaseous effluents shall be as shown in Fig-ure 5.1-1.

Release paths are shown on Figure 5.1-2.

SITE BOUNDARY FOR LIQUID EFFLUENTS i

5.1.2. The site boundary for liquid effluents shall be as shown in Fig-

)

ure 5.1-1.

Release points are shown on Figure 5.1-2.

EXCLUSION AREA s

.hL./5.1.3 The exclusion area shall be as shown in Figure 5.1-3.

lm$

LOW POPULATION ZONE 5.1.4 The low popriation zone shal'1 be as shown in Figure 5.1-4.

FLOOD CONTROL 5.1.5 The flood control provisions (dikes, levees, etc.) shall be designed (and maintained in accordance with the original design provisions contained i

Section 3.4.1 of the FSAR.

5.2 CONTAINMENT CONFIGURATION l

5.2.1 The reactor containment building is a steel lined, reinforced concrete i

building of cylindrical shape, with a done roof and having the following design features:

a.

Nominal inside diameter = 126 feet.

k b.

Nominal inside height = 185 feet.

W i

g c.

Minimum thickness of concrete walls = 4.5 feet.

I b

d.

Minimum thickness of concrete roof = 2.5 feet.

4 e.

Minimum thickness of foundation mat = 10 feet.

l f.

Nominal thickness of vertical portion of steel liner = 3/8 inch.

g.

Nominal thickness of steel liner, done portion = 1/2 inch.

f kh.

Minimum free volume = 1.73 x 10s cubic feet.

i j

BEAVER VALLEY - UNIT 2 5-1 (fropesedN*t0'*.)

^

8 i

i s

l I

INSERT 1 51 SITE LOCATIQ){

The Beaver Valley Power Station Unit No. 2 is located in Shippingport Borough, Beaver County, Pennsylvania, on the south bank of the Ohio River.

The site is approximately 1 mile southeast of Midland, Pennsylvania, 5 miles east of East Liverpool, Ohio, and approximately 25 miles northwest of Pittsburgh, Pennsylvania.

The exclusion area boundary has a minimum radius of 2000 feet around the Unit No. 1 containment building.

1 l

l l

l 4

l

.-.,,-~~,.---.-------n,.u

-,<.-~~----..~~as.--.----.a.-

u.s

=~..x

.>-x.

s

-a

___...-_w j

v l

4=

-+p

% ~ ~2 $

0 e

b

!i e

,,* i c

'x s

ts

/

I i*

i a1 0

\\

g

+

to g

i E t

/) *\\

1 4:8 b!<

a:

i p

I w

=!

I 5

80 l

30 I

L I

gJ

(

j

=

a i

8 sj

!8 s

E;l l

v l

"si s

sil p16

,e

<l

.t 7

.. e,;

I.

/

4

]

/ il

• 2 j

8

1. 5 I

gm

,/

i; a

.n

=2

< p ::

E

1. i!~.

y a

E E

g*

j 5

f t'.a2 I

g j*j;:1 E

Q I

p

=

l E'

)

E :1.: 3 p

pm y, l

=

O o

i,

.h 5' 8 a a

1

)

SEAVER VALLEY - UNIT 2 5-2) pg 1

Unit 1 Blowdtwn

~

To Cutfell Structure N'

f Cooling Tower 4

l Unit 2 Blowdown Unit No. 1 i

4 i

e Unit 1 and 2

\\ Process Vent 4

E1. 1210 t

i i

Decon. ailding Vent Exhaust

]

Including Waste Gas Storage Vault Vent Exhaust

}

i E1. 415 l

Elevated Release 1p fl. 449 i

Unit 2 Liquid Effluent to Unit i Ventilation Cooling Tower Slowdown Vent j

E1. 820 I

4 d

Turbine 1 ding Vent h

E1. 844 (Note 2)

Unit 2 Liquid 108" Cire. Water Condensate Polishing Effluent to Unit 2 {

Discharge Lines i

Building Exhaust Coeling Tower Unit 2 E1. 820 Blowdown twdm l

/

108" Cire. Weter Supply Lines EDFES 1.

Release point for Turbins Building drains j

is the Ohio River, east of the intake l

structure.

Coeling Tower 2.

Representative exhaust point for 10 roof Unit No. 2 exhavet outlets.

+

~

FIGURE 5.1-2 RADI0 ACTIVE GASEOUS AND LIQUID RELEASE Po!NTS -

BEAVER VALLEY POWER STATION UNIT 2 BEAVER VALLEY - UNIT 2 5-3 (belsk)

l.'

l l

/

l

/

i s

\\

l

\\s.

/

i eg6

).

FIGURE 5.1-3 EXCLUSION AREA - BEAVER VALLEY POWER STATION UNIT 2 BEAVER VALLEY - UNIT 2 k

1

j 1

i i

l 34

/

g O

l l'

4 OHIOVILLE BRIGHTON A

g IeD BORO 4[

j

+

~

M

/

IM

[sEAvtR L_a i

sero 1

l lz INDUST

/

Z g

80R0

\\

j l

w p

\\

i a

r l

i]

TTER

,/

CENTER 7

g no o j

\\rs i

,+

Y l

sono RAC 00N

/g i

ag I V) r

\\

\\

l l

/

\\

Z

\\

/

i

~

N:'.*l'"

/

\\

j

@l GREENE gi j

/

\\

j _ _ _3 l

,s' 5

\\

I INDEPENDENCE w

1 3l HANOVE;i

}

/

.1 i

/

FIGURE 5.1-4 LOW POPULAT:0N ZONE - BEAVER VALLEY POWER STATION UNIT 2 5-5 BEAVER VALLEY - UNIT 2 (belefe)

l l

NPF-73 i

DESIGN FEATURES 4

l

[DESIGNPRIBSUREANDTEMPERATURE 5.2.2 The reactor containment building is designed and shall be I maintained for maximum internal pressure of 45 peig and a temperature Iof 280.0*F.

1 j 14N.ETG PENETRATIONS 5.2.3 Penetrations through the reactor containment building are designed and shall be maintained in accordance with the original design provisions contained in Section 6.2.4 of the FSAR with allowance for normal degradation pursuant to the applicable LSurveillance Requirements.

f, A

-s rt-REACTOR CORE i

l D./ rUEL ASSEMBLIES 0.0.1 The reactor shall contain 157 fuel assemblies.

Each assembly shall consist of a matrix of aircaloy clad fuel rods with an j

initial composition of natural or slightly enriched uranium dioxide (U0 ) as fuel material.

Limited substitutions of airconium alloy or 3

stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used.

Fuel l

assemblies shall be limited to those fuel designs that have been analysed with applicable NRC staff approved codes and methods and j

shown by tests or analyses to comply with all fuel safety design bases.

A limited number of lead test assemblies that have not completed representative testing any be placed in non11afting core l

regiena.

j Q,1 CONTROL ROD ASSEMBLI42

{

The reactor core shall contain 48 full length and no part i

length control rod assemblies.

The full length control rod i

assemblies shall contaia a nominal 142 inches of absorber material.

j The nominal values of absorber material shall be 80 percent silver, i

15 percent indium and 5 percent cadmium.

All control rods shall be clad with stainless steel tubing.

5.4 REACfGE CODIAMT SYSTEM I

DESIGN FRESSDRE AMD TEMPERATURE i NN 5.4.1 The Reactor coolant System is designed and shall be maintained:

s a.

In accordance with the code requirements specified in Section 5.2 of the

FSAR, with allowance for nor=al j

degradati n pursuant to the applicable Surveillance i

Requiremento, I

j i

BEAVER VALLEY - UNIT 2 5-6 Amendment No. -

(fropendtJoeQ)

NPF-73 DESIGN FEATURES 5.4 REACTOR COOL &MT SYSTEM fContinued) b.

For a pressure of 2485 peig, and For a teasperature of 650*F, except for the pressurizer which c.

is 680*F.

T>ELGTE 5.4.2 The total water and steam volume of the Reactor Coolant system is 9370 cubic feet at a nominal T.,, of 576*F.

s.s mzaGENCY CORE COOLING SYSTEMS 5.5.1 The emergency core cooling systems are designed and shall be maintained in accordance with the original design provisions contained in section 6.3 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.

f3 o

w..

m.

-..n-.....

K 3.1 MW/UL ITV

[6/4M~6 (3.6.1 The spent fuel storage racks are designed and shall be

/v/77/

l maintained with a minimum of 10.4375 inch center-to-center distance yggggy M between fuel assemblies placed in the storage racks. The fuel will be stored in accordance with the revisions described in FSAR sections 4.3 and 9.1 to ensure a k.a equ. valent to 50.95 with the storage pool l(filled with unborated water.

DE&IM&fsE

f. 3. [

The spent fuel stors,ge pool is designed and shall be I maintained to prevent inadvertent draining of the pool below elevation 751'-3".

CAPACITY C 1.3

+r++

The fuel storage pool is designed and shall be maintained I with a storage capacity limited to no more than 1088 fuel assamblies.

[5.7SEIEMICCL&BSIFICATION 5.7.1 Those structures, systems and components identified as

' Category I items in Section 3.7 of the FSAR shall be designed and maintained to the original design provisions with allowance for DMETI normal degradation pursuant to the applicant surveillance Requirements.

s.a METEDROIDGIC&L TOMER IDC& TION The meteorological tower shall be located as shown on rigure (5.8.1 5.1-1.

BEAVER VALLEY - UNIT 2 5-7 Amendment No.

Uroped Weeduy )

INSERT 2 5.3.1.1 The spent fuel storage racks are designed and shall be j

maintained with:

a.

Fuel assemblies having a maximum U-235 enrichment as set forth in Specification 3.9.14, i

b.

K.gf 5 0.95 if fully flooded with unborated water, which includes an -v;.owance for uncertainties as described in UFSAR Sectie:

.s.1 ;

c.

A minimum center to center distance between fuel assemblies l

placed in the fuel storage racks of 10.4375 inches; i

i d.

Fuel assembly storage shall comply with the requirements of i

Specification 3.9.14.

l l

5.3.1.2 The new fuel storage racks are designed and shall be I

maintained with:

a.

Fuel assemblies having a maximum U-235 enrichment of 4.85 l

weight percent; b.

K,gg 5 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in UFSAR Section 9.1; c.

K.gf 10.95 if moderated by aqueous foam, which includes an allowance for uncertainties as described in UFSAR Section 9.1; d.

A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.

l I

t i

f i

e' l

ATTACHMENT B Beaver Valley Power Station, Unit Nos. 1 and 2 Proposed Technical Specification Change Nos. 234 and 107 INCORPORATE ISTS DESIGN FEATURES A.

DESCRIPTION OF AMENDMENT REQUEST The proposed amendment would modify the technical specification (TS) design feature section to reflect those provided in the Improved Standard Technical Specifications (ISTS) of NUREG-1431 Revision 1.

B.

BACKGROUND The current design feature section contains information based on Revision 0 of NUEEG-0452.

The proposed amendment updates this section to contain information based on the latest version of the ISTS.

A previous submittal for Unit 2 dated April 29,

1996, proposes specific changes to Section 5.3.1, which if approved, will be integrated into these proposed changes.

C.

JUSTIFICATION 10 CFR 50.36 sets forth those categories of information required to be included in the TS.

The design features is one of those categories and the types of information to be included are those such as materials of construction and geometric arrangements, which, if altered or modified, would have a significant effect on safety and are not covered in other sections of the TS.

The ISTS were developed to specifically comply with these requirements and to provide a model for plants to use when developing or modifying the TS design feature section.

Much of the information contained in the current design feature section is redundant to information provided in various sections of the UFSAR and is not needed to comply with the requirements of 10 CFR 50.36.

The NRC issued a Final Policy Statement in 1993 which identified four criteria to be used in determining those requirements to be included in TS.

The information being removed from the TS design feature section does not fall within these four criteria.

Therefore, the design features can be modified to reflect the ISTS requirements without any loss of the current information or affecting the safety of the plant.

D.

SAFETY ANALYSIS The TS design feature section has been modified by incorporating the ISTS wording in our format and removing the information not specified in the ISTS.

Section 5.1 has been re-titled to Site Location and includes a text description of the site in place of reference to BV-1 Figures 5.1-1 through 5.1-6 and BV-2 Figures 5.1-1 through 5.1-4.

The site boundary, provided in Figure 5.1-1 for both units, is maintained in the offsite dose calculation manual (ODCM) Figure 5-1.

Changes to the ODCM are implemented in accordance with the provisions indicated in the administrative

ATTACHMENT B, continu d Prepoxd TOchnical Spzcification Cheng3 Nos. 234 and 107 Page 2 control section of the technical specifications.

Reference to Unit'l Figure 5.1-2 in Section 5.1.2 has been deleted because this figure was previously deleted by Amendment No.

121 since Figure 5.1-1 provides the site boundary for both gaseous and liquid effluents.

The exclusion area boundary, provided in Figure 5.1-3 for both units, is described in Unit 1 UFSAR Section 2.1.1 including UFSAR Figure 2.1-7 for Unit 1,

and in Unit 2 UFSAR Section 2.1.2.1 including Figure 2.1-2 for Unit 2.

The low population zone, provided in Figure 5.1-4 for both units, is described in Unit 1 UFSAR Section 2.1.2 for Unit 1 and in Unit 2 UFSAR Section 2.1.3.5 for Unit 2.

The gaseous and liquid release points provided in Unit 1 Figures 5.1-5 and 5.1-6 and Unit 2 Figure 5.1-2 are maintained in ODCM Figure 2.4-2 for the gaseous release points and Figure 1.4-1 for Unit 1 and Figure 1.4-2 for Unit 2

for the liquid release points.

The flood control information provided in Section 5.1.5 is addressed in Unit 1 UFSAR Section 2.3.3 and Unit 2 UFSAR Section 3.4.1.

Section 5.2, containment, has been removed since this information is provided in Unit 1 UFSAR Sections 5.2.1, 5.2.2, 5.2.4 and Table 14.3.3a and Unit 2 UFSAR Sections 3.8.1, 6.2.1, 6.2.4 and Table 6.2-3.

Section 5.3, Reactor Core,-has been renumbered to 5.2.

The text for Section 5.2.1, Fuel Assemblies, and 5.2.2, Control Rod Assemblies, remains unchanged for both units.

Section 5.4, Reactor Coolant System, has been removed since this information is provided in Unit 1 UFSAR Sections 4.1 and 4.2 and Unit 2 UFSAR Sections 5.2, 5.3 and 5.4.

Section 5.5, Emergency Core Cooling Systems, has been removed; this information is provided in UFSAR Section 6.3 for both units.

Section 5.6, Fuel. Storage, has been renumbered to 5.3.

The text for renumbered Section 5.3.1, Criticality, has been replaced with Section 5.3.1.1 for the spent fuel storage racks and Section 5.3.1.2 for the new fuel storage racks like the ISTS.

Section 5.3.1.1 provides the spent fuel storage rack design criteria where item "a" limits fuel-assembly maximum enrichment to that specified in Specification 3.9.14.

This is different from the ISTS which lists a specific enrichment i

number in weight percent; however, this is intended to reduce the possibility of error since the enrichment limit is specified in only one location.

Item "b"

limits the K.gg to 1 0.95 when the storage racks are flooded with unborated water and includes reference to the applicable UFSAR section where the uncertainties are described.

Item "c" specifies the spent fuel storage rack cell center to center distance separation; this is consistent with the current criteria and ensures a change to the rack design i

cannot be made without prior NRC approval.

Item "d"

refers the reader to Specification 3.9.14 since this specification provides the spent fuel pool fuel assembly storage requirements.

Section 5.3.1.2 provides the new fuel storage rack design criteria, where item "a" limits fuel assembly maximum enrichment to 4.5 weight pwrcent for Unit 1 and 4.85 weight percent for Unit 2.

Item "b" limits the K.gg to 10.95 including applicable uncertainties when the new fuel storage racks are flooded with unborated water, this is consistent with Unit 1 UFSAR Section 9.12 and Unit 2 UFSAR Section 9.1.

Item "c"

limits the K.gg to 1 0.95 including B-2 i

u, ----- _ - -._.-

a

-n-,

s ATTACHMENT B, continusd Proposed Technical Specification Change Nos. 234 and 107 P. age 3 applicable uncertainties when the new fuel storage racks are moderated-by aqueous foam; this is consistent with Unit 1 UFSAR Section 9.12 and Unit 2 U7SAR Section 9.1 which refer to low density optimum moderation conditions.

Item "d" specifies the 21 inch new fuel storage cell nominal center to center distance between fuel assemblies.

This is consistent with that specified

~in Unit 1~ UFSAR Section 9.12 and Unit 2 UFSAR Section 9.1.

Section 5.6.2, Drainage, and Section 5. 6. 3, Capacity, have been renumbered to 5.3.2 and 5.3.3, respectively; the text remains unchanged.

Section 5.7, seismic classification, has been removed since this information is provided in Unit 1 UFSAR Appendix B and Unit 2 UFSAR Section 3.7.

Section 5.8, Meteorological Tower Location, has been removed since this information is provided in ODCM Figure 5-1.

i The proposed change removes information that'is redundant to that provided in the UFSAR, is not in the ISTS, and is not required to j

be listed in the TS design features section in accordance with i

10 CFR 50.36.

As a result of reducing the information presented, i

the TS index has been updated to reflect the change in section and page. numbers.

Format and editorial changes along with j

additional information describing the new fuel storage racks has been added for consistency with the ISTS.

These changes do not i

affect any of the UFSAR accident analyses and are consistent with the design of the plant; therefore, these changes have been i

. determined to be safe and will not reduce the safety of the plant.

j i

E.

NO SIGNIFICANT HAZARDS EVALUATION The no significant hazard considerations involved with the

)

j) proposed amendment have been evaluated, focusing on the three j

standards set forth in 10 CFR 50.92(c) as quoted below:

1 The Commission may make a final determination, pursuant to j

the procedures in paragraph 50.91, that a proposed amendment to an operating license for a

facility licensed under i

paragraph 50.21(b) or paragraph 50.22 or for a testing j

facility involves no significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not:

(1)

Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2)

Create the possibility of a new or different kind of f

accident from any accident previously evaluated; or j

(3)

Involve a significant reduction in a margin of safety.

The following evaluation is provided for the no significant i

bazards consideration standards.

B-3

_s.

-m

(

ATTACHMENT B, continusd i

Proponcd T&chnical Spscification Change Noz. 234 and 107 P, age 4 1.

Does the change involve a

significant increase in the probability or consequences of an accident previously evaluated?

The proposed change reduces the content of the technical specification (TS) design feature section consistent with the Improved Standard Technical Specifications (ISTS) of NUREG-1431.

The information that has been removed is also contained in the UFSAR or offsite dose calculation manual (ODCM);

therefore, duplication of the information is eliminated to improve the use of the TS.

Because the information removed from the TS is maintained in the UFSAR or ODCM where changes are controlled in accordance with regulatory requirements, there is no reduction in commitment and adequate control is provided.

Elimination of information from the design feature section of the TS which duplicates information in the UFSAR enhances the usability of the TS without reducing commitments.

These changes clarify and i

improve the understanding and readability of the TS.

Since the requirements remain the same, these changes only affect the ' method of presentation and would not affect possible initiating events for accidents previously evaluated or any i

system functional requirement.

Therefore, the proposed changes would not involve a significant increase in the probability or consequences of an accident previously evaluated.

2.

Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?

The relocation of existing requirements, the elimination of requirements which duplicate existing information, and making administrative improvements are all changes that are administrative in nature.

The proposed changes will not affect any plant system or structure, nor will they affect any system functional or operability requirements.

Consequently, no new failure modes are introduced as a result of the propost.d changes.

The proposed changes are consistent with the

ISTS, for the most

part, as plant-specific information is included in this section.

Therefore, the proposed change will not create the possibility of a new or different type of accident from any accident previously evaluated.

3.

Does the change involve a significant reduction in a margin of, safety?

The proposed changes are administrative in nature in that no l

change to the design features of the facility are being made.

The de: sign features section is being reformatted to be i

consistent, for the most part, with the ISTS.

The proposed l

changes do not affect the UFSAR design

bases, accident assumptions, or technical specification bases.

In addition, B-4

l s'.

l l

ATTACHMENT B, continusd Proposed Technical Specification Change Nos. 234 and 107 Page 5 i

the proposed changes do not affect release limits, monitoring equipment or practices.

Therefore, the proposed change will not involve a significant reduction in a margin of safety.

F.

NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION Based on the considerations expressed above, it is concluded that the activities associated with this license amendment request satisfy the no significant nazards consideration standards of 10 CFR 50.92(c)

and, accordingly, a

no significant hazards

(

consideration finding is justified.

l l

l l

l l

l l'

1 l

l l

I

,i i

i j

B-5 j

i i