Text

Forwards Response to Plant-Unique Sys Group Questions Addressed to BWR Operators.Info Supplements Response to IE Bulletin 79-08
	ML19256F121
Person / Time
Site:	Millstone
Issue date:	11/15/1979
From:	Counsil W; NORTHEAST NUCLEAR ENERGY CO.
To:	Kane W; Office of Nuclear Reactor Regulation
References
	NUDOCS 7911210451
	Download: ML19256F121 (22)
	v • d • e

.

IMMITHI!JUIT IFFILrrII!S

?,

A FOR CONNECTICUT 06101 (203) 666-6911 4

.,.n

.s

(

e.v flovember 15, 1979 Docket No. 50-245 Mr. William F. Kane Bulletins and Orders Task Force U. S. Nuclear Regulatory Commission Washington, D. C.

20555

Reference:

(1) NE00-24708, " August 17, 1979" (2) NRC Bulletins and Orders Task Force -

BWR Owners July 12, 1979 meeting Gentlemen:

In Reference (1), responses to the questions presented in the NRC Staff's requests of July,1979 to all operators of General Electric Boiling Water Reactor - equipped power plant.s, for information to supplement that provided in Inspection and Enforc2 ment Bulletin 79-08, was provided.

Reference (2) resulted in a deferral of several plant-unique Systems Group questions until November 16, 1979. The enclosures to this letter provide that deferred information.

Should you have any questions concerning the enclosed material, please contact us.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

.Y.

NLF H

W. G Counsil '

Vice President Enclosure lj//

197 e

W%

7011g 39 & &

Enclosure Contents A.

Bypass Capacity B.

Systems and Components shared between units C.

Plant-Specific System Information D.

Primary Containment Isolation System Data (including Figures, tables, codes and set points)

E.

Design Requirements for Containment Isolation Barriers F.

Provisions for Testing G.

Codes, standards and Guides H.

Normal Operating Modes and Isolation Modes.

l3//

i98

A PLANT Millstone UNIT (S) 1 BYPASS CAPACITY Plant Steam Bypass Capacity, % Rated 100 13//

199

[3 Pl. ANT Millstone 1 SYSTEMS AND COMP 0MENTS SHARED BETWEEN UNITS PAGE 1 CONTINUED PAGE Single-unit plant check here and do not complete Shared Between System or Component Uni ts Numbers 1.

Fire protection water system (partial) 1 and 2 2.

Ventilation stack 1 and 2

Reference:

W. G. Counsil to D. L. Ziemann letter dated April 27, 1970

" Millstone Nuclear Power Station, Unit No. 1 Systematic Evaluation Program (SEP) Shared Systems for Multi-finit Stations" i 3/ /

.?00 4

C PLANT fiillstone UNIT (S) 1 PLANT-SPECIFIC SYSTEM INFORMATION General Water Sources Instrumentation and Control _ Frequency of Safety Seismic Safety Seismic Safety Seismic System and System Classification Category Classification Category Classif. Category Component Tests 1.

RCIC flA NA flA flA flA NA flA 2.

Isolation Condenser 1,2,3 I

3.Nfl I,flA 1

I once/ cycle 3.

IIPCS flA NA flA NA flA NA flA 4.

IIPCI flA flA flA NA NA

'IA NA 5.

LPCS 1,2 I

2 I

1 I

monthly 6.

LPCI and Cont. Spray 1,2 I

2 I

1 I

monthly 7.

ADS 1,3 I

1 I

once/ cycle 8.

fRV 1,3 I

1 I

once/ cycle 9.

t"R (including O'

shutdown cooling,

['

steam condensing, suppression pool cooling, (valves) containment spray modes) 1,2 I

3 I

1,2 I

once/ouarter C 10.

SSW & ESW 3

I 3

I once/3 months

11. RBCCW 3

I 3

a 3

I

-onthly 12.

CRDS 1,2,ftfl I

2 I

1 I

weekly 13.

CST 3

I 2

I 2,3 I

(Level) Daily

14. Main Feedwater (FWCI)*

1,2 I

2 I

1 I

once/3 months

15. Recirculation NN I

3 I

I flA Pump / Motor Cooling

Feedwater Coolant Injection NN = Non-nuclear

c i 'i3 x X X X XX X X X X X X X X X

X X X X X X X

X X X X X

a5%EU8 1

1 1

2 2

2 2 1 1

1 1

4 4 8

8 7

7 7

7 zS2s 4

4 4

6 6

0 0 5 5 5

5 9 9

8 8

1 1 aSe ;2 E.

7 1

1 1

1 1 1

77 7 7 2

2 2

2 8

88 8

8 2

2 2

2 55 5 5 4

40 0 0 0

0 0 00 e

ii 1

1 CL D u u S r r

D D D

D T

R f

C e

a l

r p p

uy y r

r r

r c

i a

pw u y y y

y C.

U. U U.y p n

i p

e e

w w

w u

i w

e C

l l

e e

r n

S S S,_1 C h l

l l

l V

c S

h a C

l l

e t

S yy y

mAag s s _1

m. h V V n

e t

a s

a e e

V V E

F t

I.

a e

t tt S m

e eeu b

m n n e e q

l o

m a

m mm p

e V bt t

n n u

o t

o m

p r e e

t t

i o

o p

D x

s. _.

N =C -

1 n

r t F

p r

r v

s t

o r R

S a

a i

u v

o e D

D p

R e S m

l r

r S

m n

p e

n B i

a a

p yf T

IR e i

i l

l l

t G

l f

n n

e S

w. MtB *c 8

*U N N_ N N N N N N N N N N N NN N N N N N NN N N N N N N N

._5tJ*Eo c

4_4_4_444 4( & 6,6 3 3 6 &

IL

.u S' b.

4 1

I l

l 1

3 I

1 jl.I o.28" A.A A A A

A A W W WW S S

W W W W S S

3S S

S 3

S 9_ W A W

u. 33 P

M MM M

M 1

I CCCA A A A A

A A

A S

S SS 1

I S S M

R

% ?

1 I

I C C C C

C C C S

S SS 0

C M M S

S S

S SS S

S S

S U U_ U C M

z 5 2 i_

A 41 1 8

9 7

1 1

43 7

6 2 1 6

5 2

2 22 1

I 1

I 53_25 1_l D C BA D C B A

P R 4

3 2

_0 A Y P

.A,A,A.A.A.A A,A.A,A.A.A.A.A.A.B,B.B

,B,:,B,B,B.B,B,B,B,B G

L B

1

t8 E C A vL. "8-g FF FF F

F F F

F P.F.C,C.C C.,C,C,C,C,C.C,C,C,C,C W V,W F D,D.D D,D,D,D.D,D.D,D,D,D,D O N N T 1

T uo rO

,Y,Y2Y.

A P

J J1 P

PP P

P PP P

PPPP P

P I

N 1

a8 "Se C M 06_I0 1

00 0 Q_ 0 0 0 0 0 O D. O O O I

O I

O O O O I

I I

I O E N N s

T T t

B B

G G C_G S S

S S

G C C C C C C C C C e?e o

CCCB.

B3 B B

I I

I N

I n

TTT.

T T TT V

V V V T T B

B B

B B_B BB D

U S e

E O lim 1 AAA AA AA A

A A AA A

A S

S M

A A

A A A A et8Ss.

1 I

D L f

oD00 0Q 0Q o0 0 0 n 0Q 0

0 O O O 0 0

0 0 0 0 0 0

0 s

A 1

o O T U

o. I 8 i "tE.

l N

I N

A"" A A A_

- eta a

O I

AA A A AA A A A AA A A A A A A A A A A A A A A t

P N T i

A w3e fe "U9i vM8eb o

G S RRRR RE R P PR R

P R PE R RR R

PR P

R P

R R

iM M J!

J M J M

M M n

E Y 1

l l !

l lI 1l 1

M M

M MM! M f

it 1

1 l

L1 L

f f i

f f

S 1

V T

11 1

1 1

i 1

1 1 1 1 !

2 1 1 3

3 1

1 3

3 3

3 l

1

.u 5 G 8 h e a

2 E

8880 0 s0 0 0.5 0 O 0 0G5 5

5 5

r5w ' "8.

M l

5 5

v e

D D DAAAA A A A A A. A A AA A A A A DA A A AA A A A A a8k *8Eo s

A C CC C

C CC TA o.E "3c "E Si D D D n.

DD D D D D.D D DI n

D D D D D D D D D D D D D D L

S e 5 8 D o C

0 0C C C C C r C0 0 0O 0

0 0 C CCC 0 0 0

0 0 0 0 0 zo y -

P o

s C C C C CC C c C C C C C_ C C oEBEe i

C f_

C 0 0 0 P 0C C

I CCC L

t i

o i

CCCP C C 0 C P c.C r r r r C C C C C C C C C C C C r C

a. 8 v n

483Eo s

a. 3k.

r r r r r C C r A A

C C C C C C C C C C_

A A A C.

C C C C P

u. % ='

I T

I I

l Commen t

s bgMbM(MMg(E I

L

(

g

p h)C e

39 t

i i

el!l;,

[t

g 1

u

_! L t5 j1

_X X

X X

- X X

X X X X X X X

X X X X X X

X 4

4 EE 2B8 1

2 2

1 9

9 9

9 1

1 1

4 1

1 1

1 4

7 1

1 0 0 7

4 2

2 2

5 EEs.

1 1

3 E ;w 2. M.

1 1

5 5

5 2

3 3

8 8

88 0

0 4

4 2

4 4

8 C

S R

C F

I I

R S

S S

S l

B e

o e s s s s e

h h

C a

n e o o o o a u u u u u u

e

.C c t

d l

l l

l c

t t

U I

an S

t r

w a a a a t

d d

o o

a t

t t

t o o o o o o o

u r

l t

i i

i ir w w w w w

w S

&tg p

e o o o o l

n n n n n n y S

l R

r n n n n i C C C C C C t

l s

e o

c y

a d

C C C C a o o o o o o e s

d o o o o d o o o o o o

m t

D n n n n l

l l

l wc' N x +' -

e C

r d

d d d C i

i i

i 5

o n n n n n n m

o i

o v

o g n

g g n n l

e l

i i

e n

n n5tB%3b,>

c N Y Y N N N YY Y

Y N N N N N W N N N N N N 2*cE

?

J I_

f f E $.e 2 2 l

1 l

3 I

1 l

I l

ll 1

I I

l

a. f a W W W W W W WW W W W W S S W W WW W W W W C5 F

P C

S S

l 3

3 F F 0

0 MW N_ F I

T I

T S

S S S

S S

C l

R D5 I

I l

1 1

_WC C C C lS D DD D D D IT 6

U l 9 1 -

M S

I E$ s.

A

_ 2 8

7 5

1 1

OB 0

9 43 2

l 4

5 44 2

2 1

2 A.

3 3B A A B

A B A

8 P R F

A Y P A

G.G

.A G

L

?5'D8 E C A

.W O N K K K K A A A A A A A

N T 7

,Y

.Y 352 T

2 A J

.1 I

M N

i

. $3e C M l

3 I

0 I

O O I 0

O O O O O T

O l

O E l.

I O

T O O T.O N N s

T T t

6 C C C C C C CC C C G G G G G G C G GC G G o

& E.

I N

I n

6 B

K K K T K K K

K K T T T T T

T B B T T. T T U S e

E O d

A M M M M M M M M M M M }i 3 $ 3 i.

I D L 1

0 O O OO 0

O 0 O O O O O s

A 4

o O T U E!e8t "t8 e N

I N

l

__ h _.

A RE R -

R R R

R R A A A A A A A A A A A A D8 a

O I

_ e _.

FE F

F FF F

F t

P N T i

A t 4UN o

G S

_ %E$M?

RM R R R R R R R R

_ 6._.

R R P n

E Y 1

M M M M M M M M M M

M F f

1 S

V T

d; G 8he 1

a E

0 1

1 2

2 4

4 4

1 r'$ "8.

i l

M 4

0 4

4 5

5 8

8 8 8

8 8

v e

D A P P f.

I P P E_

P P

A n D A A

A D D D D A

A 2$ " ate s

A e

. m..

I C r C C C

C C

C C C

C C

T A

253c 5Eb D N t' R N N N N

N N D D D D D D D D D D D D D 8 5 '8U8' &.

\\

O

- O O O O 0 C O O 0

0 C C C C O O e0-0 P c _C P

os isEc 6

C P e C. C C C C C C C C P

C 0 O O O 0_O C i

t io 20 I

C r cI C

C O O O O C C C P C C C C C C C C n

L 33E-s A

A A A A A

A A A

A A

A A 2N*

I T

I I

T I

T T

I T

T 2

F F

W W W W r C C C o

o o

o l

l l

l C

a a

o n

n n

n m

t t

me I

I I

t n

n n

ny t

i i

s 9

S S

S (cgi y y y

y fm%eh3'@

,s.s s

s

)5g I

e l

a

PLANT Pj,ll 1.,,,

UNIT l PRIMARY CONTAINMENT ISOLATION SYSTEM DATA PAGE 4

CONTINUED ON PAGE FINAL ABBREVIATIONS Engineered Safety Function Isolation Valve Type Isolation Signal Codes (utility supply)

N = N0 B

= Butterfly Code Parameter (s) Sensed Set Y = YES BCK = Ball check or Group for Isolation Point (units)

BL = Ball Position Indication in Control Room CK = Check jg f7 /q c. f/s p D = Direct DCV = Diaphragm Control Valve I = Indirect GB = Globe N = None lla Others stated in Table e of Fluid SCV = Stop Check SV = Solenoid A = Air VB = Vacuum Breaker S = Steam XV = Explosive W = Water Others stated in Table Others stated in Table Isolation Valve Location Isolation Valve Power Source I = Inside Containment A

= Air 0 = Outside Containment AC = AC Others stated in Table DC = DC 11

= Iland Isolation Valve Actuation Mode P

= Process fluid Others stated in Table A = Automatic OP =.0verpressure 6

RF = Reverse Flow N

RM = Remote Manual N

Others stated in Table

'gisolation Valve Positions Isolation Valve Actuator A

AI = As Is A0 = Air C = Closed M0 = Motor 0 = Open 50 = Solenoid Others stated in Table Others stated in Table

KNPS-1 Isolation Signal Codes Signal Description A

Reactor low water level - scram and close isolation valves ex-cept main steam lines.

B Reactor low-low water level - initiate isolation condenser ac-tion and close main steam line isolation valves.

C Eigh radiation - main steam line.

D Line break - main steam line (steam line high space temperature or excess steam flow).

F High dryvell pressure - close dryvell atmospheric control and secondary containment isolation valves, scram reactor.

G Reactor low water level or high drywell pressure - initiate core spray, LPCI and FWCI systems.

H Line break in recirculation loop - close corresponding LPCI loop valves and open valves in opposite loop.

J Line break in cleanup system - high space temperature, alarm only, no auto closure.

K Line break in isolation condenser system steam line.

P Low main steam line pressure at inlet to main turbine (run mode only).

S Low drywell pressure - close containment spray and suppression cooling valves.

13//

?05

.a MNPS-1 Signal Description T

Low reactor pressure permissive to open core spray and LPCI valves.

U High reactor pressure.

W High temperature at outlet of cleanup system nonregenerative heat exchanger.

Y Standby liquid control system actuated.

Z High radiation, process rad monitor, reactor building ventila-tion exhaust plenum.

RM Remote manual switch from control room.

I i

13//

!06, e

09

MILLSTONE UNIT NO.1 Closure Modes of Recire.

MS1V ECCS Actuation Pump Discharge Closure Signals Signals Loss of Feedwater Iso-Condenser Valves (Trip Setting)

(Trip Settings)

Analyzed ?

Automatic ?

Actuation Analyzed 1.

Manual 1.

Reactor low-low 1.

Reactor low-low Yes(3) 1.

Auto (4) water level (1).

water level (2)

(P>1085 for 15 sec.)

(79 inches above (79 inches above Docketed Occurrence TAF)

TAF) 2.

Main Steam Line 2.

liigh Drywell

1. R0-76-29/IP (5) 2.

Manual from control high radiation (1).

Pressure (2)

R0-76-29/1T (6) room.

b ckground)

- 2 psig)

R0-76-29/10 (7)

(<~ 7 times normal

(<

ISE Inspect. 76-19 (8) 3.

Main Steam line 3.,

Manual f rom 3.

Manual from Valve IC-3 high flow (1).

control room Outside Containment

(<_ 120% rated steam flow)

Interlocks 4.

Main Steam line 4.

Reactor low

References:

tunnel high pressure permissive (1) Tect

s. Table 3.2.1 and

(<_ 00 (3 0 psig <

P<

350 psig) 5.

Main Steam line (2) Tech. Specs. Table 3.2.2 low pressure (1).

5.

Timer Auto Blowdown (2)

(3) FSAR Section XI - 3.5

(> 880 psig)

(<__120 seconds)

(4) Tech. Specs. Bases 3.5.E 0

te to I A u 6.

Manual from control 6.

Co ainm Spray 0 e e u

(7) NNECO letter to I&E, January 20, 1977 u

(4. 5 <_P<_ 5.5 psig)

(8)

I&E letter to NNEC0, Septeniber 13, 1976 N

7.

APR LP Core Cooling Pump Interlock (2)

(90 <__ P <_ 110 psig)

.v y

8.

Power Available on Energency Buses (2)

(Buses 5 and 6) 9.

Power Available on Energency Buses (2)

(Buses 1,2,3, and 4)

.... ~. - -

=

y l

E i

1 i

,+ 44

+.4

+

.i

!! !?

i i

$9

(.Si r

F I

i I

I I

sij!!! bd:'

rk M, i:,4 h p

.a:f:n

_H:

t u

$24" 2

-* o 3

3 e

a y *w o-O s 1

s I

J r

kE 3

.4 t

5 a

Y,-s e.3 e

a a

e e

o i

e g

=,wd..

3 9,

q\\ +t s g

at I

2 VO

!3

.I 3

T Z'

M Sy

~

g i.. g g {.. H f )l.v 3gg g

I',6x'9 4 >,

'r--X : -

j U.g

-Y if f f!51 8dio g

,,] f 3

iE w l,.,,,

2 o

g 2#

3 b:i.,, ':n t

1 L"for

,t., s 49 I

XZ.

i4 4

<~

r, I '

i 9,o; Lbc o~u

' ec a

w, N

'h

+

H 4,r-X is p>=

.~

i e

h h

E

"'((

0 lg a p a

f I1*l

'5ii e.

5 b

.i S

f. in 9l.!

i s'i t.: m

.s 4:l IH iW ~

> 'T 3 ".0" j

1

'~

L il

'Li - l 11 1:

5gg a

+

'l si_! L.

'.'.L.

~

at J

=

s1 1

c E

Is T d L.-

L J LT, ri

- ruuuul r1 r

11 I

.'illis i

4 2

i a

5

,C:g es L

1 o

e 4

i I

I I

i fisii i

.nrmrmrmrm2 tr trhnqnn, u

x G$g

%n i. -n

,,-.._,,.,,e-....

N,

8 p

i'

,,J L, t_,L L, j

L

,t c,-

i g

~

i i

~

l IH w

21 e

a eL' =s =,a

sp S:

-s<

n a

.u, M

I is ir y

,.o f i

-y, s

I:

n e

3,,,,,,

u u

o,c qs

. 'N

,1 %,8 p 1, 3

gi gj g g j, s,jrX W s

u-o.s e

a i

s a 9 g s.

c a

_a p

a a

s L.,

a y

a o

r a

a g

.f k

.3, g,

k

~

h 4

lI

.A AA A

S ;

I a

g w a ir, g

g

=

3 a

=

s 1

I i

o 3

3 4 4 4 4,i l

4 4 4,!

1 {i i

i i

s

~ b., I

.208 I -

N-WD&g tw

===gM4 age

m. 9 =m d4 N**6.-

-~ ~

~ _ _

xa I

e g

v !

3 g

LL ::

D PC P

9'T 8

5 3

D N

4 1

-l,!

~

LL ll m

11]

ii lL ':luL 1

=

l i

l!i.j 30

'il 8 (

.i 5

r n!.I

3*g

,,,,, w.

Je

, i, er,

wv !.

11

.!.:s!

/

+

1if: I a.

y JW i;

{

j,'

-O-l",

'./i/71 C

I t I f

y YI!

.f!

![3Jf%gk

';l 8

l l l I!IstF I

~'

M: n=f2 lf='MC i; J-u'c wh L=

~ dit D]!4' i

e a$ c i \\b I.gn!B,2n e

i a it i

s Y,, II.. h. _ b.

f l 4-a

!g!.

i t

I. liplp3 t, #..r fr. i}: :,I _ l e

8 i'.

! !. P --112.i.E. i itt 1 ': _-

ap.

f!I

';b.3-1y a leyj., O l M

i ;3,

g

i,

.g. O.-g e

1 u.

.d.l w

i.

i

. 3..!i..

i

....: tg._ WO'

?

g 3%

3 s

1

.i s s.;

X<

!!!!o l

i 5-

_3 l{l s

_ d b _

==

6,e 9

3 4

w~

Ed'$

w y

'- i,,,

e

-i 1*

I

,i; ff.

.

m,J, m 4 s

~ Lff f

a i

L 13//

109 l

4 O

d 3

I

~

I a

I 1

0 I

l

{f0 T }'

5 D

~

8

~

N dJ h

g j

d a

g r

a v 7

$$$ $I Eb 5$5 5,[

=W v V 0 I

p f

gs_

lllll'll) i 4: 5 m

f p~

D

{ Di j

55 P

d

> *- s.

/

v 3 p 2 a

st 5t i g g 2

t r-~As

+

a 1 +

i ;,

f9 "'

+-

I

'p!

i t

~

I Y

s

Y e

I O

4

<2 r

i I

l

~

g 4

h I

4 i

49 l

l ti lO{

m.- f 3 5 I,

y y'D

,Qa,

',jv jg l

Y m.l ------...:s' g y n

C u

aa a

I s

td I

o pu$. - - me O

l m::

o I

IT 2

I I-G Z s

I el Oo I

'I

'cu

% ~~

bJ D

I sI

+

,d

+

I.

d J

m

,.[).,-

- - -.g y. - - - - - -.

- -.g I a-Os

-D NI d

II I

I p3

'I 4 h

y II I

2 g

o NN

'f 5

LJ d.

I "

II!p

@M US l7 s

0

\\;-

_ 4 3

3 p

'f 3

r=

++i-avl-w 'Ir -l'7he

1+-

9

'i II A

I y

=

?, ?

l lI - M l ~#!? O "i l

/

I 3

II 4

o I

1 9

y 4l s - --. :------ r * ---- J --- '

O g

+

I s

K W

F

U 4

2d*

EE 13//

?10 db

8 g,33,1 ein e umi Feg sar* 4 T REACTOR BLDG k/Att.

G 9

STA C K 16" M

l Ng>AAKE 09 SY5TUA NOT W f

O l

1-AC-B h

T To EllHAusT I

S

---u' h 1~ 5 6s

" " " ' " ^

y A, C. to_ _ _;I x

a-I i-AC 9

.. AC...

g;

-z

=

V

-..se.,A og li -e :

l 8.

3 r, X, *- r 4

,s

,E,

.u ~

n e

i g,,.,,'a,i e c

~gA=

i

=,"r~'y g],,e.,A:

c;

[,a.

i-so 4^

n i,c g.as- ~,- /

~

se m,

.m

,, A4,s,

,a.

i 1

_ _ _ %)l-C l

. _4

__4i____.

i l

12' E I

B

'8" B

, (WCEQ gPLACES B

to" l

5 e tG. r.,

,SG78 E

e-AC 4 I

g g

j igH;F-- a La p,g

\\[(f.g.,is

,- i-Ac-i-I ' *'

LS' oj. M I.

J

'j.M', y

.a s 2 + ' ^'5 1 ! fc.

i i.Ac.c i.se.4 e g-

+--

>-so ta g,"I,

t-AC-3 A D'I E===.=l} he =o= M t-AC-2 2

B

[

aounoARx oiAseAu L __4 p 9,,y.,,

2,,

s 6TAHbBY GA6 AMD ATMO6PHERE CONTROL 6YSTEM VAcum i.4c. 3 N

NON-NUCLEAR. P nPE REttE F ct ASS

E PtPtNG en - en es B, a t-AC-l m.,b, C,tTC.

l

-J

,u-a _>,,.,-ws4

- -x i

na mnn i

i i

"" "z T-77 IUU. w3: wir g

atv om aviuou avi o.um

M i

4 I

l j

.I

s s,

i nn-

=

sss n

J

. v 9

Y<a ljg hy

!8 I $

I SC ON!

ON

}

se s

o a*

2 m,

$p m

!,

d.:

E. 4 O

a, s.

r4ii Lf b

.....__ q l

0 i

l l

7 g _ _ _ _ _ _ _ _ _ _ _ __.;

p 4

G H.)

GHs!

3 3

3 8z e 8f a

55 Lg e

~

Y a

0 8

I I

}

.I l

.l 8:5 ci 3

si g=,Y I

W w

z s

35 8

3-f g

r E

2

)0

$g I

ea s:

i l

C W ii 8

.o.

i

.e,

a su i.

i x

iz 9=

t'

's 88 h.

I I

8 I

I l

i.__.___.o________,

o, i

3.__._____9_..........J

'i g]

~

e

,,,/ /

,l2 13 S

a

.w

..e e

..ee4.-

e o.

],_

DRYWELL FLOOR ORAIN _'~~~- ~ ~ ~ ~ ~ ~

b8 b b8 I M*-

=.9 e.e.Nhe

~~

~**

h.=w Prim wy

.[

s % g,,,, f

' '~ l~ l~_7_~~

c.nba

..it c

u;,, m,,4

(

7 y

i

~~'

%.)

$$.4

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

h-S p

e_g=4@pgS L.

h.

l

~

FLoon ourn

.!. _ M

~

~~

~

. [_

~ ~ 'D'RYWELL EQUIPPENT DRAIN,___

I i

e-*.m.-

.N.

,-.m W e.N.-ee_e

.e-i.*.

"**. *.__ w w.e e

w_w_g

.m e..

.e e

+e W

=.m.h_mg.....

y-..=_.

_ N-.

w e

e..

o.--

e%

..,.-e.

_,g DAYW6LL G eusf. O Most. - -.-- - _. -_. -

.,,g

.e

.-e

. sui.

e

Odee=.

-===>..**6

.'"+=-*.*. _ -

6.

.__-.***^-*e-e

__ae_**.

.__Mw.N_e_

m===mme e__

e-

..e a

RECIRC. LOOP SAMPLE LINE. -l.. __ __

g g

l 5;><._...__.

3

-. 5;c re A eemeut dien _....__

. g _....

L..p__.._._-...._...

[

Y __.

Y__. -_Y. _-. _ __ __._. _ _b - __.

s,--.

a-a. = _

-N*

.am we g.

.g

(

l

.$e_.

6"".**"'ON*i

..-_.=_o.e.

6

. _-.==

-+e.

-. -_~....

/..

-....---..E mem.m.._

-e.m.

.-eg.--e.-

..--+-.m

+..og.*

-e

E5 PLANT Millstone UNIT (S) 1 DESIGN REOUIREMENTS FOR CONTAINMENT ISOLATION BARRIERS Discuss the extent to which the quality standards and seismic Question:

design classification of the containment isolation provisions follow the recommendations of Regulatory Guides 1.26, " Quality Group Classifications and Standards for Water, Steam, and Radioactive-Water-Containing Components of Nuclear Power Plants",

j and 1.29, " Seismic Design Classification".

i Reculatorv Guide 1.26 - The Northeast Utilities Ouality Assurance

Response

Program Topical Report NU-QA-1, Rev. 3A (1) provides guidelines to the engineer (designer) for determination of and the detailed i

quality requirements associated with the various comoonents.

Addition.'lly, this item is currently under active SEP review, Reaulatorv Guide 1.29 - (2)Section XII of the FSAR, " Structural Design," relates in detail to the design and classification of plant structures and equipment.

Classification of structures and equipment are listed in para-graph XII-1.1.4 of the FSAR and Amendment 18 in answer to Interaction of Class I/ Class II structures question A.16.

i and equipment is discussed in Amendment 14, pages III-I, 2 and l

3 and Amendment 18, pages 203 and 204.

Class I structures and equipment indicated in Section XII and in the above-mentioned amendments of the FSAR are in conformance with the requirements. of paragraph C (Regulatory Position) of Guide 1.29 for Category I structures, systems and comnonents.

(1) Letter with Topical from W. G. Counsil to W. P. Haass dated April 23, 1979.

(2) Reference " Full Term License Application" Appendix C dated September 1,1972.

13//

?l4

I PLANT Millstone UNIT (S) 1 PROVISIONS FOR TESTING Ouestion:

Discuss the design provisions for testing the operability of the isolation valves.

Response

Detailed discussion of the design provisions for testing the operability of the isolation valves can be found in the Millstone Unit FSAR section VII (Instrument and Control), 6.0, FSAR section V, Containment systems, specifically paces V-2,34-V-2.35 also provides details of the testability design.

Technical Specifications 4.7.D provides requirements for operability testing.

13/7

.?)5

G PLANT Millstone UNIT (S) 1 CODES, STANDARDS, AND GUIDES Question:

Identify the codes, standards, and guides applied in the design of the containment isolation system and system components.

Response

This item is an Systematic Evaluation Program (SEP) topic which will be evaluated for Millstone 1.

However, the following information is included for your review:

Compliance with Appendix A to 10CFR50, " General Design Criteria for Nuclear Power Plants," (GDC) effective July 7,1971, was not included as a design basis for structures, systems or components for Millstone I' nit No. I since the GDC were not in existence at the time of issuance of the plant construction permit (May(October 19, 1966) or the plant provisional operating license 7, 1970).

The primary containment isolation system was designed in accordance with the licensing criteria in effect at the time of issuance of the provisional operating license.

These criteria are stated as follows:

(1) The primary containment isolation system complies with IEEE-279 (August 1968) " Proposed Criteria for Nuclear Power Plant Protection Systems."

(2) Piping other than instrument sensing lines which penetrates the primary containment and is in direct communication with the reactor coolant system has two automatic isolation valves, one inside the primary containment and one outside the primary containment.

(3) Piping other than instrument sensing lines which penetrates the primary containment and communicates with the primary containment free space has two automatic isolation valves, t'oth located outside the primary containment.

5 b!I

?lh (4) Piping which penetrates the primary containment but communicates directly with neither the reactor vessel, the primary containment free space, nor the environs, has at least one isolation valve located outside the primary containment which may close either by process action (reverse flow) or by remote manual operation.

(5)

Instrument sensing lines which cormiunicate directly with the reactor coolant system have one excess flow check valve and one manual globe valve located outside the primary containment, (6)

Instrument sensing lines which communicate directly with the primary containment free space have one manual globe valve located outside the primary containment.

(7) The operability of each automatic isolation valve may be tested periodically.

The criteria used meets the intent of GDC 54 which gives general requirements for isolation system redundancy, reliability and testability.

GDC 55, 56, and 57 give specific reauirements for particular classes of penetrations.

Table 3.1-2(1) gives the isolation valving arrangements used on all fluid line penetrations and discusses compliance with the applicable GDC.

(1) Application for conversion from provisonal operating license to full-term operating license, dated September 1, 1972.

13//

117

VN PLANT Millstone UNIT (S) 1 NORMAL OPEPATING M0 PES AND ISOLATION MODES Question:

Discuss the normal operating modes and containment isolation provision and procedures for lines that transfer potentially radioactive fluids out of the containment.

Response

The normal operating modes and containment isolation orovisions are detailed in the Final Safety Analysis Peport and have been previously responded to in the response to IEB 70-08, item 2.

Additionally, the Millstone 1 Technical Specifications and the response to item D of this letter provides details concerning valve position for various modes of operation.

e

.

ML19256F121

Text

Reference:

Reference:

References:

.

Response

Response

Response

Response

Navigation menu

Search