ML19337A635

Proposed Revisions to Tech Specs 3.11 for Containment

ML19337A635
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/30/1980
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML19337A626	List: A01162, Application for Amend to Licenses DPR-61,DPR-21 & DPR-65, Incorporating Revisions to Tech Specs for RCS Per TMI-related Requirements.Fee Encl ML19337A629 ML19337A635 ML19337A638 ML19337A644 ML19337A651 ML19337A655 ML19337A659 ML19337A661 ML19337A665
References
TASK-2.E.1.1, TASK-2.E.1.2, TASK-TM TAC-11733, NUDOCS 8009290358
Download: ML19337A635 (6)

Text

_. _ _ _ _,

e e

. '.l,' o '.,..

3.11 CONTAINMENT Applicability: Applies to the operating status of reactor containment.

Obj ective:

To insure containment integrity.

Specification: A.

Leakage The reactor shall not be critical if the containment leakage exceeds 0.25 weight percent of the contained air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when extrapolated to 40 psig in accordance nith Surveillance Standard 4.4.

B.

Containment Integrity (1) Containment integrity shall be maintained when-ever the reactor coolant system is above 300 psig and 2000F. The shutdown margin shall be greater than 3% 21 k with all rods inserted when the containment is open.

(2) Containment integrity shall not be violated when the reactor vessel head is removed unless a shut-down margin greater than 8% Z1 k is constantly maintained.

(3) Positive reactivity changes shall not be made by ad drive motion or boron dilution whenever the containment, integrity is not intact.

C.

Internal Pressure The reactor shall not be critical if the containment internal pressure exceeds 3 psig, or the internal vacuum exceeds 2.0 psig.

D.

Air Recirculation System Three of the four air recirculation units shall be operable whenever the reactor is critical.

E.

Containment Spray System The containment spray system shall be operable whenever the reactor is critical.

F.

Containment Venting (1)

Either the containment air particulate monitoring system or the containment purge exhaust system shall be available at all times when the reactor is critical for post accident hydrogen venting.

8009290357

(2)

Containment purge espability may be rendzred inoperable when the reactor is critical by placing a blank flange on the 42-inch purge air exhaust penetration inside the reactor containment for a period of seven days. If the blank flange can not be removed within i

seven days, then the reactor shall be shut dows within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

G.

The containment isolation valves specified in Table 3.11-1 shall be operable while in Modes 1, 2, 3 and 4 or:

With one or more of the isolation valve (s) specified in Table 3.11-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either:

Restore the inoperable valve (s) to OPERABLE a.

status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.

Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or c.

Isolate each aff ected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange, or d.

Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Basis:

A containment leakage rate of 0.3 weight percent of the con-tained air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at an internal pressure of 40 psig under hypothetical accident conditions with 3 of 4 nir recircu-lation units operating will enintain public exposure well below 10 CFR 100 values.

(See Section 10.4 of the FDSA).

The reactor coolant system conditions of 300 psig and 2000F assure that no steam will be formed and hence there would be no pressure buildup in the containment if a reactor coolant system rupture were to occur.

The shutdown margins are selected based on the type of activities that are being carried out.

The 8% shutdown margin during refueling precludes criticality under any circumstances, even though fuel is being moved. When the reactor head is not r

to be removnd, the specified shutdown margin of 3% /1 k pre-cludes critzcality in any occurrence.

l

Regarding internal pressure limitationa, the containment design pressure of 40 psig would not be exceeded if the internal pressure before a major loss-of-coolant accident were as much as 10 psig (see Figure 3.12-1 of FDSA). How-ever, 3 psig maximum is sufficient for operations of the continuous leakage monitoring system.

The containment is designed to withstand an internal vacuum of 7.5 psig. The 2.0 psig vacuum is specified as an operating limit to avoid any difficulties with motor cooling.

The design air recirculation flow rate with 4 fans operating under saturated conditions of 40 psig and 2610F is 200,000 CFM. The system is designed to perform its functi'r with only 3 of 4 units in operation.

~he air filtration system is discussed in detail in FDSA Section 3.6.

The containment spray system in itself can control the containment pressure. It therefore provides a backup to the air recirculation system.

Containment post accident hyorogen venting can be accomplished by two methods.

One uses the containment air particulate monitoring system and the other uses the containment purge exhaust system. These methods are not required in any short time frame after an accident; it is expected that months may elapse.

In any event the systems used if not operable for maintenance reasons can be readily made operable providing access into the containment is not required.

j Containment purge is utilized as a backup means of venting hydrogen from the containment following a loss-of-coolant accident.

The containment air particulate monitoring system provides the primary means of purging because it provides adequate purge flow to prevent an explosive mixture buildup while allowing fine control of the release of radioactivity during purges. When necessary to effect repairs to the containment purge or purge bypass isolation valves, a blank flange must be applied to the 42" purge air exhaust pene-tration inside the reactor containment so that the contain-ment remains leak tight. This renders the purge system inoperable for a finite time.

Seven days in considered a reasonable length of time for repair parts to be received, inst'alled and the system retested for leak tightness and returned to service.

M 2

i The OPERABILITY of thn containatnt isolation v21ves Ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment.

Containment isolation ensures that the release of radioactive l

material to the enivironment will be consistent with the assumptions used in the analyses for a LOCA.

Reference:

(1) FDSA Section 3.6 (2)

D. C. Switzer (CYAPC.) letter to A. Schwencer (NRC),

-dated June 27, 1977, Attachment No. 2.

1 l

..,.._,s.,

,,..,,, _..s,.

_...y...,_

..s....s..,

i SEVLAV 1N

- O 1I T

1. A 3L O ES LI BAT TNEM N

IATN OC e

e g

g r

r a

a t

h h

r i

c c

d n

s s

H k

i i

n o

e M

l e

D D

f a

N p

e l

f T

n n

O m

l p

e p

p o

i i

t t

k I

e e

e a

p m

l m

m k

d a

a n

n a

T c

c c

S m

a p

u u

a a

r r

e e

e C

i i

i a

S m

S S

e e

D D

V V

L N

f f

f r

S a

L H

U i

i i

e d

S t

t k

k k

k t

F r

r r

d m

i n

n m

l n

n n

n n

O O

O a

a u

H e

e e

a a

a a

a e

E e

e q

T m

m t

e T

T T

T mn V

n n

n H

t i

n n

S S

L w

w w

S L

1 i

i f

f f

f i

A o

o o

n a

a e

r e

e e

e a

V d

d d

i p

t t

v o

i i

i i

t t

t t

a r

r o

n n

l p

l l

l l

n e

e e

r z

z o

o o

a a

e e

e e

o L

L L

D P

P L

C C

V V

R R

R R

C 0

4 A

A N

2 3

4 8

6 2

3 4

4 8

5 1

T EN 0

0 0

0 5

0 5

1 4

4 4

5 4

5 4

1 MO 2

2 2

5 5

6 6

8 8

8 5

8 5

8 8

NI 9

9 9

9 V

1 1

1 1

1 1

RIT 7

V V

C V

V EEAA c

0 0

V V

V V

I V

V V

0 V

0 V

V T

T A

T A

T T

VBTL A

A A

T T

T T

H-T-

LMNO AUOS D

D D

S S

S S

D D

H H

H H

C G

M VNCI L

L L

S S

S S

W W

D D

D D

W W

L m

y I.

I m

SEV

.L

)

A tV noN CO

( I T

1 A

- L 1 O S

1 I

3 T

EN LE !

B!

AN TI ATN O

C kT d

D n

/

o n

n n

n B

C w

w w

w t

t o

o o

o o

o i

i d

d d

d t

t n

n t

w w

w w

n o

o e

o o

o o

r M

M l

l l

l l

u t

t f

t B

B B

B t

e e

n n

f e

l l

r r

o O

a a

O r

r r

r R

n n

D D

k N

k k

u s

a I

e e

o o

o o

I I

e e

s e

T L

L C

t t

t t

C C

a a

a a

r r

r y

y n

n a

L N

t t

r r

r r

t e

e t

t i

i p

e e

e e

U d

d i

i L

L y

m F

e e

r n

n n

n a

a v

v B

e U

n n

m m

i e

e e

e e

e i

i t

E n

n C

G G

G G

H H

t t

m m

l S

1 c

c t

t a

L a

a n

m m

m m

C n

n A

A S

S e

e V

i i

S v

A t

t i

a a

a a

i i

V n

n a

e e

e e

T a

a r

r l

o o

r t

t t

t S

r r

i i

n n

1 a

C C

D S

S S

S N

D D

A A

M l!

il iiV M

it I!

Ii II

!(

I 1

2 3

4 B

T B

N 1

2 1

2 2

2 2

1 1

7 8

2 3

1 2

EN 1

1 1

1 1

1 1

3 4

4 4

1 1

3 4

MO 8

8 6

3 3

3 3

8 8

8 8

1 2

2 3

8 NI 1

1 1

1 1

1 1

1 1

1 1

1 1

RIT V

2 V

EEAA V

V C

V V

V V

V V

V V

1 V

V O

V VBTL T

T F

T T

T T

T T

T T

T T

M T

LMNO V

AUOS M

M C

G G

G G

C H

H S

O S

S H

H VNCI L

L C

S S

S S

C D

D V

S M

M C

D

]J ; *

'l It 2