ML20036B288

Proposed Tech Specs SR 4.6.1.2.a Re Type a Containment ILRTs

ML20036B288
Person / Time
Site:	Waterford
Issue date:	05/07/1993
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20036B286	List: ML20036B285 ML20036B288
References
NUDOCS 9305180457
Download: ML20036B288 (10)

Text

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ATTACHMENT A i

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i 9305180457 930507 PDR ADOCK 05000382 P

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CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a.

An overall integrated leakage rate of:

1.

containmentairper24$o,urs.50percentbyweightofthe Less than or equal to L 0

at P,, 44 psig, or 2.

Less than or equal to L., 0.25 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a reduced pressure of P,

g 22 psig.

b.

A combined leakage rate of less than or equal to 0.60 L for c11 penetrationsandvalvessubjecttoTypeBandCtestsw$enpressurized l-to P,.

A combined bypass leakage rate of less than or equal to 0.06 L, paths for c.

all penetrations that are secondary containment bypass leakage

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when pressurized to P,.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75L,allpenetrktionsandvalvessubjecttoTypesBandCtests or 0.75 L, as applicable, or (b) with the measured combine'd leakage rate for exceeding 0.60 L,the overall integrated leakage rate to less than or equal

, or (c) with the combined bypass leakage rate exceeding 0.06 L restore to0.7$,L or less than or equal to 0.75 L., as applicable, and the combined leakage rlte for all penetrations and valves subject to Type B and C tests to less than or equal to 0.60 L and the bypass leakage rate to less than or equalto0.06L,priortoin$r,easingtheReactorCoolantSystemtemperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI N45.4-1972:

a.

Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals during WATERFORD - UNIT 3 3/4 6-2 AMENDMENT NO.75

CCNTAINMENT SYSTEMS l

SURVEILLANCE REQUIREMENTS (Continued) i i

't snutdown at either P, 4' psig, or at P, 22 psig, during eacn 10 year service period.

The third test of eacn set shall be concuctea during the snutdown for the 10 year plant inservice inspection.

If any periccic Type A test fails to meet either 0.75 L b.

r 0.75 L,

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a t

the test scnedule for subsequent Type A tests shall be reviewed and approved by the Commission.

If two consecutive Type A tests fail to meet either 0.75 L. or 0.75 L, a Type A test shall be performed at 4

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least every 18 months until two consecutive Type A tests meet either 0.75 L or 0.75 L. at wnich time the acove test schedule may be a

w resumed.

The accuracy of each Type A test snall be verified by a supplement >1 c.

test whicn:

t 1.

Confirms the accuracy of the test by verifying that the supple-I mental test result, L, minus the sum of the Type A and the superimposed leak, L ? are equal to or less than 0.25 L

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a 2.

i Has a duration sufficient to establish accurately the change in i

leakage rate between the Type A test and the supplemental test.

3.

Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to'be between 0.75.L, and 1.25 L,.

Type B and C tests shall be conducted with gas at P,, 44 psig, at l

d.

intervals no greater than 24 months

• except for tests involving:

j 1.

Air locks, 2.

Purge supply and exhaust isolation valves with resilient material seals.

Purge supply and exhaust isolation valves with resilient material i

e.

9 seals shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.7.2.

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• Testing for the first cycle of operation shall be cone during the first I

i refueling cutage.

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t WATERFORD - UNIT 3 3/4 6-3 NN 80 '

14 6

CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) f.

The combined bypass leakage rate shall be determined to be less than or equal to 0.06 L, by applicable Type B and C tests at least once per 24 months

• except for penetrations which are not individually testable; penetrations not individually testable shall be determined to have no detectable leakage when tested with soap bubbles while the containment is pressurized to P, 44 psig, during each Type A a

test.

g.

Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.

h.

The provisions of Specification 4.0.2 are not applicable.

• Testing for the first cycle of operation shall be done during the first refueling outage.

d e

d WATERFORD - UNIT 3 3/4 6-4 AMENDMENT NO. 4

c 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CORTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive I

materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses.

This restriction, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE i

The limitations on containment leakage rates ensure that the total i

containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure, P,.

As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L, or less than or equal to 0.75 L, as applicable during t

performance of the periodic tests to account for possible degradation of the cortainment leakage barriers between leakage tests.

s 4

1 The surveillance requirements for measuring leakage rates are consistent.

with the requirements of Appendix J of 10 CFR Part 50.

Secondary containment bypass leakage paths previously, Table 3.5-1, have been incorporated into plant procedure UNT-005.026.

3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment i

leak rate.

Surveillance testing of the air lock seals provides assurance that i

the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

WATERFORD - UNIT 3 B 3/4 6-1 AMENDMENT NO. 75 i

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.t NPF-38-135 ATTACHMENT B t

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-COVTAINMENT SYSTEMS iC0!#AINMENT LEAKAGE i

t LIMITING CONDITION FOR OPERATION I

L3,6.1.2 Contaiment leakage rates shall be limited to:

f i

a.

An overall integrated leakage rate of:

1.

Less than or equal to L. 0.50 percent by weight of the a

contaiment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P 44 psi 9 0F l

a f

Less than or equal to L. 0.25 percent by weight of the 2.

t contaiment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a reduced pressure of P -

t 22 psig.

b.

A combined leakage rate of less than or equal to 0.60 L for all a

penetrations and valves subject to Type B and C tests when pressurized i

to P -

a e

c.

A combined bypass leakage rate of less than or equal to 0.06 L for a

all penetrations that are secondary contaiment bypass leakage paths when pressurized to P -

a APPLICABILITY:

MODES 1. 2. 3. and 4.

ACTICL

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.With either (a) the measured overall integrated contaiment leakage rate or 0.75 L. as applicable, or (b) with the measured combined exceeding 0.75 L t

a leakage rate for all penetrations and valves subject to Types B and C tests i

exceeding 0.60 L. or (c) with the combined bypass leakage rate exceeding a

0.06 L. restore the overall integrated leakage rate to less than or equal j

a or less than or equal to 0.75 L. as applicable, and the combined to 0.75 L t

a

' leakage rate for all penetrations and valves subject to Type B and C tests to less than or equal to 0.60 L and the bypass leakage rate to less than or j

a equal to 0.06 La prior to increasing the Reactor Coolant System temperature above 200*F.

i SURVEILLANCE REQUIREMENTS 4.6.1.2 The contaiment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI N45 4-1972.

a.

Three Type A tests (Overall Integrated Containment Leakage Rate)

MOVE shall be conducted at 40 i 10 month intervals during TO Pg.

-3/4 63 WATERFORD - UNIT 3 3/4 6-2 AMENDMENT NO. 75 l

i l CONTAltfiENT SYSTEb SURVEfLLANCE Requirements (Continued)

(

a.

Three Type A tests (Overall Integrated Containment Leakage Rate) i shall be conducted at 40 t 10 month intervals E during shutdown ADD l

at either P. 44 psig, or at P. 22 psig, during each 10-year l

a t

service period. The third test of each set shall be conducted i

during the shutdown for the 10-year plant inservice inspection.

i b.

If any periodic Type A test fails to meet either 0.75 L or 0.75 L -

a t

the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission. If two consecutive Type A tests fail to or 0.75 L. a Type A test shall be performed at meet either 0.75 L t

a least every 18 months until two consecutive Type A tests meet either

'i 0.75 L or 0.75 t-t at which time the above test schedule may be l

a resmed.

I c.

The accuracy of each Type A test shall be verified by a supplemental j

test which:

i 1.

Co,1 firms the accuracy of the test by verifying that the supple-f mental test result. L. minus the sm of the Type A and the c

superimposed leak. L are equal to or less than 0.25 L -

f a

a 2.

Has a duration sufficient to establish accurately the change in j

leakage rate between the Type A test and the supplemental test.

4 3.

Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be i

between 0.75 L and 1.25 L -

a a

d.

Type B and C tests shall be conducted with gas at P. 44 psig. at a

intervals no greater than 24 months

• except for tests involving:

I 1.

Air locks.

2.

Purge supply and exhaust isolation valves with resilient f

material seals.

i e.

Purce supply and exhaust isolation valves with resilient material MOVE seals shall be tested and demonstrated OPERABLE per Surveillance TO Pg.

.I Recuirement 4.6.1.7.2.

3/4 6-4 i

- ' Testing for the first cycle of operation shall be done during the first j

refueling outage.

' D one time extension of the test interval is alloed for the third Type A ADD

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' test of the first 10-year service oerlod, provided that performance of the i

lype A test occurs prior to unit restart following Refuel 7.

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l WATERFORD - tlNIT 3 3/4 6-3 AMENDMENT 4

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-CONTAINMENT SYSTEMS i

II

-SURVEILLANCE REQUIREMENTS (Continued)

.I e.

Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per surveillance Requirement 4.6.1.7.2

-j f.

The combined bypass leakage rate shall be determined to be less than

-j a y applicable Type B and C tests at least once or equal to 0.06 l b

per 24 months

• except for rtetrations which are not individually i

testable; penetrations not individually testable shall be determined

]

to have no detectable leakage when tested with soap bubbles while the containment is pressurized to P. 44 psig, during each Type.A a

test.

j g.

Air locks shall be tested and demonstrated OPERABLE per surveillance

[

Requirement 4.6.I.3.

h.

The provisions of Specification 4,0.2 are not applicable.

-f,!

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' " Testing for the first cycle of operation shall be done during tM first f

- refueling outage.

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f WATERFORD - UNIT 3 3/4 6-4 AMENDMENT 4

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d 3/4.6 CONTAltNEhT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAltNENT 3/4.6.1.1 CONTAltNENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses. This restriction. in conjunction with the leakage rate limitation. will limit the SITE BOUNDARY radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

3/4.6.1.2 CONTAlfNEhT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assu1ed in the safety analyses at the peak accident pressure. P. As an added conservatism the a

measured overall integrated leakage rate is further limited to less than or equal to 0.75 L or less than or equal to 0.75 Lt. as applicable during a

performance of the periodic tests to account for possible degradation of the containment leakage barriers betweeit leakage tests.

The surveillance requirements for measuring leakage rates are consistent with the requirements of Appendix J of 10 CFR Part 50.*.

ADD Secondary contaiment bypass leakage paths previously. Table 3.61. have been incorporated into plant procedure UNT-005-026.

3 /4. 6.1.3 CONTAINMEtU AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMEhT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

2A one time extension of the test interval is allowed for the third Type A ADD test of the first 10-year service period. as recuired by Surveillance Reauire-ment 4.6.1.2.a and by Section III.D.(a) of Appendix J to 10 CFR Part 50.

provided the performance of the Type A test occurs prior to unit restart following Refuel L WATERFORD UNIT 3 B 3/4 6-1 AMENDMENT NO. 75