ML20072F009

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Proposed Tech Specs,Requesting one-time Exemption from 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors,Section III.D.1.(a)
ML20072F009
Person / Time
Site: San Onofre  
Issue date: 08/17/1994
From:
SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20072E994 List:
References
NUDOCS 9408230167
Download: ML20072F009 (7)


Text

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CCNTAINMENT SYSTEMS

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CCNTAINMENT LEAKAGE Oy:

-Lf L:v!?:sc CCNDIT!:N ~CR :2 ERAT'CN

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3. 6.1. 2
.-.a' 7e t :ea< age rates snall be limited to:

a.

An overall integrated leakage rate of:

Less than or equal to L 0

containmentairper24$o,urs.10percentbyweightoft.te 1.

at P, 55.7 psig, or a

containmentairper24bo,urs.05percentbyweightofthe Less than or equal to L 0

2.

at a reduced pressure of P.

g 27.9 psig, b.

A combined leakage rate of less than 0.60 L, for all penetrations and valves subject to Type B and C tests, when pressurized to P '

a APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate or 0.75 L, as applicable, or (b) with the measured combined exceeding 0.75L,allpenetrktionsandvalvessubjecttoTypesBandCtests leakage rate for

-,)

exceeding 0.60 L, restore the overall integrated leakage rate to less than or a

combined leakag$ or less than or equal to 0.75 L, as applicable, and therateforallp equal to 0.75 L tests to less than 0.60 L, prior to increasing the Reactor Coolant System temperature 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 50 using the methods and provisions of i

ANSI N45.4 - 1972:

l a.

Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals during shutdown at service $e(riod.55.7 psig) or at Pt (27.9 psig) during each 10 year either P Prior to tha Type A tests a visual inspection shall be conducted in accordance with Specification 4.6.1.6 to demonstrate the containment structural integrity.

I i

i SAN ONOFRE-UNIT 2 3/4 6-2 AMENOMENT NO. 93 r

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fDR ADOCK 05000361 9408230167 94o917 h

O ATTACHMENT B EXISTING TECHNICAL SPECIFICATIONS UNIT 3 i

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c sta;w!NT 5 /5'EWS

yra:sw!N~.ia<a0!

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_:w:- sG :~90U:0N 204 psoAT:04 l

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3. 5.1. 2 3 13t-e

'eakage rates snall :s limited to:

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An everall integrated leakage rate of:

a.

p 1.

Less than er equal to L 0

[

containment air per 24 $o,urs.10 percent by weight of t e at P,, 55.7 psig, or hf 2.

Less than or equal to L, 0.05 percent by weight of the containment air per 24 Ifours at a reduced pressure of P,

p 27.9 psig.

h b.

A combined leakage rate of less than 0.60 L for all cenetrations a :

[

valvessubjecttoTypeBandCtests,when$ressurizedtoP,.

y y

APPLICABILITY:

MODES 1, 2, 3 and 4 ACTION:

f'e With either (a) the naasured overall integrated containment leakage rate tO exceeding 0.75 L,all penetrItions and valves subject to Types 8 an E-leakage rate for exceeding 0.60 L, restore the overall integrated leakage rate to less than or i

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

(

combined leakagl rate for all penetrations and valves subject to Type B and C tests to less than 0.60 L temperature above 200*F., prior to increasing the Reactor Coolant Systein 4

N:

SURVEILLANCE REQUtREHENT$

f C,

N 4.6.1.2 The containment leakage ratas shall be demonstrated at the following

'i test schedule and shall be determined in conformance with the criteria i

.J specified in Appendix J of 10 CFR 50 using the methods and provisions of AN5! N45.4 - 1972:

Three Type A tests (Overall Integrated Containment Leakage Rate) a.

I shall be conducted at 40.+ 10 month intervals during shutdown at either P servicebr(55.7psig)oratPt (27.9 psig) during each 10 year iod.

Prior to the Type A tests a visual inspection shall Q

be conducted in accordance with Specification 4.6.1.6 to demonstrata L

the containment structural integrity.

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SAN ONOFRE-UNIT 3 3/4 6-2 MEN 0 MENT N0'. 83

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ATTACHMENT C PROPOSED TECHNICAL SPECIFICATIONS UNIT 2

CONTAINMEJLT 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.

Less than or equal to L, 0.10 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 P., 55.7 psig, or containment air per 24 b,our.05 percent by weight of the Less than or equal to L 0

2.

s at a reduced pressure of P,

t 27.9 psig, b.

A combined leakage rate of less than 0.60 L, for all penetrations andvalvessubjecttoType8andCtests,wI1enpressurizedtoP,.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, or 0.75 L, as applicable, or (b) with the measured combined 1

leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L., restore the overall integrated leakage rate to less than or equal to 0.75 L, or less than or equal to 0.75 L, as applicable, and the t

combined leakage rate for all penetrations and valves subject to Type B and C tests to less than 0.60 L, prior to increasing the Reactor Coolant System temperature above 200oF.

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 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 shutdown at either P, (55.7 psig) or at P (27.9 psig) during each 10-year t

service period.

Prior to the Type A tests a visual inspection shall be conducted in accordance with Specification 4.6.1.6 to demonstrate the containment structural integrity.

'One:timeTonly a stests:intervaliof 60%.10imonths; willi;be; allowed;between Type : Altests isti,clh(thati forf the. Cycl e18 T refueli.ng} outagei no TypefA stest wilF required.?This/isaniexemption5from?10CFR50,[ Appendix;JnSectionilII.D.1.(a).

SAN ON0FRE-UNIT 2 3/4 6-2 AMENDMENT NO.

O ATTACHMENT D PROPOSED TECHNICAL SPECIFICATIONS UNIT 3 1

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:

containment air per 24 b,our.10 percent by weight of the Less than or equal to L 0

1.

s at P., 55.7 psig, or containment air per 24 b,our.05 percent by weight of the Less than or equal to L 0

2.

s a reduced pressure of P,

t 27.9 psig.

b.

A combined leakage rate of less than 0.60 L for all penetrations andvalvessubjecttoTypeBandCtests,wbenpressurizedtoP,.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

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

leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L., restore the overall integrated leakage rate to less than or equal to 0.75 L, or less than or equal to 0.75 L, as applicable, and the t

combined leakage rate for all penetrations and valves subject to Type B and C tests to less than 0.60 L, prior to increasing the Reactor Coolant System temperature above 200oF.

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 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 shutdown at either P, (55.7 psig) or P (27.9 psig) during each 10-year service t

period.

Prior to the Type A tests a visual inspection shall be conducted in accordance with Specification 4.6.1.6 to demonstrate the containment structural integrity.

  • f 0ne time"onlyMalt'estlintervalr fq60110 monthsjill: be7 allowed bstweeri o

Type Attests suchcthat foritiesCycle 81refuelingLoutageLno1 Type;A1. test:will?be t

required.EThisListanLexemption~from;10CFR50,5AppendixJ,9Section911.I.Dilj(a);

SAN ON0FRE-UNIT 3 3/4 6-2 AMENDMENT NO.