ML20117G498

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Proposed Tech Specs,Allowing Implementation of Approved Option B to 10CFR50,App J
ML20117G498
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 08/23/1996
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20117G497 List:
References
NUDOCS 9609050210
Download: ML20117G498 (10)
v • d • e


Text

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ANO-1 PROPOSED TECHNICAL SPECIFICATION CHANGES 1 l

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9609050210 960023 PDR ADOCK 05000313 P PDR

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'4.4 REACTOR BUILDING 4.4.1 Reactor Building Leakage Tests Applicability  ;

l Applies to the reactor building.

Objective  ;

To verify that leakage from the reactor building is maintained within allowable limits.

Specification f 4.4.1.1 Integrated leakage rate tests shall be conducted and visual inspections performed in accordance with the Reactor Building Leakage Rate Testing Program.

4.4.1.1.1 Deleted l 4.4.1.1.2 Deleted l 4.4.1.1.3 Deleted l 4.4.1.1.4 Integrated leakage rate testing frequencies shall be in accordance with the Reactor Building Leakage Rate Testing Program.

4.4.1.1.5 Deleted l 4.4.1.1.6 Deleted l l 4.4.1.1.7 Deleted l 4.4.1.2 Local leakage rate tests shall be conducted in accordance with the Reactor Building Leakage Rate Testing Program.

t 4.4.1.2.1 Deleted l ,

4.4.1.2.2 Deleted l 4.4.1.2.3 Deleted l 4.4.1.2.4 Deleted l 4.4.1.2.5 Local leakage rate testing frequencies shall be in accordance with the Reactor Building Leakage Rate Testing Program.

4.4.1.3 Deleted l 4.4.1.4 Isolation Valve Functional Tests Every three months, remotely operated reactor building isolation valves shall be stroked to the position required to fulfill their safety function unless such operation is not practical during plant operation. The latter valves shall be tested once every 18 months.

4.4.1.5 Deleted l Amendment No. H,M,4M,4-M,MG, 79

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ANO-2 PROPOSED TEC_HNICAL SPECIFICATION CHANGES l

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CONTAINMENT SYSTEMS i

$URVEILLANCE REQUIREMENTS l

4.6.1.3.1 Each containment air lock shall be demonstrated OPERABLE as specified in the Containment Leakage Rate Testing Program *. i 4

i 4.6.1.3.2 Each containment air lock interlock shall be demonstrated OPERABLE !

f by testing the air lock interlock mechanism at least once per 184 j days'. l

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  • Leakrate results shall also be evaluated against the acceptance criteria of specification 3.6.1.2.
  • An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

This surveillance requirement is only required to be performed upon entry or exit through the associated containment air lock.

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ARKANSAS - UNIT 2 3/4 6-5 Amendment No.

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CONTAINMENT SYSTEMS J $IMITING CONDITION FOR OPERATION i

]~ 4.6.1.5.2 End Anchorages and Adjacent Concrete Surfaces The structural integrity of the end anchorages of all tendons inspected pursuant to Specification 4.6.1.5.1 and the adjacent concrete surfaces shall be 1

. demonstrated by determining through inspection that no apparent changes  ;

have occurred in the visual appearance of the end anchorage or the l concrete crack patterns adjacent to the end anchorages. Inspections of

the concrete shall be performed during the Type A containment leakage rate
tests (reference Specification 4.6.1.2) while the containment is at its ,

j maximum test pressure. l l

4.6.1.5.3 containment Surfaces The structural integrity of the exposed accessible interior and exterior surfaces of the containment, including the liner plate, shall be determined by a visual inspection of these surfaces and verifying no apparent changes in appearance or other abnormal degradation has occurred in accordance with the Containment Leakage Rate Testing Program.  !

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ARKANSAS - UNIT 2 3/4 6-9 Amendment No. M,Me,

k MARKUP OF CURRENT ANO-1 TECHNICAL SPECIFICATIONS (FOR INFO ONLY)

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4.4 REACTOR BUILDING 4.4.1 Reactor Building Leakage Tests Applicability i

i Applies to the reactor building.  ;

Objective j To verify that leakage from the reactor building is maintained within allowable limits.

Specification 4.4.1.1 Integrated Q,eakage RIate Tiests shall be conducted and visual inspections performed in accordance with the Reactor Buildino Leakace Rate Testino Procram,

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Amendment No. 4M, ~19 l

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MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS l l

4 (FOR INFO ONLY) i

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)

CONTAINMENT SYSTEMS i

SURVEILLANCE REQUIREMENTS 1

i 4.6.1.3.1 Each containment air lock shall be demonstrated OPERABLE as specified in 10 CF" 50, ?.ppendin J,  :: :: : dified by :-

en =pti:n the Containment Leakage Rate Testing Program * .+ prev:d '

O. Sy : nducti..g : d;; :::1 leck t::t with : :: 1 lech:g: ::t

'Of f 0. 01 L xhen t :ted :t 2 10 p:ig'r

b. By ::nducting :n :ver:11 ci 1; h lech t::t with :n :v:::11  !

eir 1;;k lesh g: st: Of f 0.05 La when tested at b "ar-and  !

. The previ ien: cf Specificcti:n t.0.2 ::: n:t :pplic:ble. l 4.6.1.3.2 Each containment air lock interlock shall be demonstrated OPERABLE by testing the air lock interlock mechanism at least once per 184 days'. ,

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  • Leakrate results shall also be evaluated against the acceptance criteria of l

'pecification s 3.6.1.2.

An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

If thi; ;urveillane: :: :: duc uhen th: : nt in=enti: n:t Open,it =sy be def ::d until the nent entry int: cont in=ent. This surveillance requirement is l only required to be performed upon entry or exit through the associated I containment air lock.

ARKANSAS - UNIT 2 3/4 6-5 Amendment No.

I CONTAINMENT SYSTEMS L'IkITIOG CONDITION FOR OPERATION 4.6.1.5.2 End Anchorages and Adjacent Concrete Surfaces The structural integrity of the end anchorages of all tendons inspected pursuant to l Specification 4.6.1.5.1 and the adjacent concrete surfaces shall be demonstrated by determining through inspection that no apparent changes I have occurred in the visual appearance of the end anchorage or the l concrete crack patterns adjacent to the end anchorages. Inspections of '

the concrete shall be performed during the Type A containment leakage rate tests (reference Specification 4.6.1.2) while the contaimment is at its maximum test pressure.

4.6.1.5.3 Containment Surfaces The structural integrity of the exposed accessihle interior and exterior surfaces of the containment, including  ;

the liner plate, shall be determined during th: hutd un fer ::ch Typ: ?. 1

ntair .cne 1 : hag: ::t: t :t ': ferene: Sp :ification t.S.I.2) by a '

visual inspection of these surfaces and verifying no apparent changes in l appearance or other sbnormal degradation has occurred in accordance with the i Containment Lea 3ggy state Testina Procram.  !

1 l4.5.1.5.t 0:leted i

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ARKANSAS - UNIT 2 3/4 6-9 Amendment No. M,MB, I

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