ML20042E998
| ML20042E998 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/02/1990 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20042E997 | List: |
| References | |
| NUDOCS 9005070081 | |
| Download: ML20042E998 (4) | |
Text
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4 REACTCR COOLANT SYS'tEW l
3/4.4.10 STRUCTURAL INTEGRITY l
i ASME CODE CLASS 1. 2 AND 3 COMPONENTS LIMITING CONDITION FOR OPERATION I
3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 com-ponents shall be maintained in accordance with $pecification 4.4.10.1.
APPLICABILITY: ALL MODES.
ACTION:
a.
With the structural integrity cf any ASME Code Class 1 com.
l ponent(s) not conforming to the above requirements, restore t
the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT considera-i tions.
b.
With the structural integrity of any ASME Code Class 2 com-ponent(s) not conforming to the above requir>ments restore the structural integrity of the affected component s) to within its limit or isolate the affected component s) prior to increasing the Reactor Coolant System temperature above 200'F.
c.
With the structural integrity of any ASME Code Class 3 com-l ponent(s) not confortning to the above requirements restore the structural integrity of the affected component s) to l
within its limit or isolate the affected component s) from service.
i d.
The provisions of Specification 3.0.4 are not applicable.
I
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l-SURVEILLANCE REQUIREMENTS 4.4.10.1.1 The structural integrity of ASME Code Class 1, 2 and 3 components shall be demonstrated:
a.
Per the requirements of Specification 4.0.5, and-b.
Per the requirements of the augmented inservice inspection program specified in Specification 4.4.10.1.2.
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CALVERT CLIFFS - UNIT I 3/4 4 27 i
9005070081 900502 PDR ADOCK 05000317 P
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i REACTOR CDOLANT SYSTEM t
SURVEILLANCE REOUTREMENTS (Continued) s in addition to the requirements of Specification 4.0.5, each Reactor Coolant Pumo flywheel shall be inspected per the recomendations of Regulatory Position C.4.b of Regulatory Guide 1.14. Revision 1. August 1975.*
4.4.10.1.2 Avomented inservice Inspection Procram for Main Steam and Main Feedwater Piping - The unencapsulated welds greater than 4 inches in nominal diameter in the main steam and ma n feedwater piping runs located outside the containment and traversing safety related areas or located in compartments adjoining safety related areas shall be inspected per the following augmented inservice in-spection program using the applicable rules, acceptance criteria, and repair procedures of the ASME Boiler and Pressure Vessel Code, f
Section XI.1983 Edition and Addenda through Sumer 1983, for Class 2 components.
Each weld shall be examined in accordance with the above ASME Code requirements, except that 100% of the welds shall be examined, cumulatively, during each 10 year in-spection interval. The welds to be examined during each inspection period shall be selected to provide a repre-sentative sample of the conditions of the welds.
If these.
examinations reveal unacceptable structural defects in one or more welds, an additional 1/3 of the welds shall be examined and the inspection schedule for the repaired welds shall revert back as if a new interval had l
l begun.
If additional unacceptable defects are detected in the second sampling, the remainder of the welds shall i
also be inspected.
l
- Reactor coolant pump flywheel inspections for the first inservice inspection interval may be completed 6 ;-.. i;Z in conjunction l
with the reactor coolant pump motor overhaul program.
DURIWG t) HIT I h!utLW6 l
ouTMs No.10 CALVERT CLIFFS - UNIT 1 3/4 5.28 Amendment No. 3,y7),
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REACTOR CTLA'7 SYSTEM 3/4.4.10 STDUCTUR;L INTE30!TY ASMF CODE class 1, 2 tND 3 CCMDONENTS LIMITING CCNOITION FOR OFED.ATION 3.4.10.1 The structural integrity of AS'4E Code Class 1, 2 and 3 com-ponents shall be maintained in accordance with Speeification 4.4.10.1.
APPLICABILITY:
ALL MODES.
ACTION:
With the structural. integrity of any ASME Code Class 1 com-a.
ponent(s) not conforming to the above recuirements, restore the structural integrity of the affected component (s) ::
within its limit or isolate the affetted compenent(s) prior to increasing the Reactor Ceolant System temperature more than 50'F above the minimam temperature requircd by NDT considera-tions.
b.
With the structural integrity of anj ASME Cece Class 2 ccm.
ponent(s) not ccn'crming to the above recuirements, restere the structural integrity of the affecte: ccepenent(s) to within its limit or isolate the affectec component (s) r.rior to increasing the Reactor Coolant System. temperature above 1
200*F.
c.
With the structural integrity of any AS"E Code Class 3 com-l i
ponent(s) not conforming to the above requirements, restore the structural integrity of the a#fected c:mpenent(s) to r
l within its limit or isolate the effected com;cnent(s) fr m l
service.
d.
Tne provisions of Specification 3.0.a are not applicable.
S'.'FNEILL;1CE REOUID.EMENTS l
4.4.10.1.1 The structural integrity of ASME Code Class 1, 2 and 3 compenents i
shall te cem:nstrated:
I a.
Per the re:;uirements cf Specification 4.0.5, ar.d b.
Per the recuiremens c' the sug entet inservice ins:ection pr;; ram s:ecified in Specification 4.a.10,1.2.
CALVEF,7 CLIFF 1-U'i:T 2 3/a a-25 L
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react:; :::. w s.s ty i
suRyt:. act ata ::tSt es ::: ti.u.e1 In accitten to t.e recuiremea.ts of Specificatica 4.0.5, each Reactor
'I aeel sna11 ee inscecteo per tne recomencations of
- ociant 3 r.:
f
$. n,iat:af :: sits:n 0.4.o of Regulatory Guice 1.14 Revision 1 August i
i..
l 4.4.13.1.2
!..,cneatec Inservice inspection program for Main Steam w t a. ree==a:er picing - ine unencaesslates welds greater tnan anc a
j a incnes in nominai clameter in tne main steam and main feedwater piping runs located outside the containment and traversing safety related areas or located in compartments adjoining safety related i
areas snali ce inspected per the following augmented inservice in.
spection program using the applicable rules, acceptance criteria, I
anc repair procecures of the ASME loiler and Pressure Yessel Code.
t Secticn XI, !!E3 teition and Addenda through Sumer 1983, for Class I components.
Eacn weld shall be examined in accordance with the above
[
ASMt Coce recuirements, except that 100% of the welds snail be examined, cumulatively, during each 10 year in-spection interval. The welds to be examined during each inspection period shall be selected to provide a repre-sentative sample of the conditions of the welds.
If these examinations reveal unacceptable structural defects in one or more welds, an additional 1/3 of the welds shall be examined and the inspection schedule for the repaired I
weics snali revert back as if a new interval had
- egun.
If additional unacceptable defects are detected l
in the second sampling, the remainder of the welds snall also be inspected.
' Reactor coolant pump flywheel inspections for the first inservice inspection interval may be completed t,, 2...
1;;; in conjunction with the reactor coolant t
pump motor overhaul program.
%DURWG UNIT 2 REFullIAf 6 ourA6s No. p l
l CALVERT CLIFFS - UNIT 2 3/4 4-29 Amendt.entNo.pp,106, b
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