ML20134M414

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Proposed Tech Spec Section 3/4.4.5,providing Addendum Re Specific Alternative Action for Defective Steam Generator Tubes & Repair of Tubes Using NRC Approved Method.Proposed No Significant Hazards Determination Encl
ML20134M414
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 08/30/1985
From:
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20134M412 List:
References
NUDOCS 8509040114
Download: ML20134M414 (3)


Text

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. ATTACIDfENT I Page 1 of'2 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 Acceptance Criteria

a. As used in this Specification:  !
1. Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings o i specifications. Eddy-current testing indications below 20% o the nominal tube wall thickness, if detectable, may be
considered as imperfections.
2. Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
3. Degraded Tube means a tube containing imperfections greater than or equal to 20% of the nominal wall thickness caused by degradation. _ NOTE 1
4.  % Degradation means the percentage of the tube wall thickness affected or removed by degradation. i
5. Defect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective.
6. Plugging Limit means the imperfection depth at or beyond which the tube shall be removed from service and is equal to 40% of

, the nominal tube wall thickness._se n (

7. Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a

! loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.

8. Tube Inspection means an inspection of the steam generator tube
from the point of entry (hot leg side) completely around the l 4

U-bend.to the top support'of the cold leg.

N011L1.3 THiS_I.RITERIA 3055__NOT KtTt.'( ~ID_%1h55 JbR _.

_WatcMc_SPEcWtc . WmtPJ4ATivf._ACdoRJA5_EcAt4_.1@/tEWe'D_ . l At4n_ATProviQ __BL_THE_t4% l 850904o114 850830 5-PDR ADOCK O P

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3/4 4-14 SUM 1ER - UNIT 1 .

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' c TABLE 4.4-2 ,

S

=

0 STEAM GENERATOR TUBE INSPECTION g

O N 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION h

! 5 IST SAMPLE INSPECTION Action Required Result Action Required Action' Required Result Sample Site Result N N/A N/A N/A . y C-1 None N/A '

g A minimum of S Tubes per S. G. *e REPW N/A N/A Plug" defective tubes C-1 ,e upshl8pe C-2 and inspect additional Plugbefective tubes C-1 Nonen REPAk*

and inspect additional Plug 9efective tubes n

25 tubes in this S. G. C-2 C-2 45 tubes in this S. G. Perform action for '

C-3 C-3 result of first sample .

s m

Perform action for u C-3 C-3 result of first N/A N/A

p

) sempie oo C-3 Inspect all tu All other e"

i this S. G., p 5. G.s are None N/A N/A N d lective tubes and C-1 o inspect 25 tubes $ ,rne S. G.s Perform action for N/A N/A each other S G ,in C-2 but no N C-2 result of second additional ,,,p g, Prompt notification S.G.we to NRC pursuant C-3 to 10 CFR 50.72 Additional Inspect all tubes in (b)2(1) and S. G. is C-3 each S. G. and plug,e4 (tP M

Prompt notification N/A N/A

' f 2(11) g to NRC pursuant to 10 CFR 50.72 I * (b)2(1) and 10 f, ,

CFR 50.73(a)2(ii)

s Where N is the number of steam genwators in the unit, and n is the number of steam generators inspected ta8 S=3"% n during an inspection ue

$ REPAIR. 6y NRC APfRoVED METHOD e

O ATTACHHENT II Proposed No Significant Hazards Determination Current Technical Specifications define a plugging limit which requires all steam generator tubes with eddy current results indicating a greater than 40%

thru-wall imperfection to be plugged and removed from service. However, industry has now provided repair methods and analyses which allow for some tubes to be repaired or remain in service. The proposed Technical Specification change would not always require tube plugging, but would allow SCE&G the alternative of: 1) leaving a steam generator tube in service providing the NRC had reviewed and approved the justification for doing so, or;

2) repairing the tube using an approved NRC method.

Because the above described Technical Specification change requires prior specific NRC review and approval for all repair methods and degraded tubes left in service, SCE&G proposes that this amendment: 1) does not involve a s igni ficant increase in the probability or consequences of an accident previously evaluated; 2) does not create the possibility of a new or different kind of accident from any accident previously evaluated; or 3) involve a significant reduction in a margin of safety. Therefore, SCE&G concludes that a no signficant hazards determination is justified.