ML20138K612
| ML20138K612 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/06/1985 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20138K607 | List: |
| References | |
| NUDOCS 8512190006 | |
| Download: ML20138K612 (6) | |
Text
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'1 Docket No. 50-213 9-Attachment Haddam Neck Plant Proposed Revision to Technical Specifications
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- l; a) A seismic-occurrence greater than the operating basis It earthquake. -
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b) : A loss ' of coolant accident which causes significant deviations in temperature or pressure which affect the i
' integrity of the steam generator tubes, or requires actuation of the engineered safeguards.
c)
A major steam linc or major feedwater line break.
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D.- Acceptance Criteria:
1.
As used h this Specification:
-a)
Imperfection means an exception---to the l dimensions, P
. finish or contour of a tube from that required by fabrication drawings or specifications.. Eddy-current testing indications below 20% of the nominal tube wall thickness, - if detectable, may be considered as imperfections.
b)
Degradation means a servicsinduced cracking, wastage, pitting, wear or general corrosion occurring on either inside or outside of a tube.
i c)
Degraded Tube means a tube containing imperfections 20 % of the nominal wall thickness ci sed by M'
- degradation.
d)
% Degradation means the percentage of the tube wall thickness affected or removed by degradation.
r e) _ Defect means an imperfection of such severity that it exceeds the plugging limit. A tube or sleeve containing a defect is defective.
f). Plugging Limit - means the imperfection depth at or beyond which the tube or sleeve'shall be removed from l
' service because it may become unserviceable prior to the next inspection and is equal to 50% of the nominal
- tube wall thickness for tubes.*
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- The plugging limit for sleeves will be determined prior to the next refueling outage.
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4 g), 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 a Operating Basis
. Earthquake, a loss-of-coolant accident, or. a steam line or feedwater line break as specified in Specification 4.10.1.C.3.
h)
Tube Inspection means an inspection of.the steam generator. tube from the point.of entry (hot leg side) completely around the U-bend to the top support of.the -
cold leg.
2.
The Steam Generator may be returned to service - after completing the corresponding actions (plug or sleeve all tubes exceeding the plugging limit and plug all defective sleeves) required by Table 4.10.1-2.
E. ~ Following each inservice inspection of steam generator tubes, the number of tubes plugged or sleeved in each steam generator shall be reported in accordance with Specification 6.9.
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' BASIS The Surveillance Requirements for > inspection of steam generator tubes ensure that structural integrity of this portion of the reactor coolant pressure boundary will be maintained.
The program for
. Inservice inspection of steam genera:or tubes is based on the following criteria.
L a)
Modification of Regulatory Guide 1.83, Revision 1.
b) 'On previous Eddy Current Examinations results Inservice Inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of tubes in the event that there is evidence of mechanical damage or progressive degradation due to
- design,' manufacturing errors, or inservice conditions that lead to corrosion, or excess leakage. Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
. The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits 4'
found to result in negligible corrosion of the steam generator tubes.
Specified chemistry treatment of the secondary coolant also limits the possibility of wastage - type defects.
If the secondary coolant chemistry is not maintained within these limits, localized corrosion Jmay result in stress corrosion cracking. The ex+ent of cracking during plant operation _would be limited by the limitation of steam generator tube leakage between the primary coolant system and the secondary
. system imposed. in Specification, Section 3.14, Primary System-Leakage.
Operating plants have demonstrated that primary to secondary leakage specified in Specification 3.14 can readily be detected by radiation monitoring of steam generator blowdown.
If Afect should develop in service, it should _ be found during scheduled lidervice steam generator tube examinations. Plugging or sleeving will be required for all tubes with imperfections equal to or exceeding the plugging limit of-50% _ of the tube nominal wall thickness. Tubes containing sleeves with imperfections exceeding the -
' plugging limit will be plugged. Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the ' original tube wall thickness.
Whenever the ~ results of any steam generator tubing inservice inspection fall into. Category C-3, these results will be promptly reported to -the Commission pursuant to Specification 6.9 prior to resumption of plant operation.
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_ _ _ _. _ _, _. _, _. _ _. ~. _. _....
r TABLE 4.10.1-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE o
-INSPECTED DURING INSERVICE INSPECTION Preservice Inspection None No. of Steam Generators per Unit Four First Inservice Inspection (2)
All Second & Subsequent Inservice Inspections One(l) -
. Table Notation:
- (1)
The inservice inspection may be limited to one steam generator on a rotating schedule encompassing 12% of the tubes if the results of the first or previous
- inspections indicate that all steam generr. tors are performing in a like manner. Note that under some circumstances, the operating conditions in one or more steam generators may be found to be more severe than those in other steam generators. Under such circumstances the sample sequence shall be modified to inspect the most severe conditions.
(2) ' The first inservice base line inspection was performed in 1975.-
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.. p TABLE 4.10.1-2
- STEAM GENERATOR TUBE INSPECTION' Ist SAMPLE INSPECTION 2nd SAMPLE INSPECTION.
3rd SAMPLE INSPECTION Sample Size Result '
' Action Required '
Result
' Action Required Result
' Action Required A minimum of C-l '
None N/A N/A N/A N/A S Tubes per S.G.
C-2 Repair defective tubes C-1 None N/A N/A and inspect additional defective tubes C-2 Repair Repair.
C-1 None 25 tubes in this S.G.*
C-2 and inspect -
defective tubes
- additional 45 tubes C-3 Perform action for in this S.G.*
C-3 result of first -
sample C-3 Perform action for N/A N/A C-3 result of first sample ~
C-3 Inspect all All other tubes in S.G.s are None N/A N/A l
' this S. G., repair C-1 defective tubes and Some S.G.s Perform action for.
N/A N/A inspect 25 tubes in C-2 but no C-2 result of second i
each other S.G.*
additional sample l
l S.G. are l
Prompt notification -
C-3
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to NRC pursuant to specification Additional Inspect all 6.9 S.G. is C-3 tubes in each S.G. and repair i
defective tubes.*
Prompt notification N/A N/A i
to NRC pursuant j
to Specification 6.9 i
S = l_2%
Where n is the number of steam generators inspected during an inspection.
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- Repair of defective tubes shall be limited to plugging with the exception of those tubes which may be sleeved. Tubes with defective sleeves shall be plugged.
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