ML20099B175
| ML20099B175 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/22/1992 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML19303E951 | List: |
| References | |
| NUDOCS 9207300231 | |
| Download: ML20099B175 (4) | |
Text
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PROPOSED ANO-2 TECHNICAL SPECIFICATION CHANGE 9207300231 920722 PDR ADOCK 05000368 P
..g REACTOR COOLANT SYSTEM -
SURVEILLANCE-REQUIREMENTS (Contfrued) 4.4.5.4 Acceptance Criteria a.
As used in this Specification 1.
Tubing or Tube means that portion of the tube or sleeve which forms the primary system to secondary system pressure boundary.
2.- Imperfection means an exception-to the dimensions, finish or contour of a tube from that required bv fabrication drawings or specifications.- Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
3' Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a-tube.
4.
Degraded Tube means a tube containing imperfections 220% of the nominal wall thickness caused by degradation.
5.
% Degradation means the percentage of the tube wall thickness affected or removed by degradation.
.6.
Defect means an imperfection of such severity that it exceeds the plugging or repair limit.
A tube containing a defect is defective.
.7.
Plugging or Repair Limit means the imperfection depth at or beyond which the tube shall be removed from service by plugging or repaired by sleeving because it may become unserviceable
~ prior to the next inspection.
The plugging or repair limit is equal to 40% of the nominal parent tube and sleeve wall thickness for. sleeves installed in accordance with B&W Topical Report BAW-2045-PA-00 as supplemented by the information provided in-B&W Report 51-1212539-00, L"BWNS Kinetic S1.eeve Design -
Application to ANO Unit 2'.
The plugging limit is equal to 34%
of the nominal sleeve wall thickness for sleeves installed in accordance'with CENS Report CEN-601-P. "ANO-2 Steam Generator Tube Repair Using Leak-Tight Sleeves",-Revision 01-P, dated July, 1992.
8.
Unserviceable describes the condition of a tube if it leaks lc
- or containsfa-defect large enough to affect its structural integrity-in the event of an Operating Basis Earthquake, a
L
' loss-of-coolant accident, or a steam line or feedwater line break as specified in=4.4.5.3.c, above.
9.
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 ARKANSAS - UNIT 2 3/4 4-9 Amendment No. 133, 1
t;
e REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 10.
Preservice Inspection means an inspection of the full lenyth of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing.
This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
- b. The steam generator shall be determined OPERABLE af ter completing the corresponding actions (plug or repair all tubes exceeding the plugging or repair limit and all tubes containing through-wall cracks) required by Table 4.4-2.
Defective tubes may
,e repaired in accordance with:
- 1) B&W Topical Report BAW-2045PA-00 as supplemented by the information provided in B&W Report 51-1212539-00, "BWNS Kinetic Sleeve Design-Application to ANO Unit 2".
- 2) CENS Report CEN-601-P, "ANO-2 Steam Generator Tube Repair Using Leak Tight Sleeves", Revision 01-P, dated July, 1992 4.4.5.5 Reports Following each inservice inspection of steam generator tubes the a.
number of tubes plugged or sleeved in each steam generator shall be rer;rted to the Commission within 15 days.
- b. The complete results of the steam generator tube inservice inspection shall be reported on an annual basis for the period in which the inspection was completed.
This report shall include:
- 1. Number and extent of tubes inspected.
- 2. Location and percent of wall-thickness penetration for each ind' cation of an mperfection.
3.
Identification of tubes plugged or sleeved.
- c. Results of steam generator tube inspections which fall into Category C-3 shall be reported in a Special Report pursuant to Specification 6.9.2 as denoted by Table 4.4-2.
Notification of the Commission will be made prior to resumption of plant operation.
The written Special Report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
ARKANSAS - UNIT 2 3/4 4-10 Amendmer.t No. 91, 133,
[EACTORCOOLANTSYSTEM l
BASES Wastage-type defects are unlikely with proper chemist ry t reatment of the secondary coolant.
However, even if a defect should develop in cervice, it will be found during scheduled inservice steam generator tubes examinations.
Piugging or sleeving will be required for all tubes with imparfections c.xceeding the plugging or repair limit as defined in Surveillance Requirement 4.4.5.4.a.
Defective tubes may be repaired by sleeving in accordance with the B&W Top.
. Retort BAW-2045PA-00 as supplemented ty the i n f omation provided in B&W Report 51-1212539-00 "BWNS Kinetic Sleeve Design-Application to ANO Unit 2" or CENS Report CEN-601-P,
"'NO-2 Steam Ceneratot Tube Repair Using Leak Tight Sleeves", Revision 01-P, dated July, 1992.
Steam panerator tube inspections of operating plants have demonstrated the capabill y to reliably detect degradation that has penetrated 20% of the tube wall tLhickness.
For sleeved tubes, the adequacy of the system that is used for periodic inservice inspection will be validated.
Additionally, upgraded test.ng methods will be evaluated and appropriately irrplemented as better methods are developed and validated for commercial use.
Whenever the resuits of any steam generator tubing inservice inspection fall into Category C-3 certain results will be reported in a Special Report to the Commission pursuant to Specification 6.9.2 as denoted by Table 4.2-2.
Notification of the Commission will be made prior to resumption of plant operation.
Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necest.ary.
3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakag from the Reactor Coolant Pressu-e
- Boundary, These detection systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems" May 1973.
3/4.4.6.2 REACTOR COOLANT SY5 TEM LEALAGE Industry experience has shown that while a 11mitta amount of leakage is expected from the RCS. the unidentified portlop f this lealage can be reduced to a threshold value of less than 1 GPM.
This threshold value is sufficiently low to ensure early detection of additional leakage.
The 10 GPM IDENTIFIED LEAKAGE limitation provides allowances for a limited amount of leak re f rom known so trees whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detectic stems.
The Surveillance Requirements for RCS Pressure Isolat.on Valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA.
Leaka,.
m the RCS Pressure Isolation Valves is IDENTIFIED LEAKAGE and will be cons) ared as a portion of the allowed limit.
ARKANSAS - UNIT 2 B 3/4 4-3 Amendment No. 91, !)),
fddl dif(d 4 20 $1
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