ML20071D226
| ML20071D226 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  (DPR-24-A-063, DPR-24-A-63, DPR-27-A-068, DPR-27-A-68) |
| Issue date: | 02/17/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20071D227 | List: |
| References | |
| TAC-49449, TAC-49450, NUDOCS 8303090268 | |
| Download: ML20071D226 (3) | |
Text
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Tablo 1 Class 1 Compon:nts Licensee proposed Relief IWB-2600 IWB-2500 System or Area to be Required alterna-request item no.
exam. cat.
component examined method tive exam.
status Bl.4 B-D Reactor Nozzle-to-Volumetric Volumetric -
Granted vessel vessel welds at frequency all nozzles nozzles and inside below:
once every (6) radiused 1st period -
10 years when sections 2 welds core barrel 2nd perid -
is removed 1 or 2 welds 3rd period -
remaining welds Bl.6 B-F Safety Weld Volumetric Volumetric Granted Injection
& surface only once every nozzle-at frequency 10 years when to-safe in IWB-2411.
core barrel end is remcved Bl.12 B-H Reactor Integrally-Volumetric Volumetric-f, Granted vessel welded at frequency 100% of weld.
supports below:
when core ist period-barrel is 25%
removed 2nd period -
during 25%
interval 3rd period -
remainder 01.14 E-I-1 Reacter Cladding Visual at Visual -
Granted (Applies vessel patches frequency 100% when to Unit 1 below:
core barrel only) 1st period -
is removed
'25%
2nd period -
25'd 8303090268 830217 3rd period -
PDRADOCK05000g P
B3.7 B-H Regenera-Integrally -
Volumetric Visual Granted tive heat welded sup-(10% of exchaager ports weld)
B5.4 B-K-1 Reactor Integrally -
Volumetric Visual Granted coolant welded pumps supports B5.6 B-L-1 Reactor Pump Volumetric Examine Weld Granted coolant casing To 1977 578 pumps weldsSection XI Code
2, containment isolation valves will be tested in accordance with Technical Specification 15.4.4 instead of Section IWV-3420, Valve Leak Rate Test.
Bases l
The proposed inspection program is, where practical, in compliance with the recom=endations of ASME Boiler and Pressure Vessel Code,Section XI, Su=mer.
1971 Addenda.
It must be recognised, however, that equipment and techniques to perform the inspection are still in development.
It is recognized, however, that examinations in certain areas are necessary and therefore a schedule is proposed that includes areas and frequencies that are believed practical at this tice for this reactor.
In most areas scheduled for test, a. detailed pre-service mapping will be conducted using techniques which can be used for post-operation inspections.
The areas indicated for inspection represent those of relatively high stress and therefore will serve to indicate potential problems before significant flaws develop there or at other areas. As more experience is gained in operation of pressurized-water reactors, the recommended time schedule and location of inspection might be altered, or should new techniques be developed, consideration will be given to incorporate these new techniques into this inapection program.
t The use of conventional non-destructive, direct visual and remote visual test techniques can be applied to the inspection of all primary loop co=ponents except.for the reactor vessel,.
The reactor vessel presents special problems because of the radiation levels and remote underwater accessibility to this component.
Because of these limitations on access to the reactor vessel, several steps have been incorporated into the design and manufacturing procedures inprepgyptionfornoniestructivetest techniques which may be available in the future The techniques for in-service inspection include the use of visual inspections, volumetric (ultrasonic or radiographic) and surface (d.ye penetrant or magnetic particle) testing of selected parts during refueling periods.
The intent of the inspection is the detection of flaws large enough to initiate fast fracture and gross leakage prior to subsequent inspection. At this' time it is judged that such a flaw is substantially larger than 1/2 inch by 1 inch which is the degree of detectability.
The inspection method is designed to detect flaws of this magniture.
(1)
FSAR - Section 4.4 Point Ec.:ch Unit 1 15.4.2-2 Amctdment No. 63
~
<s','
j._
2; Containment isolation valves 'will be tested in accordance with I
Technical Specification 15.4.4 instead of Section IWV-3420, Valve Leak _ Rate Test.
l Bases The proposed inspection program is, where practical, in compliance with the recom=endations of ASME Boiler and Pressure Vessel Code,Section XI, Summer
'1971 Addenda.
It must be recognized, however, that equipment and techniques to perform the inspection are still in development.
It is recognized, however.
that examinations in certain areas are necessary and therefore a schedule is i
proposed that includes areas and frequencies that are believed practical at
[
this time for this reactor.
In most areas scheduled for test, a detailed i
pre-service mapping will'be conducted using techniques which can'be used for post-operation inspections.
The areas indicated for inspection represent those of relatively high stress and therefore will serve to indicate potential problems before significant flaws develop there or at other areas. As more 4
- experience is gained in operation of pressurized-water reactors, the recommended 1
time schedule and location of inspection might be altered, or should new techniques be developed, consideration will be given to incorporate these new techniques into this inspection program.
The use of conventional non-destructive, direct. visual and remote visual test i
techniques can be applied to the inspection of all primary loop components except.for the reactor vessel.
The reactor vessel presents special problems l
because of the radiation levels and remote underwater accessibility to this I
component.
Because of these limitations on access to the reactor vessel, i
several steps have been incorporated into the design and manufacturing procedures future.g{ftionfornon-destructivetesttechniqueswhichmaybeavailableinthe in prep I
The techniques for in-service inspection include the use of visual inspections, g
volu. metric (ultrasonic or radiographic) and surface (d,ye penetrant or cagnetic particle) testing of selected parts during refueling periods.
The intent of the inspection is the detection of flaws large enough to initiate i
fast fracture and gross leakage prior to subsequent inspection. At th'is,. time it is judged that such a flaw is substantially larger than 1/2 inch by 1 inch t
which is the degree of detectability.
The inspection method is designed to
]
detect flaws of this.cagniture.
s' (1)
FSAR - Section 4.4 Point' Beach Unit 2 15.4.2-2 Amendment No. 68
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