ML20003G149
| ML20003G149 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 04/17/1981 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8104280381 | |
| Download: ML20003G149 (2) | |
Text
>
. e, Mabama Power Company 600 Norm 18m Street Post Office Box 2641 Birmmgesm. Asbama 35291 Te4 phone 205 250-1000 m
AlabamaPower mescreem eec:rc system April 17, 1981 Docket No. 50-348
,<tiew
?
' 'c.
Q (/Wl V('
M 4
Director of Nuclear Reactor Regulation
/pJ
/
,7p.,
'7 U. S. Nuclear Regulatory Coc=ission 42 h
7 c.,, k ;>
/ A M Washington, D. C.
20555 r
!\\n Attention:
S. A. Varga Nhrg
/
^
JOSEPH M. FARLEY NUCLEAR PLANT - UNIT h Dj INSERVICE INSPECTION PROGRAM FOR ASME CODE CLASS 1, 2, AND 3 COMPONENTS Centlemen:
The provisions of 10 CFR 50.55a(g), " Inservice Inspection Requirenents", stipulates that specific written relief =ust be requested fro = the Nuclear Regulatory Co==1ssion whenever the require =ents of Section XI of the ASME Code cannot be met.
By our letter dated March 30, 1978, Alaba=a Power Cc=pany sub=itted the J. M. Farley Unit 1 Inservice Inspection Progra=.
In your letter dated December 7, 1979, the NRC approved our Inservice Inspection Program including the relief requests submitted at that ti=e.
Subsequently, one additional area has been identified where the require =ents of Section XI cannot be fulfilled. Consequently, Alabana Power Company hereby sub=its to the NRC for approval the attached relief request which identifies the applicable code require =ents, justification for the relief request, and the testing =ethod to be used as an alternative.
Yours truly, h f' L0
?
i J. 4 sl 0 F. L. Clayton, Jr.
/
WGW:bs Enclosure
\\
e
[g. k cc:
Mr. R. A. Thomas
'g Mr. G. F. Trowbridge Mr. L. L. Kintner Mr. W. H. Bradford 8.10.4 2 8 0 3El h
x J. M. Farley - Unit 1 Request for Relief from ASME Code Section XI Note 17 to the Class 1 Table s
v Component:
Reactor Pressure Vessel Closure Head Cladding
[
Examination Requirement:
l Table IWB-2600 Item 31.13 Category B-I-1 requires either (1) visual and surface or (2) volumetric examination of at least six patches (each 36 sq. in.) evenly distributed in the closure head during each 10-year interval.
Basis for Relief:
The preservice inspection was performed using the visual and surface methods.
The inservice inspections were scheduled to be performed using the same methods. However, due to high radiation level on the interior of the vessel head, these examinations cannot be performed. The radiation dose rate on the clad surface is approximately 25 Rem / Hour. The minimum amount of time required to examine one clad patch is approximately one honr.
Therefore, the minimum radiation exposure dose would be approximately 25 man-Rem.
l' In order to comply with the NRC's ALARA requirements on radiation as stated in Regulatory Guide 8.8 and 8.10, these examinations will be deleted per i
h In addition, the latest NRC-approved ASME Section XI, the 1977 Edition with i
f Addenda through Summer 1978, deletes the requirement for examination of I
Reactor Pressure Vessel closure head cladding.
Alternative Examination:
The Reactor Pressure Vessel closure head welds are volumetrically examined per Table IWB-2600, Item 31.2 Category B-B and Item 31.3 Category B-C.
The closure head cladding adjacent to the welds is also examined volumetrically since Section XI requires that the base material for one wall thickness on each side of the weld also be examined. Although the clad areas adjacent to the welds are not " evenly distributed" as required in Category B-I-1, the total area of examinations as required by Categories B-B and B-C far exceed those of l
Category B-I-1.
Therefore, the weld examinations per Items B1.2 and Bl.3 l
will be used to satisfy the requirements of Item 31.13.
4 l
l l
l
..