ML20086N625
| ML20086N625 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/06/1971 |
| From: | Boyer V PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Kirkman R US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20086N624 | List: |
| References | |
| NUDOCS 8402210252 | |
| Download: ML20086N625 (3) | |
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l PHILADELPHIA ELECTRIC COMPANY I
l 1000 CHESTNUT STREET PHILADELPHI A. PA.19105 V. S. BOYER AREA CODE SIS April 6, 1971
_j nce..... oic wauan S mo Mr. Robert W. Kirkman Director United States Atomic Energy Commission l
Division of Compliance, Region I 970 Broad Street I
Newark, New Jersey 07102
Dear Mr. Kirkman:
This letter is in response to your letter of March 9, 1971 to gr.
R.
F. Gilkeson concerning apparent deficiencies identified I
by your representatives during an-inspection of the Chicago Bridge and Iron fabrication shop in Memphis, Tenn. on November 18-20, 19,70, relating to the manufacture of the reactor vessel for Peach j
.*yottomUnitNo.
2.
Our response is as follows, numbered as in your letter.
J 1.
Complete film coverage of the girth seam between the No. 1 l
and No. 2 shell rings has been established by CB&I by ref-
.I crence to the dimensioned intervals recorded on their drawing
'j between markers and comparing the overlaps on the two adjacent films.
This comparison showed a 2-1/2" overlap at the end j
marked "26" and a 2" overlap at the "27" end which barely missed the marker in the film in question.
As a further
.l check, the theoretical vessel circumference requires 58 films to go around che vessel using a nominal 14" film interval and 58 films were accounted for.
- l 2.
There were two MK-207 six-inch weld neck flanges, serial Nos. 207-146-2 and 207-139-3, for which UT inspection re-ports could not be found during the course of Mr. Potapovs revier at Memphis.
A GE Quality Control representative has since verified at B&W, Mt. Vernon, that these flanges were UT inspec*ted' to approved procedure UT-4, Rev. O.
Copies of the records have been received at CB&I, Memphis, to com-
'x plete the information package.
5 8402210252 710428 PDR ADOCK 05000277 O
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April 6, 1971 i
2 Mr. Robert W. Kirkman l
1, 3.
CB&I has submitted a contract variation, DR 4962-16 to cover the excess accumulated time at temperature of the MK-57 lower shell course of PB-2.
General Electric has accepted this deviation from their vessel specification.
I As you indicated, this overrun is permitted by ASME.
I General Electric Quality Control personnel have completed i
their technical review of the PB-2 reactor vessel documentation i
and have informed us that no other discrepancies similar to the above on either B&W or CB&I portions of this vessel have been f
found.
If you have any questions concerning the above, please 7
feel free to communicate with me or directly with our Project Manager, Mr. John Moskowitz.
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t' Sincerely,-
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