ML20052G437
| ML20052G437 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 05/12/1982 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| TASK-A-12, TASK-OR 4101N, NUDOCS 8205180358 | |
| Download: ML20052G437 (4) | |
Text
._
J O Commonwealta Edison O
.) One First f4ational Plaza. Chicago, Illinois O 7 Address R: ply to: Post Office Box 767 j-Chicago. Illinois 60690 May 12, 1982 Mr. Harold R.
Denton, Director Of fice of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission Washington, DC 20555
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 NSSS Support Materials NRC Docke t No. 50-45 4, 455, 456 and 457 Reference (a):
January 11, 1982, letter from T.R.
Tramm to H. R. De n t o n.
Dear Mr. Denton:
This is to provide additional information regarding the materials used in the supports for reactor coolant pumps and steam generators at Byron and Braidwood Stations.
Attachment A to this letter describes the specifications for these materials as they relate to fracture toughness.
It supplements the information provided in reference (a) regarding Unresolved Safety Issue A-12.
Please address questions regarding this matter to this One signed original and fifteen copies of this letter are provided for your use.
Very truly yours,
}ik VAd= -
T. R.
Tramm Nuclear Licensing Administrator 1m gool i
Attachment iI 410lN 82 0 5 2. 8 0 Mb S
F ATTACHMENT A BYRON /8RAIDWOOD REACTOR COOLANT PUMP AND STE AM GENERATOR SUPPORT MATERI ALS ASTM A588 Grade A or 8, A618 Grade III, and SA533 Class 2 are the materials used in the steam generator and reactor coolant pump supports.which are welded.
Charpy V notch (Cy) testing was specified for these supports to insure adequate fracture toughness.
The Cy tests were performed on the base metal and qualification welds in accordance with ASME Code,Section III, Div. 1, Subsection NF 2320 and NF 4335, Summer o f 1975 addenda.
These Cy tests were performed at 100F, 300F oelow the assumed lowest service metal 0
0 temperature of 40 F and well below 65 F, the minimum operating temperature for the containment.
NF 2331 contains the acceptance criteria; 15 mils laterial expansion for naterials 5/8" to 1" and 25 mils lateral expansion for material 1" and over.
Im 410lN.
[O Commonwealth ECson
{ C ^) ons Frat Nitional Plua. Chicago. lilinois
~
Address Reply to: Post Othee Box 767 g
j
\\
Chicago, lihnois 60690 May 12, 1982 i
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission Washington, DC 20555
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 NSSS Support Materials NRC Docke t No. 50-45 4, 455, 456 and 457 Reference (a):
January 11, 1982, letter from T. R.
Tramm to H. R. Den t o n.
Dear Mr. Denton:
This is to provide additional information regarding the materials used in the supports for reactor coolant pumps and steam generators at Byron and Braidwood Stations.
Attachment A to this Jetter describes the specifications for these materials as they relate to fracture toughness.
It supplements the information provided in reference (a) regarding Unresolved Safety Issue A-12.
1 Please address questions regarding this matter to this o f fice.
i One signed original and fifteen copies of this letter are provided for your use.
Very truly yours,
]/ N h44= -
I T.R.
Tramm Nuclear Licensing Administrator 1m 1
Attachment 410lN
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ATTACHMENT A BYRON /BRAIDWOOD REACTOR COOLANT PUMP AND STE AM GENER ATOR SUPPORT MATERI ALS ASTM A588 Grade A or B, A618 Grade III, and SA533 Class 2 are the materials used in the steam generator and reactor coolant pump supports which are welded.
Charpy V notch (C ) testing was y
specified for these supports to insure adequate fracture toughness.
The Cy tests were performed on the base metal and qualification welds in accordance with ASME Code,Section III, Div. 1, Subsection NF 2320 and NF 4335, Summer o f 1975 addenda.
These Cy tests were performed a t 100F, 300F below the assumed lowest service metal temperature of 400F and well below 65 F, the minimum operating 0
temperature for the containment.
NF 2331 contains the acceptance criteria; 15 mils laterial expansion for materials 5/8" to 1" and 25 mils lateral expansion for material 1" and over.
1m 410lN
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