ML20071Q162

Forwards Revised Summary File for PTS Using Mean of Copper & Nickel Values,W/Revised Chemistry Factors

ML20071Q162
Person / Time
Site:	Seabrook
Issue date:	07/29/1994
From:	Feigenbaum T NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-94087, NUDOCS 9408110104
Download: ML20071Q162 (4)

Text

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Nortli North Atlantic Energy Service Corporation k; f{jg3{Q

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y.O. ne, 300 Seabrook, N1I 03874 (603) 474 9521, Fax (603) 474 2987 o

The Northeast Utilities System Ted C. Feigenbaum NYN-94087 Senior wee President &

Chief Nuclear Officer July 29,1994 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention:

Document Control Desk

References:

(a)

Facility Operating License No. NPF-86, Docket No. 50-443 (b)

North Atlantic Letter NYN-94073 dated June 29,1994, " Generic Letter 92-01, Rev 1, Reactor Vessel Structural Integrity (TAC No. M83512)", T.C. Feigenbaum to USNRC (c)

USNRC Letter dated May 27,1994, " Generic Letter 92-01, Rev 1, Reactor Vessel Structural Integrity (TAC No. M83512)," A.W. De Agazio to T.C. Feigenbaum

Subject:

Generic Letter 92-01, Rev 1, Reactor Vessel Structural Integrity (TAC No. M83512)

Gentlemen:

As previously reported in Reference (b), North Atlantic Energy Service Corporation (North Atlantic) determined that the values for copper and nickel content for the Seabrook Station reactor vessel as stated in the Summary File for Pressurized Thermal Shock provided in Reference (c) are not correct in all cases. The values listed in Reference (c) are those values supplied by the reactor vessel manufacturer, Combustion Engineering, and were contained in the previous submittals for Seabrook Station. Ilowever, the values contained in the initial material certifications supplied by the reactor vessel plate manufacturer Lukens Steel Company are slightly ditTerent in some cases. North Atlantic committed to providing a revised Summary File for Pressurized Thermal Shock using the mean of the copper and i

nickel values, with the revised Chemistry Factors, by July 29, 1994. The revised Summary File for Pressurized Thermal Shock is enclosed.

North Atlantic is reviewing other license documents to determine if they are afTected by this change and will make appropriate changes, if required.

Should you have any questions regarding this matter, please contact Mr. James M. Peschel, Regulatory Compliance Manager at (603) 474-9521, extension 3772.

Very /,yours,

=P ux UvUL32 Ted C. Feigeriba ern l

9408110104 940729 I

fDR ADOCK 05000443 PDR

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United States Nuclear Regulatory Commission July 29,1994

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Attention:

Document Control Desk Page two TCF:MJM/act Enclosure cc:

Mr. Thomas T. Martin Regional Administrator U.S. Nuclear Regulatory Commission Region 1 j

475 Allendale Road King of Prussia, PA.19406 I

Mr. Albert W. De Agazio, Sr. Project Manager Project Directorate 1-4 Division of Reactor Projects l

U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Antone C. Cerne NRC Senior Resident inspector P.O. Ilox 1149 Seabrook, Nil 03874 I

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North Atlantic July 29,1994 t

e ENCI,OSUltE TO NYN-94087 i

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f Summary File for Pressurized Thermal Shock Plcnt Belttine Heat No.

10 Wout.

1RT,

Method of Cheelstry Method of

%Cu XNI Wome Ident.

Ident.

Fluence et Deternin.

Factor Deternin.

EOL/EFPY

!RT.

CF

1. e Secbrook Lower R1808 1 3.1E19 40'F Plant M

\\

Table

-0;95-0.58

$helt Specific 37 Plate l.

.06 A

i EOL:

Lower R1808 2 3.1E19 10'F Plant M

Table 4,05 467-1

.06

.58

}

. r10/17/

ShotI spect fic -

37

-I 2

Plate 6

Lower R1808-3 3.1E19 40*F Plant

$7 Table 44 4 67-Shell Specific 44

.07

.59 f'

Plate f

Int. shell R1806 1 3.1E19 40*F Plant

{6 Tehte w.045 **.61 Plate Speelffc.

28.5 (

1 I

i Int shelt R1806-2 3.1E19 0'F Plant

-3+

3 7

, Table M.06

• • .64 Plate Specific

( 17 of.075 te5.63 Int. Shell R1806-3 3.1E19 10*F Plant 44 47.5 Table l

Plate Specific

)

Int. Shell 4P6052 3.1E19 60'F Plant 34.3 Table 0.07 0.02 Axist Speelffc Welds 101 124A/c Lower 4P6052 3.1E19 60'F Plant 34.3 Table 0.07 0.02

$hell SpectffC Axial Welds 101-142A/C Int. to 4P6052 3.1E19

-60'F Plant 34

• Table 0.07 0.02 Lower SpectfIc Shell Cire. Weld 131 171 References for Seebrook IRT, and cheef cal composition data are from the August 17, 1992, letter from T. C. Folgersee (P$NN) to USNRC Document Control Desk, s@ ject: Reactor Yeassasaaaassassace Capsule Report.

Fluence from August 17, 1992 PTS sdzelttet.

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