ML20070D446
| ML20070D446 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/29/1994 |
| From: | Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-01, GL-92-1, NYN-94073, TAC-M83512, NUDOCS 9407080096 | |
| Download: ML20070D446 (5) | |
Text
gpA A"::::S North North Atlantic Energy Service Corporation 4
F.o. 3,,300 i)
Atlantic Seabrmk, Nil 03874 (603) 474 9521, Fax (603) 474 2987 The Northeast Utilities System Ted C. Feigenbaum NYN 94073 Senior %ce President &
Chief Nuclear Officer June 29,1994 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention:
Document Control Desk
References:
(a)
Facility Operating License No. NPF so, Docket No. 50-443 (b)
USNRC 1.etter 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:
North Atlantic Energy Service Corporation (North Atlantic) has reviewed the information provided by Reference (b) to verify that it accurately reflects the information for the Seabrook Station reactor 5 essel. The infonnation in Reference (b) is data contained in the NRC's Reactor Vessel Integrity Database (RVID) for pressurized thermal shock and upper-shelf energy.
Reference (b) accurately reflects the data for Seabrook Station's reactor vessel with the following exceptions:
The summary files for Pressurized Thennat Shock and for Upper Shelf Energy state in Column i that the expiration of license for Seabrook Station is 10/17/2006. The correct expiration of license is 10/17/2026.
The values for copper and nickel content in the Summary File for Pressurized Thenual Shock are those values supplied by the reactor vessel manufacturer, Combustion Engineering, and were contained in the previous submittals for Seabrook Station. However, the values contained in the initial material certifications supplied by the reactor vessel plate n anufacturer Lukens Stee:
Company are slightly different in some cases. A revised table using the mean of the copper and nickel values, and the revised Chemistry Factors, is being prepared and will be provided by separate correspondence by July 29,1994.
Should you have any questions regarding this matter, please contact Mr. James M. Peschel, Regulatory Compliance Manager at (603) 474-9521, extension 3772.
Very truly y urs,
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.d'c Ted C. Feigenbaum I
9407080096 940629 PDR ADOCK 05000443 j
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United States Nuclear Regulatory Commission June 29,1994 Attention.
Documert Control Desk Page two I
TCF:MJM/act Enclosure 1
cc:
Mr. Thomas T. Martin Regional Administrator U.S. Nuclear Regulatory Commission Region I i
475 Allendale Road King of Prussia, PA 19406 Mr. Albert W. De Agazio, Sr. Project Manager Project Directorate I-4 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Antone C. Cerne NRC Senior Resident inspector P.O. Box 1149 Seabrook, Nil 03874
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North Atlantic l
June 29,1994 l'NClJ)SilRE TO NYN-94073 e~
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Sumary File for Pressurized Thermal Shock Plant Beltline Heat No.
ID Neut.
I R T.
Method of Chemistry Method of ICu tut Nwne Ident.
Ident.
Fluence et Determin.
Factor Determin.
EOL/EFPY 1 R T.
CF 5eabrook Lower R1808 1 3.1E19 40'F Plant 31 Table 0.05 0.58 thell specific Ptete E0L:
ower R1808 2 3.1E19 10'F Plant 31 Table 0.05 0.57 10/ 9/
shell specifte
-2006~~
Piete 00k Lower R1808 3 3.1E19 40'F Plant 37 Table 0.06 0.57 Shell Cpecific Plate int. Shell R1806 1 3.1E19 40*F Plant 26 Table 0.04 0.64 Ptete Specific Int. Shell R1806 2 3.1E19 0'F Plant 31 Table 0.05 0.65
, Plate specifle int, $ bell R1806-3 3.1E19 10'F Plant 64 Table 0.07 0.65 ptete speelffc Int. Shell 4P6052 3.1E19 60'F Plant 34.3 Table 0.07 0.0 Axial specific kelde 101 124A/c Lower 4P6052 3.1E19 60*F Plant 34.3 Table 0.07 0.02 shett specifte Aalet Velds 101 142A/C Int to 4P6052 3.1E19 60*F Plant 34.3 Tebte 0.07 0.02 Lower
$pecific Shell Cire. Weld 101 171 References for Seabrock 1RT. and chemical composition data are from the August 17, 1992, letter from T. C. Folgerteue (P$NN) to USNRC Document Controt Desk, etbject: Reactor Vasseeeeeeeeeeeence Capsule Report.
Fluence from August 17, 1992 PTS stinittal.
~
Sumary File for Upper Shelf Cnsrgy w-Plant Fene Belttfrw West No, Meterial 1/4T USE 1/4T Unfrred.
Method of Ident.
Type et Neutron USE Deternin.
EDL/EFPY Fluence et Unirred.
EOL/EFPY Usf sembrook Lower R1808 1 A 5338 1 61 1.85E19 78 Direct Shell Plate EOL:
tower R1808 2 A 5338 1 60 1.85E19 77 Direct 10/17/
shett
-2006 piete Lowr R1808 3 A 5338 1 68 1.85E19 T8 Direct shell Piete Int. Shett R1806 1 A 5338 1 64 1.85E19 -
82 ofroct plate Int, shell 41806 2 A 5338 1 80 1.85E19 102 Direct Piete Int. shet t 41806 3 A 5338 1 90 1.85Ei9 115 Direct Piete Int. shott 4P6052 Linde 110 1.85E19 156 sury.
Axlel 0091, SAW Walde Wotd 101 174A/c Lowr 4P6052 Linde 110 1.85E19 156
- sury, shell 0091, SAW Axlet Weld Welde 101 142A/C Int. to 4P6052 Linde 110 1.85E19 156 sury.
Lower 0091, SAW shell Weld Cire. Weld 101 171 References for tembrook UUSE and cheelcel cosposition date are from the August 17, 1992 letter from T. C. Feuertmus (PSNN) to U$NRC Document Control Desk, s4Jocts teactor vesset surveillance Capeute toport.
Fluence from August 17, 1992 PTS e delttet.
,