ML20140A557

Forwards Projected Values of Rt Pressurized Thermal Shock, Per 10CFR50,Section 50.61(b)(1).Ref Temp Determination Also Encl

ML20140A557
Person / Time
Site:	Mcguire, McGuire
Issue date:	01/15/1986
From:	Tucker H DUKE POWER CO.
To:	Harold Denton, Youngblood B Office of Nuclear Reactor Regulation
References
REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR TAC-59962, TAC-59963, NUDOCS 8601230222
Download: ML20140A557 (4)

Text

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DUKE Powna Gone.txy 1*.O.150X 33ttM)

Cl(A14LOTTE. N,0. 215242 IIAI. II. TUCKER TrLe n=nsown wwarar.nor=, (704) 07:F4504

===*-r== January 15, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: [B'.'J1 Youitgblood," Director

'PWR Project Directorate #4

Subject:

McGuire Nuclear Station Docket Nos. 50-369 and 50-370

Dear Mr. Denton:

Pursuant to 10CFR50, 550.61 (b)(1), please find attached the projected valves of RT gg for McGuire Nuclear Station.

Please feel free to contact us if you require any additional information.

Very truly yours.

M /

Hal B. Tucker RLG/j gm Attachments xc: Dr. J. Nelson Grace, Reg. Admin.

U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Darl Hood, Project Manager Division of Licensing Office of Nuclear Regulatory Commission Washington, D.C. 20555 Mr. W.T. Orders NRC Resident Inspector McGuire Nuclear Station

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Ntt tMaN AD - J. Knicut (3tr only)

Es (sALI.ARD)

Escss (ROSA)

Pss (cAam1LL)

R$s (BERLINCER)

' I ros (scamaovan 0601230222 860115 PDR ADOCK 0 % g9 P

_ . ~ .- . . - _ . .. _ _ . . . . ._ . _ - .

4 REFERENCE TEMPERATURE DETERMINATION FOR THE MCGU1RE NUCLEAR STATION i in response to the requirements of.10CFR20.61, Fracture Toughness Require-ments for Protection Against Pressurized Thermal Shock, the reference tem-peratures for the McGuire Nuclear Station reactor vessel beltline materials

} have been calculated for the expected service life of the station.

[

The materials were evaluated based upon the expected maximum fluence at 32 EEPY as determined by the analyses associated with McGuire Unit 1 ,

radiation surveillance program's first capsule withdrawal and examination. '

This introduces significant conservatism due to the following points:

! 1 1

e Expected spacial variations in fluence upon the vessel '

4 results in the use of the maximum vessel fluence over-

[ estimating the radiation damage for most of the beltline j materials i

j e Low neutron leakage core loading patterns have been

implemented at McGuire (after removal of first capsule) and thus the fluence at 32 EPPY based upon the capsule overestimates the expected fluence at the expiration date of the operating license f Although the above conservatisms were applied to the calculation of the i McGuire values of RTPTS, no material in the beltline region of the vessels is expected to exceed the screening criteria. Upon evaluation of future

capsule reports and revised estimates of end-of-life fluence values, the-I RTprs values provided on the attached pages shall be updated.

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Region (Code #) 1(F) M(F) Cu(%) Ni(%) F(E-19) RTPTS(F)

Inter. Shell (B5012-1) 34 48 0.13 0.60 2.90 187 Inter. Shell (B5012-2) 0 48 0.13 0.62 2.90 154 i

Inter. Shell (B5012-3) -13 48 0.10 0.66 2.90 116 Lower Shell (B5013-1) 0 48 0.14- 0.56 2.90 159 i Lower Shell (B5013-2) 30 48 0.10 0.52 2.90 152 '

l Lower Shell (B5013-3) 15 48 0.10 0.55 2.90 138 j

Inter./ Lower Wold (G1.39) -70 48 0.05 -

-2.90 -

Inter. Long. Welds (M1.22) -50 48 0.21 0.88 2.90 203

) Lower Long. Weld (M1.32) -56 59 0.20 -

2.90 -

Lower Long. Weld (M1.33)

-56 59 0.21 0.68 2.90 188 Lower Long. Weld (M1.34) -56 59 0.30 0.64 2.90 268 4

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I Region I(F) M(F) Cu(%) Ni(%) F(E-19) RTPTS(F) i i

Inter. Shell -4 48 0.16- 0.85 2.90 195 i Lower Shell -30 48 0.15 0.88 2.90 -161. ,

j Inter./ Lower k' eld -68 48 0.05 0.70 2.90 15 i.

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