A07397, Responds to Generic Ltr 88-11 Re Methods Described in Rev 2 to Reg Guide 1.99 to Predict Effect of Neutron Radiation on Reactor Vessel Matls.Rcpb for Plants Should Behave in Nonbrittle Manner.Calculated Adjusted Ref Temp Values Encl

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Responds to Generic Ltr 88-11 Re Methods Described in Rev 2 to Reg Guide 1.99 to Predict Effect of Neutron Radiation on Reactor Vessel Matls.Rcpb for Plants Should Behave in Nonbrittle Manner.Calculated Adjusted Ref Temp Values Encl
ML20205Q193
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 11/01/1988
From: Mroczka E
CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
RTR-REGGD-01.099, RTR-REGGD-1.099 A07397, A7397, GL-88-11, NUDOCS 8811090134
Download: ML20205Q193 (7)


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NdRTHEAST UTILITIES o.n.,.i cac., . s.m.n som 8.mn. conn.cnea i .U[$CO*C P O BOX 270 2..."., C . C $ , H ARTFORD. CONNECTICUT 06141-0270 k k J . .v w . . . c (2M) 665-$000 November 1, 1988 Docket Nos. 50-213 50-245 50-336 50-423 A07397 Tse: GL 88-11 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen:

Haddam Neck Plant Millstone Nuclear Power Station Unit Nos.1, 2, and 3 Response to Generic letter 88-11 In a letter da.ed July 12, 1988,II) the NRC transmitted to all licensees Revision 2 to Regulatory Guide 1.99 (Gent.aic Letter 8811). This letter requer.ted that licensees use the methods described in Revision 2 to Regulatory l Guide 1.99 to predict the effect of neutron radiation on reactor vessel l materials, which is required by paragraph V.A of 10CFR50, Appendix G, and to sutMt the results of the technical analysis and a proposed scheduled of any neeessary actions within 180 days of the effective date of Revision 2.

t.oinecticut Yankee Atomic Power Company (CYAPCO) and Northeast Nuclear Energy Company (NNECO) have analy7ed the impact of Revision 2 of Regulatory Guide 1.99 for the Haddam Neck Plant and Hillstone Nuclear Power Station, Unit Nos, 1, 2, and 3. The impact has been evaluated fo.' both the current technical specification pressure / temperature (P/T) limits and the operating license expiratici dates. The values resulting from thit analysis for the adjusted reference temperature (ART) for all four plants do tiot exceed the ART values used to develop the current P/T limit curves. One minor exception is a calculated ART value for Hillstone Unit No. 2 which is 0.29'F higher than the current value. This is considered insignificant in comparison with the margin term, which is added to account for error, of 34'F. The actual calculated ART values for all four plants are provided in Tables A D, included as Attachment 1.

(1) F. J. Miraglia letter to All Licensees of Reactors and Holders of Construction Permits, dated July 12, 1988, 'NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations (Generic Letter 88 11)."

Sol 1090134 881101 g(

PDR ADOCK OSX>0213 P FDC

  • U.S. Nuclear Regulatory Comission A07397/Page 2 November 1, 1988 l

On the basis of this study, CYAPC0 and NNECO have concluded that the reactor ,

coolant pressure boundaries for the Haddam Neck Plant and Millstone Nuclear l Power Station, Unit Nos.1, 2, and 3, should behave in a nonbrittle manner, that the probability of a rapidly propagating fracture should be minimized under regular operating conditions, testing, maintenance and postulated accidents, and that no further actions are necessary. ,

We trust you find this information satisfactory, and we remain available to assist you in the review of this matter.

Very truly yours,  !

CONNECTICUT YAhKEE ATOMIC POWER COMPANY NORTHT ' NUCLEAR El.ERGY COMPANY b - 4/

E. J. Mroptka ~~~f~ l Senior Vice President I i

cc: W. T. Russell, Region i Administrator .

M. L. Boyle. NRC Project Manager, Millstone Unit No. 1 '

D. H. Jaffe, NRC Project Manager, Millstone Unit Nos. 2, 3 A. B. Wang, NRC Project Manager, Haddam Neck Plant

, W. J. Raymond, Senior Resident Inspector, Mill done Unit Nos. 1, 2, and 3  ;

l J. T. Shediosky, Senior Resident inspector, Haddam Neck Plant i

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Docket Nos. 50-213 50 245 50-336 50-423 A07397 t

Attachment 1 Haddam Neck Plant >

Millstone Nuclear Power Station, Unit Nos. 1, 2, and 3 Generic letter 88 11 i Calculated Ad_iusted Reference Terneerature (ART) Values I

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!!ADDAM hTCK l'IANT TABER A ant VAtmEs (*F)

S W FACE f-F13dNCE (D 1 Nev)10"n/" 2 SWtFACE ART CMMICAL CONTDff INITIAL MARGIN IACATION Ut.Z Cu Ut.Z Ni ART IIP. DATE E,, 922 EFFT @32 EFFT $22 EFFT @32 EFFT Nozzle Course 99007-6 0.11 0.20 34 34 1.M4 2.42 138.70 144.76 Iatermed.

Course W9907-7 0.12 0.20 -3 34 5.21 7.58 125.49 129.83 Inver Course V9907-3 0.12 0.29 20 34 2.6 3.78 138.15 144.04 99807-5 0.15 0.20 10 34 2.6 3.78 144.48 151.51 Weld (14asijud-inal) 0.22 0.10 -%  % 4.3 6.26 143.34 150.91 8

TABE2 B NIRASTWE WitT W.1 ~

ART VARANS (*F) sestFACE CEENISTRY INITIAL f-FLUENCE (D 1 NeV)10"m/ -

    • 2 SWFACi ART MARCIN MARCIN 1ACATION FACTOR RT/,, #16 EFFT ART IIF. DATE 932 EFFT @!6 EFFT #32 EFFT 916 EFFT @32 EFFT C-2002-4 140.70 -4 34 34 0.06 0.12 75.38 .93.93 C-2002-5 132.10 26 34 34 0.06 0.12 102.60 120.02 C-2002-6 135.5 20 34 34 0.06 0.12 97.70 115.%

1-073A/C 252 -20  %  % 0.06 0.12 117.07 150.49 3-073 252 -50  %  % 0.06 0.12 57.07 120.49 C-2012-1 252 -20 34.57 53.15 0.014 (top) 0.028 49.14 86.30 C-2012-1 110.25 40 10.% 16.48 0.008 (BR) 0.016 60 72 72.96 C-2012-1 110.25 40 3.62 6.25 0.002 (CL) 0.004 47.24 52.50 8

Tests C NItJstems autT me. 2

  • ART vat 3ES (*F) sumFact f-FLUENCE (D 1 NeV)10"a/"2 SWIF&CE ART CIRMICAL CONTENT INITIAL MARGIN

~ l IACATION ~Jr.Z Cu Vt.Z N1 ART EIF. DATE RJT , @l2 EFFY $32 IFFY @l2 EFFT (32 EFFY Intermed.

Course C505-2 0.13 0.64 25 34 1.6 5.0 162.94 188.02 C505-3 0.13 0.65 0 34 1.9 6.2 142.45 167.06 Lower Course C506-1 0.14 0.61 6 34 1.6 5.0 153.26 180.59 C506-3 0.13 0.70 0 34 1.6 5.0 139.63 165.12 Velds 1-203 0.22 0.99 -45  % 0.25 0.75 154.77 222.81 8-203 0.30 0.18 -60  % 0.25 0.75 86.17 128.81 9-203 0.30 0.06 -55  % 1.6 5.0 154.08 191.02 2-203 0.12 0.20 -50  % 1.6 5.0 87.34 106.97 e

TABER D NIEJ3TW E Mf!T NO. 3 Astr VatAES (*F) sumFACE f-FLUENCE (D 1 NeV)10"n/**2 SIRFACE ART CNERICAL CONTBff INITIAL NAACIN MARCIN ART 1ACATTON Vt.Z Cu Vt.Z Ni IIF. DATE

%, #10 EFFT #32 EFFT #10 EFFT #32 EFFT #10 EFFT $32 EFFT Base Flste 0.05 0.61 60 30.42 34 0.935 3.03 120.84 134.09 (39005-1)

Weld 0.07 0.03 -50 34.78 45.84 0.935 3.03 19.56 41.68 9

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