ML20137L535

Submits Projected Values of RT Pressurized Thermal Shock. Calculated Values for Each Plate,Axial Weld & Circumferential Weld Applicable Screening Criterion Encl

ML20137L535
Person / Time
Site:	Calvert Cliffs
Issue date:	01/23/1986
From:	Tierman J BALTIMORE GAS & ELECTRIC CO.
To:	Thadani A Office of Nuclear Reactor Regulation
References
REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR NUDOCS 8601280012
Download: ML20137L535 (3)

Text

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BALTIMORE GAS AND ELECTRIC CHARLES CENTER R O. BOX 1475 BALTIMORE, MARYLAND 21203 JOSEPH A.TIERNAN 3anuary 23, 1(186 Vict PatslotNT NuctEAn ENERGY U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 Attention:

Mr. Ashok C. Thadani, Director PWR Project Directorate #3 Division of PWR Licensing-B

Subject:

Calvert Cliffs Nuclear Power Plant Units Nos.1 & 2; Dockets Nos. 50-317 and 50-313 Response to Pressurized Thermal Shock Rule Gentlemen:

Pursuant to 10 CFR 30.61, " Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events", Baltimore Gas and Electric Company hereby submits projected values of "RTP f r the Unit I and 2 reactor vessels calculated in accordance with the method spec.TS"d in Paragraph 50.61(b)(2). The calculated values tise RT f r each plate, axial weld, and circumferential weld are listed in Attachment I PTS along with the applicable screening criterion. As indicated in Attachment 1, none of the reactor vessel beltline materials will exceed its respective screening criterion prior to the expiration date of the operating license. The RTPTS values are predicated on current neutron fluence data extrapolated for 40 years of operation with an 30% capacity factor, an 18-month fuel cycle, and current core loading ~ patterns.

We will submit updates to these projections whenever changes in core-loadings, surveillance measurements, or other information indicate a significant change in projected values.

Should you have any quest!ons, please do not hesitate to contact us.

Very truly yours, k

O

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3. A. Tiernan.

Vice President - Nu'c! car Energy 3AT/BSM/dmk Enclosure cc: D. A. Brune, Esq.

I

. 3. E. Silberg, Esq.

Mr. D. H. Jaffe, NRC

$7, hcg,",Fruoot,on3,3 Mr. T. Foley, NRC 1 ass (% 43, Etesa (PAna l I Foa (w, aggg)g)

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. Attachment 1 Page 1 of 2 Calvert Cliffs Unit 1.

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'10 CFR 50.61 WELD ID TYPE

• 32 EFPY RTPTS ( F)

PTS Screening Criteria ( F) 2-203-Axial 238 270

.l A,B,C I

3-203-Axial 223 270 A,B,C i

i 9-203 Circumferential 152

-300 t

10 CFR 50.61 4

j PLATE ID LOCATION

• 32 EFPY RTPTS ( F)

PTS Screening Criteria ( F)~

i i

D-7206-1 Intermediate 167 270 1

Shell Plate D-7206-2 Intermediate 133 270 Shell Plate D-7206-3 Intermediate 173 270 Shell Plate l

D-7207-1 Lower Shell 177 270 Plate l

j D-7207-2 Lower Shell 138 270 Plate i

D-7207-3 Lower Shell 126 270 l

Plate i

32 Effective Full Power Years (EFPY) corresponds to the expiration of the current operating license of 40 years with an 80% Capacity Factor.

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Attachment i Page'2 of 2 Calvert Cliffs Unit 2 i

10 CFR 50.61 WELD ID TYPE

• 32 EFPY RTPTS ( F)

PTS Screening Criteria ( F) 2-203-Axial 143 270 A,B,C 3-203--

Axial 151 270 A,B,C 9-203 Circumferential 141 300 10 CFR 50.61 PLATE ID LOCATION

• 32 EFPY RTPTS ( F)

. PTS Screening Criteria ( F)

D-8906-1 Intermediate 199 270 Shell Plate D-8906-2 Intermediate 157 270 Shell Plate J

D-8906-3 Intermediate 183 270 Shell Plate l

D-8907-1 Lower Shell 185 270 Plate D-8907-2 Lower Shell 196 270 Plate D-8907-3 Lower Shell 142 270 Plate 32 Effective Full Power Years (EFPY) corresponds to the expiration of the current operating license of 40 years with an 3096 Capacity Factor.

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