ML18018A547
| ML18018A547 | |
| Person / Time | |
|---|---|
| Site: | Harris |
| Issue date: | 05/18/1983 |
| From: | Mcduffie M CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| LAP-83-175, NUDOCS 8305200384 | |
| Download: ML18018A547 (8) | |
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- CXQE, Carolina Power & Light Company MAY 18 1S83 SERIAL:
LAP-83-175 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS.
1 AND 2 DOCKET NOS.
50-400 AND 50-401 DRAFT SAFETY EVALUATION REPORT RESPONSES MATERIALS ENGINEERING BRANCH
Dear Mr. Denton:
Carolina Power 5 Light Company (CPKL) hereby transmits one original and forty copies of the responses to the Shearon Harris Nuclear Power Plant Draft Safety Evaluation Report (DSER)
CPAL Open Item Nos.
32 and 33.
Carolina Power 4 Light Company will be providing responses to other Open Items in the DSER shortly.
Yours very truly, PS/cfr (6845PSA)
Attachment M. A. McDuffie Senior Vice President Engineering
& Construction Cct Mr. N. Prasad Kadambi (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Mr. J.
P. O'Reilly (NRC-RII)
Mr. Barry J. Elliot (NRC-MTEB)
Mr. Travis Payne (KUDZU)
Mr. Daniel F.
Read (CHANGE/ELP)
Chapel Hill Public Library Wake County Public Library Mr. Wells Eddleman Dr. Phyllis Lotchin Mr. John D. Runkle Dr. Richard D. Wilson Mr. G.
O. Bright (ASLB)
Dr. J.
H. Carpenter (ASLB)
Mr. J. L. Kelley (ASLB) 8305200384 830Sf8 PDR ADOCK 05000400 E
PDR 411 Fayetteville Street o P. O. Box 1551
~ Raleigh, N. C. 27602
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SHEARON HARRIS NUCLEAR POWER PLANT DRAFT SAFETY EVALUATION REPORT (DSER) 0 en Item 32 (DSER Sections 4.2.1.
1 and 4.2.3.
1 a es 4-4 4-16 and 4-28)
Resolve the use of irradiation-strengthened Zircaloy yield strengths.
~Res ense The fact that credit is taken for irradiation strengthening for the Zircaloy clad yield strength was documented as part of the WCAP-9500, "Reference Core Report 17x17 Optimized Fuel Assembly," and acknowledged in the NRC's Safety Evaluation dated May 1981 (page 7).
In support of this Westinghouse provided supplementary information to the staff<") that demonstrated excellent agreement between experimental
- data, BMI-NUREG-1948, and the best estimate curves described in the equation in the Westinghouse Materials Design Manual, WCAP-9179, Rev.
1.
(1)Letter from E. P.
Rahe to C. 0. Thomas, NS-EPR-2687, dated November 30, 1982.
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SHEARON HARRIS NUCLEAR POWER PLANT DRAFT SAFETY EVALUATIONREPORT (DSER) 0 en Item 33 (DSER Section 4.2.3.2 a es 4-21 4-22 and 4-29)
Confirm that the predicted cladding collapse time exceeds the expected lifetime of the fuel.
Response
The Shearon Harris fuel is designed and operated go that clad flattening vill not occur as predicted by the Westinghouse model.~
The predicted cladding collapse time for the fuel is )40 000 EFPH.
The expected lifetime of the fuel is (40 000 EFPH.
- George, R.
Ae F et. ale F "Revised Clad Flattening Model", WCAP-8381, July 1974.