ML14184A451
| ML14184A451 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 06/27/1983 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Utley E Carolina Power & Light Co |
| References | |
| NUDOCS 8307270320 | |
| Download: ML14184A451 (3) | |
Text
DISTRIBUTION g)I 21 u
Docket File NRC PDR Docket No. 50-261 Local PDR ORB# 1 Reading D. Eisenhut Mr. E. E. Utley, Executive Vice OELD President E. Jordan Power Supply and Engineering G. Requa
& Construction C. Parrish Carolina Power and Light Company NSIC P. 0. Box 1551 J. Taylor Raleigh, North Carolina 27602 ACRS (10)
Dear Mr. Utley:
Your letter dated April 1, 1983 documented your Flux-Reduction Action Plan presented to our staff on March 11, 1983 and requested our re view of the achievability of your plan for the cycle 10 core reload schedule.
The objective of the NRC review is to determine the acceptability and achievability of the proposed schedule and methodologies to obtain the necessary pressure vessel flux reduction. The short term targets for the new thermal limits are 1.65 for the enthalpy rise factor FAH and 2.32 for the total peaking factor F0.
The sh6%tit m 019 is for Cycle 10 for H. 8. Robinson 2 has two essential elements:
(a)- the hot channel analysis portion of the existing LIB limiting transients for 2,300 K4T operation will have to be redone for the higher allowed FAH:and (b) the recalculation of the DNS limiting portions of the H. B.
Robinson safety limit curves will have to be redone.
However, the NRC SERs for the ENC IN8 correlation and XCOBRA-IIIC PwR model have not yet been written.
The new limits for F H and F necessitate reanalyses for the LOCA which will be carrieA out asgiming that (1) the steam generators will be replaced, (2) the reactor will be operating at full power, and (3) F and F -will be at 2.32 and 1.65 respectively. The ENC EXEM/PWR LOCA model W 11 be used.
Long term alternatives to be studied by CP&L for additional margin include statistical combination of uncertainties and part power operation.
8307270320 830627 PDR ADOCK 05000261 I
P PDR DFFICER SURNAME~
NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD CO PY USGPO: 1981-335-960
IUUN L7 984 Mr. E. E. Utley
-2 We believe that the schedule is acceptable and achievable provided that the proposed licensing actions are submitted on time and complete with regard to technical content.
Sincerely, Priginai u-6iIed byj Steven A. Varga, Chief Operating Reactors Branch No.1 Division of Licensing cc: See next page OFFICEO.R B.
SURNAME
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a 6/20/83 6/
DATE
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NRC FORM 318 (10-80) NRCM 0240 OFFICIAL R ECO RD COPY USGPO: 1981-335-960
E. U-iev C::rolina Power and Light Company cc: G. F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.
Washington, D. C. 20036 U. S. Nuclear Regulatory Commission Resident Inspector's Office H. B. Robinson Steam Electric Plant Route 5, Box 266-1A Hartsville, South Carolina 29550 James P. O'Reilly Regional Administrator -
Region II U. S. Nuclear Regulatory Commission 101 Marietta Street - Suite 3100 Atlanta, Georgia 30303