ML20116B177
| ML20116B177 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 04/22/1985 |
| From: | Denton R BALTIMORE GAS & ELECTRIC CO. |
| To: | John Miller Office of Nuclear Reactor Regulation |
| References | |
| NFM-85-154, NUDOCS 8504250100 | |
| Download: ML20116B177 (2) | |
Text
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BALTIMORE G AS AND ELECTRIC COMPANY P.O. B O X 147 5 B A LTIM O R E. M A R YL A N D 2120 3 C LVERT CL FFS NUCLEAR WER PL ANT
".USBY. M A RYL AN D 20657 April 22,1985 NFM-85-154 U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC 20555 ATTENTION: Mr. James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit No.1; Docket No. 50-317 Responses to Questions - Unit 1, Cycle 8 License Submittal
REFERENCE:
(1)
A.E. Lundvall, Jr., to J.R. Miller letter dated 2/22/85, Eighth Cycle License Application Gentlemen:
This letter responds to verbal questions received in the course of NRC review of the Calvert Cliffs Unit 1, Cycle 8 Reload License Spmittal, Reference 1. Specifically, the questions pertain to the reanalysis of the 0.1 ft Small Break Loss of Coolant Accident (SBLOCA) performed a part of the Unit 1 Cycle 8 reload evaluations. The questions and responses are provided in Attachment 1.
Should you have further questions regarding the license submittal, we will be pleased to discuss them with you.
-Since ely,
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l r J4-I{.E. Denton l
deneral Supervisor Training & TechnicalServices RED /JFW/jes Att:
cc: D.A. Brt v, Esq.
G.F. Tros 3 ridge, Esq.
D.H. Jatte, :!RC
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T. Foley, NRC V
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M T. Magette, DNR 8504250100 850422 PDR ADOCK 05000317 P
j ATTACHMENT 1 2
QUESTION:
Justify the 0.1 ft SBLOCA as the limiting break size with reduced High Pressure Safety Injection (HPSI) flow 2
RESPONSE
The 0.1 ft break size was originally shown to be the limiting SBLOCA in CENPD-137, Supplement 1, " Calculative Methods for the CE Small Break LOCA Evaluation Model", January 1977. Larger breaks result in greater depressurization of the primary coolant system and sufficient discharge of Safety Injection Tank water to maintain peag clad temperature below the limiting case. Breaks smaller than 0.1 ft result in little or no core uncovery. The reduction in HPSI flow does not change the limiting break size.
QUESTION:
Provide certification that the Chemical and Volume Control System (CVCS) components credited in the SBLOCA analysis are safety grade.
RESPONSE
The Q-List, " List of Safety Related Items, Calvert Cliffs Nuclear Power Plant" documents that all CVCS components required to provide coolant injection credited in SBLOCA analysis are safety related components.
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