3F1085-13, Forwards Assessment of Crystal River 3 Reactor Coolant Leak Detection Sys, Action Item Labeled in 850201 Request for Exemption from 10CFR50,App A,Gdc 4 Re RCS Leakage Detection Sys Capability
| ML20134A004 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/29/1985 |
| From: | Westafer G FLORIDA POWER CORP. |
| To: | Harold Denton NRC OFFICE OF ADMINISTRATION (ADM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20134A007 | List: |
| References | |
| RTR-REGGD-01.045, RTR-REGGD-1.045 3F1085-13, NUDOCS 8511040033 | |
| Download: ML20134A004 (2) | |
Text
M*oic,S*
d ooOf JGo:e Florida Power CORPORAT4ON October 29, 1985 3F1085-13 Mr. Harold R. Denton Office of Nuclear Reactor Regulation Attn: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Transmittal of Report Related to Request for Exemption from a Portion of 10 CFR 50 Appendix A, General Design Criteria 4
Reference:
Florida Power Corporation (FPC) letter to NRC, Westafer to Denton, dated February 1, 1985 (3F0285-02), subject Request for Exemption from a Portion of 10 CFR 50, Appendix A, General Design Criteria 4 (GDC-4).
Dear Sir:
The reference letter requested an exemption from a portion of the GDC-4 requirements in order to utilize the Leak-Before-Break concept at Crystal River Unit 3 (CR-3) and presented a sequence of actions (tentative dates of reports) which would provide additional justifications for the reduction at CR-3 in the number of large bore hydraulic snubbers restraining the reactor coolant pumps.
The report enclosed with this letter is the FPC Action Item labeled in the Reference as RCS Leakage Detection System Capability.
The format of the report lists Regulatory Positions cont ained in Reg.
Guide 1.45 and describes the monitoring devices and accuracies used by FPC to detect primary system coolant leakage.
The report shows that CR-3's leak detection system follows the guidelines of Reg. Guide 1.45, except that the system is not totally seismically supported.
This report is the last FPC report pl anned in the sequence of Reference 1 prior to NRC approval of FPC's subject exemption request.
8511040033 851029 gDR ggl ADOCK 0500 2
G EN ERAL OFFICE 3201 Thirty-fourth Street South e P.O. Box 14042, St. Petersburg, Florida 33733 e 813-866-5151 g
October 29, 1985 3F1085-13 Page 2 A technical meeting has been arranged among representatives of NRC, FPC and B&W representatives on October 31, 1985 to discuss the status of NRC review to identify needs for additional information, if required.
This meeting date is consistent.with our continued need for informal input from NRC during November,1985 to permit procurement by FPC of an optimized snubber arrangement to replace the current design.
i Sincerely, 1
G. R. Westafer Manager, Nuclear Operations Licensing and Fuel Management
Enclosure:
Assessment of CR3 RC Leak Detection System File:
SP 83-133 Octcber 25, 1985 Westaf er(T01)C3-1 t
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