ML20041G428
| ML20041G428 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/15/1982 |
| From: | Mardis D FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.1.2, TASK-TM 3F-0382-11, 3F-382-11, NUDOCS 8203220267 | |
| Download: ML20041G428 (3) | |
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U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 NUREG-0737; Item II.E.1.2 Emergency Feedwater System (Additional Information)
Dear Mr. Stolz:
By letter dated February 9,1982, your staff requested additional information needed to continue your review of the proposed upgrade of the emergency feedwater (EFW) system at Crystal River Unit 3 (CR-3).
Florida Power Corporation (FPC) hereby provides responses to ycur questions as follows:
Question 1.
Provid
- up-to-date electrical schematic / elementary diagrams for:
a)
Emergency feedwater (EFW) automatic initiation circuits including that circuitry from the channel outputs (channel level relay contacts), through the actuation logic, to the final actuation (slave) relays.
b)
EFW pump control circuits for both motor and turbine drive pumps.
c)
EFW valve control circuits for all control / isolation valves in the EFW flow paths and valves in the steam supply lines to the turbine driven EFW pump.
Re,ponse 1.a) The electrical schematic / elementary diagrams that are presently bT & c) available were transmitted to you by letter dated August 11,1981, and appear in the system description under Appendix "A". The final electrical schematic / elementary diagrams for the EFW automatic initiation circuits, EFW pump control circuits, and EFW valve control circuits will be forwarded to you on or before August 1,1982.
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General Office 32o1 Tnirty-fourin o..... soutn. P O. Box 14042. St Petersburg. Flonda 33733 e 813-866-5151
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. Mr. John F. Stolz March 15,1982 Page 2 l
Question 2.
Describe the emergency feedwater flow rate (instrumentation) and the steam generator. level instrumentation at Crystal River Unit 3..
This description should include:
1 a)
Type and number of channels per steam generator including the range of each channel.
b)
The specific source (vital bus) from which each of these channels is powered.
c)
Capability for testing and calibration.
d)
The specific indication available in the control room for each channel.
Response 2.
The emergency feedwater flow rate instrumentation and steam generator level instrumentation at CR-3 is described in Section 3.4 of the system -
description transmitted to you by letter dated August II,1981.
a)
The type and number of channels, including the rar.ge of each l
channel is. included in Sections 3.4.4 and 3.4.5 and Appendix B.
Details of this instrumentation will be forwarded to you on or before August 1,1982.
b)
The power source vital busses are incic4ed in Figures 3.3-1, -2, and -3 of the above transmitted system description between pages 33 and 34.
c)
The capability for testing and calibration of the system is covered in Sections 3.4.9 and 4.2.
Further details of this capability will be forwarded to you on or before August 1,1982.
i d)
The engineering design for the specific indication available in the control room for each channel has_not reached a sufficient level of refinement where this input can be provided. This will be forwarded l
to you on or before August 1,1982.
Question 3.
Provide a Piping and Instrumentation Diagram (P&ID) of the Crystal River 3 EFW system showing the third EFW pump, if it has been determined that a third pump is necesary.
Response 3.
In regard to the P&lD for the EFW system with a third EFW pump, FPC advised you by letter dated November 30, 1981, that the addition of a third EFW pump was not deemed cost effective. Our present plans do not provide for implementation of a thrr e-pump system.
i 4
Mr. John F. Stolz March lj,1982 Page 3 To date, the specific details of the system are still being finalized and thus, comprehensive responses to your inquiry are not available.
Our present schedule still calls for installation of the Emergency Feedwater Initiation and Control System during the Spring I'/63 Refueling Outage.
If you have any further questions, please contact this office.
Very truly yours, ad h eb David G. Mardis Acting Manager Nuclear Licensing Enclosure RAW:mm i
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