ML20077F838
| ML20077F838 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/28/1983 |
| From: | Westafer G FLORIDA POWER & LIGHT CO., FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20077F840 | List: |
| References | |
| 3F-0783-25, 3F-783-25, 83028, GL-81-21, NUDOCS 8308030081 | |
| Download: ML20077F838 (2) | |
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....... e.... Pow r July 28, 1983 3F-0783-25 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Rerctors Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Cry,tal River Unit 3 Docket No. 50-302 Operating License DPR-72 Generic Letter No. 81 Natural Circulation Cooldown
Dear Sir:
Florida Pcwer Corporation has received your request for additional informatio:1 dated May 20, 1983, on the above subject.
The responses to your questions are given below.
Question 1:
Provide a description of your natural circulation cool-down procedure.
Response 1:
Abnormal Procedure AP -530,
" Natural Ci rcul a ti on," is attached.
Question 2a:
Demonstrate, by analysis or otherwise, that use of pro-cedure will not result in upper head voiding.
Response 2a:
It can not be demonstrated that the use of this procedure will not result in upper head voiding. If voiding should occur, there is no way to predict whether it will happen in the upper head or in the top of the hot legs.
Question 2b:
Demonstrate, by analysis or otherwise, that if voiding occurs, your procedures will prevent voiding in the hot legs, and that if voiding in the hot legs did occur, your procedures provide adequate guidance for managing cool-down with interrupted natural circulation.
8308030081 830728 i
PDR ADOCK 05000302 I
\\
P PDR General Office 3201 Thrty fourtn street soutn. P.O. Box 14042, st. Petersburg. Fiorda 33733 e 813-866-5151
3F-0783-25 July 28, 1983 Page 2 Response 2b:
As stated in Response 2a, it cannot be demonstrated that the use of this procedure will not result in voiding in a specific location in the Reactor Coclant System.
If voiding does occur in the hot legs, the procedure provides adequate guidance for managing a cooldown with interrupted natural circulation.
Question 3:
Provide an analysis that shows you have sufficient con-densate supply to support a conservative estimate of the time to reach the Decay Heat Removal System entry conditions.
Response 3:
As discussed in Response 1, the symptom-oriented emer-gency operating procedures give direction for eliminating any voids should they form. Should the supply of conden-sate be exhausted prior to reaching the Decay Heat Removal System entry conditions, a symptom will occur which will be handled by another emergency operating procedure, i.e., the loss of cooling will result in loss of subcooling margin which will result in the use of the HPI once through mode of cooling.
Sincerely, l
lg I
/ /
/
G. R. Westafer Manager Nuclear Licensing and Fuel Management Attachments Bright (T01)C4-3 cc: Mr. J. P. O'Reilly Regional Administrator Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street NW Suite 3100 Atlanta, GA 30303
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