ML19340B184
| ML19340B184 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/16/1980 |
| From: | Richard Bright FLORIDA POWER CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| 3--3-E, 3-0-3-E, NUDOCS 8010210631 | |
| Download: ML19340B184 (2) | |
Text
_
!y 1
M P..o. w.. e..r, October 16, 1980 File:
3-0-3-e f
Mr. Darrell G. Eisenhut Director Division of Licensing Office of Nuclear-Reactor Regulation U.~ S. Nuclear Regulatory Commission Washington, DC 20555 l-
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License NO. DPR-72
Dear Mr. Eisenhut:
Your letter of June 11, 1980, to "All Operating PWRs", re-quested submittal of Technical Specifications regarding redun-l_
dancy in ' systems ucilized ' to remove decay heat.
Florida Power i
understands the basis for your general concerns in this area.
However, we are not in complete agreement with the standard i
Technical Specifications provided.
FPC hereby requests fur-i-
ther information before it can adequately address specific l
constraints on plant operation thich would be considered necessary and sufficient to achieve the desired level of safe-
. ty. - -It -is, therefore, requested :that the staff provide the
[
following information:
a.
The= basis for linking Mode'4 to Mode 5 in draft Spe-ci fication. 3.4.1.3.
PCl considers the ability to makeup.to the RCS, in Mode 5, to be a sufficient re-dundant means of removing decay heat.
2 b.
The l basis of using 23 feet as definition of " low
- water level".
FPC is -' unaware of any thermal-hydraulic basis for the 23 feet.
[
t 8010210434 7
L I
General. Office 320s inrtyacurtn.sireet soutn. P o ecx 14042 St Petersou g. F or.ca 33733 813--866 5151 r
7-
!-/-
i October 16, 1980 l
Mr. Darrell G. Eisenhut_
Page Two i
i :.
l c.-
Definition of "...immediately. initiate corrective action...".
FPC does not consider anything more
~ than expeditious repair.of' inoperable components. to l
be necessary..FPC'would not. support such ' actions as repressurizing to allow operation of reactor coolant pumps.
FPC is especially concerned with (a)', above.
The ability to meet boil-off is as acceptable -in the vessel as it is in the spent ~ fuel pool. ' We strongly urge consideration-of this as a third alternative to the systems identified in your letter.
FPC anticipates. submitting a Technical Specification Change Requesti on. this' subjact' within 60 days of receipt of your written response to this inquiry.
Please contact this office if further clarification is required.
L
- Very truly yours,.
FLORIDA' POWER CORPORATION
(
Ronald M.' Bright Acting Manager l
Nuclear Support Services RMBekcW01(D8-3) i i
4 a
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