ML20054D976
| ML20054D976 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/23/1982 |
| From: | Mardis D FLORIDA POWER CORP. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-SSINS-6820 3F-0382-14, 3F-382-14, IEB-80-11, NUDOCS 8204230559 | |
| Download: ML20054D976 (3) | |
Text
0
')l j
o, q ;. A.m 7
s sun o - <
.d
' "., e fg
- ,. - 'y 'lbI
- v..,y n_n ra M
Power C 0 m P C a a, s o se March 23,1982
- 3F-0382-14 File: 3-0-3-a-4 e
A N
Mr. 3. P. O'Reilly, Regional Administrator Of fice of Inspection & Enforcement U.S. Nuclear Regulatory Commission RECEIVED y
101 Marietta Street N.W., Suite 3100 ppb U $82b
--U Atlanta, GA 30303
{
NT $usEc$**
Subject:
Crystal River Unit 3 Tec
//
Docket No. 50-302 g
Operating License No. DPR-72 4
IE Bulletin 80-11 Masonry Walt Design
Dear Mr. O'Reilly:
Florida Power Corporation (FPC) responded to IE Bulletin 80-11 by letter dated July 7,1980. We have subsequently determined that our response did not include the emergency feedwater (EFW) system as we did not consider it a safety-related system at that time. Since the EFW system is presently considered safety-related, FPC's response to IE Bulletin 80-11 is hereby amended to reflect the following.
Two areas exist where a collapsed concrete block wall could impact components related to the EFW system. The two areas are the Motor Control Center TBMCC-3A, located on the 119' elevation of the Turbine Building which supplies power for EFV-3 and 7 motor operators (Bulletin response item I number 1.2.a) and the 8" suction line from the condenser hotwell to the EFW pumps, located in a trench below the turbine basement floor (Bulletin response item I number 1.2.b).
FPC will review and evaluate the areas in question in compliance with item 2. We will make your of fice aware of the results as soon as they become available. We anticipate the results on or before April 15, 1982. For the present, FPC does not consider either of these areas in questions to be a problem for the following reasons:
1.
EFV-3 and 7 are normally-open valves and are the suction and discharge isolation valves for the motor-driven pump, EFP-1. Loss of power to these valves would not change their position. The valves can be manually operated, if required. Also, the redundant,100% capacity, steam-driven pump is available for heat removal.
8204230 5 M sy General Office 201 Thirty-fourin street souin. P O. Box 14042. st Petersburg. Florca 33733 813-866-5151 hf i
i Mr. 3. P. O'Reilly March 23,1982 Page 2 2.
The 8" suction line is for the backup feedwater source and would not normally be used. The line is located in a trench which is covered with a 1/4" checker plate.
The chances of damage affecting the operability of this line due to a falling block wall are minimum.
Should you have any questions or comments, please contact us.
Very truly yours, i
&&0 mA David G. Mardis Acting Manager Nuclear Licensing KFP:mm cc:
Mr. Richard DeYoung, Director.
[
Office of Inspection & Enforcement Division of Reactor Operations inspection U.S. Nuclear Regulatory Commission Washington, D.C. 20555 t
?
l i
i f
. STATE OF FLORIDA COUNTY OF PINELLAS D. G. Mardis states that he is the Acting Manager, Nuclear Licensing, of Florida Power Corporation; that he is authorized on the part of.said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and.
matters set forth therein are true and correct to the best of his knowledge, information, and belief.
I ob "D. G. Mardik Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 23rd day of March,1982.
f Not9 y Public Notary Public, State of Florida at Large,
.My Commission Expires: May 29,198tf t
x
-