ML20039B294
| ML20039B294 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/15/1981 |
| From: | Trimble D ARKANSAS POWER & LIGHT CO. |
| To: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML20039B293 | List: |
| References | |
| 0CAN08106, CAN8106, NUDOCS 8112220498 | |
| Download: ML20039B294 (3) | |
Text
.
~'
Tr nc:". " C2IJ?.aLL octific.1 'J7
_'__,2 ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK. ARKANSAS 72203 (501) 371-4000 October 15, 1981 BCAN108106 Mr. K. V. Seyfrit, Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011
Subject:
Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Protection Factor Calculations for Emergency Control Center (File:
1510.4, 2-1510.4)
Gentlemen:
As committed to you in our letter of September 18, 1981, attached is a summary of the calculations performed to determine the protection factor of the Secondary Technical Support Center portion of the Emergency Control Center.
If you have any questions on the attached material, please contact us.
Very truly yours, bY David C. Trimble Manager, Licensing DCT:DEJ:sl f'
i Attachment i
8112220498 811015 PDR ADOCK 05000 Q F
MEMBEA MIDDLE SOUTH UTluTIES SYSTEM
\\
b ATTACHMENT
SUMMARY
Protection Factor Calculation For Emergency Offsite Facility Assumptions:
1.
Distance from plant = 0.65 miles 2.
Source Terms = DBA LOCA (FSAR)'
3.
Semi-infinite cloud surrounding EOF 4.
Gamma Energy = 0.7 MeV From the above, calculations were performed to determine the 30' day whole body dose to an unshielded individual at the EOF location.
The results indicated a dose of 4.84 Rems would be received.
A specific area within the EOF was analyzed to determine expected 30 day-WBD within it and the associated Protection Factor.
Location:
Technical Support Center (Room 259)
The EOF is comprised basically of four types of building material.
For the location analyzed, the fraction (%) of each of these materials separating the room from the cloud was determined. Table 1 below shows the results from the above location.
Table 1-Technical Support Center Material Reduction Factor
% Total Area Windows 1
4.2 l'11" Concrete 140 4.3 5" Concrete 3.9 31.7 5" Concrete +
4.8 59.5 5" Insul. Concrete
e.
Given the proportional areas of each material and the associated Reduction Factor, the inside dose may be calculated as:
4.84R
.063[4.84R] _.043[4.84R] _
1 140
.317[4.84R] _.595[4.84R]
- L 128 3.9 4.8 The Protection Factor is then calculated as:
4.84R
_g3 1.12R These calculations do not assume the presence of any internal walls, etc.
and are therefore conservative as they do not consider the associated Reduction Factors for these internal structures.
L