ML17199F668
| ML17199F668 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, 05000000 |
| Issue date: | 02/28/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17199F665 | List: |
| References | |
| NUDOCS 8603110168 | |
| Download: ML17199F668 (2) | |
Text
..
.r
. ~ *
....... _,,.~., -:... -.*. -i: *~.,
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO RADIOLOGICAL CONSEQUENCES OF A LOCA WHILE PURGING CONTAINMENT COMMONWEALTH EDISON COMPANY IOWA-ILLINOIS r,As AND ELECTRIC COMPANY OUAO CITIES NUCLEAR POWER STATION UNITS 1 AND 2 DOCKET NOS. 50-254/265
1.0 INTRODUCTION
The staff has reviewed the radiological consequences of a hypothetical LOCA while purging the containment at power for Quad Cities Units 1 and
- 2.
This evaluation was conducted under Multi-Plant Issue B-24 and in accordance with the guidance of Branch Technical Position CSB 6-4, Standard Review Plan Sections 6.2.4 and 15.6.5 and Requlatory Guide 1.3.
2.0 EVALUATION Our evaluation is based on the release of 660 pounds mass (lbm) of steam prior to the post-LOCA closure of the purge valves at the maximum Technical Specification primary coolant concentration of 5 uCi/gm, dose equivalent I-131. It was assumed that the containment isolation would be achieved before the onset of fuel failure resulting from the accident. The five percent X/Q values at the Exclusionar_v
- Area Boundary (EA8) and the Low Population Zone (LPZ) boundary consistent with a ground level release were used in the dose calculations. A list of apolicable assumptions is given in Table 1.
I The staff estimates that the steam released through the purge line
. would result in an incremental dose of 0.31 Rem to the thyroid at the EAB and 0.02 Rem to the thyroid at the LPZ boundary.
These doses when added to the staff Safety Evaluation Report LOCA doses (See Table 2) of 150 Rem to the thyroid at the EAB and 108 Rem to the thvroid at the LPZ, meet the applic~ble guidelines of 10 CFR Part 100.
3.0 CONCLUSION
We conclude that the radiological consequences of a LOCA during purging at Quad Cities Units 1 and 2 meet the applicable guidelines of 10 CFR Part 100, and are therefore acceptable.
Principal Contributors:
K. Dempsey Dated: February 28, 1986
....v....
.- Quad Cities, Units 1/2 TABLE 1 ASSUMPTIONS USED TO EVALUATE THE CONTAINMENT PURGE CONTRIBUTION TO THE LOCA DOSE -
(
)
3
-4 X/Q value 0-2 hour, EAB, ground level release, sec/m3 4.0 x 10_5 (0-8 hour, LPZ, ground level release), sec/m 2.3 x 10 Purge valve closure time, sec 5
Amount of steam released through the purge valves prior to 660 post-LOCA closure, lbm Maximum technical specification primary coolant limit, 5
dose-equivalent 1-131,,uCi/gm TABLE 2 RADIOLOGICAL CONSEQUENCES
.. THYROID DOSES Containment purge contribution SER LOCA dose Effective LOCA dose NOTES:
EAB, 0-2 HOUR LPZ, 30 DAYS 0.31 Rem 150 Rem 150 Rem 0.02 Rem 108 Rem 108 Rem
- 2. The whole body doses from the containment purge contribution are not listed because they would be negligible when compared to the guideline values.