ML20129E172
| ML20129E172 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/01/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20129E111 | List: |
| References | |
| NUDOCS 8507160749 | |
| Download: ML20129E172 (2) | |
Text
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ENCLOSURE 2
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING THE RADIOLOGICAL CONSEQUENCES OF A LOCA WHILE PURGING CONTAINMENT POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 The staff has reviewed the radiological consequences of a hypothetical LOCA while purging the containment at power for Fitzpatrick. This evaluation was conducted under fluiti-Plant Issue B-24 and in accordance
' ith the guidance of Branch Technical Position CSB 6-4, Standard Review w
Plan Sections 6.2.4 and 15.6.5 and Regulatory Guide 1.3.
Our evaluation is based on the release of 5000 pounds nass (lbm) of steam prior to the post-LOCA closure of the purge valves at the maximum Technical Specification prinary coolant concentration of 31 pCi/gm, dose equivalent I-131.
It was assumed that the containment isolatien would be achieved before the onset of fuel failure resulting from the accident. The worst 0.5% probahility directionally dependent case X/Q values consistent with ground level releases were used in the dose calculations. A list of applicable assumptions is given in Table 1*
8507160749 850701 PDR ADOCK 05000333 P
PDR The staff estinates that the steam released through the purge line would result in an incremental cose of 18 Rem to the thyroid at the Exclusion Area Boundary (EAB) ano 0.5 Ren to the thyroid at the Low Population Zone Boundary (LPZ). Thece doses when added to the staff Safety Evaluation Report LOCA doses (See Table 2) of 36 Rem to the thyroid at the EAB and 60 Rem to the thyroid at the LPZ, meet the applicable guidelines of 10 CFR Part 100. We conclude, therefore, that the radiological consequences of a LOCA during purging at the Fitzpatrick wmild b meantv21R-
C TABLE 1 ASSUMPTIONS USED TO EVALUATE THE CONTAINMENT PURGE CONTRIBUTION TO THE LOCA DOSE 3
X/0 value (0-2 hour, EAB, ground level release), sec/m 5.0x10-f 3
(0-8 hour, LPZ, grcund level release), sec/m 1.5 x 10-Purge valve closure time, sec 4 10 Amount of steam released through the purge valves prior to 5000 post-LOCA closure, lbm Maximum technical specification primary coolant limit, 31 dose-equivalent I-131,jaci/gm TABLE 2 RADIOLOGICAL CONSECUENCES THYROID DOSES EAB, 0-2 HOUR LPZ, 30 DAYS Containment purge contribution 18 Rem 0.5 Rem SER LOCA dose 36 Rem 60 Ren Effective LOCA dose 54 Rem 61 Rem NOTES:
1.
The X/Q values and the SER LOCA doses were taken from the NRC Plant Data File, updated 5/12/83.
2.
The whole body doses are not listed because they would be negligible when compared to the guideline values.
Principal Contributor:
K. Dempsey, AEB Dated: July 1, 1985
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