ML20028B864
| ML20028B864 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 11/30/1982 |
| From: | Wuller G ILLINOIS POWER CO. |
| To: | Thomas C Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0853, RTR-NUREG-853 U-0579, U-579, NUDOCS 8212070125 | |
| Download: ML20028B864 (2) | |
Text
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e ILLINDIS POWER 00MPANY
- U-0579 yfy L30_g2(ty_3nys 500 SOUTH 27TH STREET, DECATUR, ILLINOIS 62525 November 30, 1982 Mr. Cecil O. Thomas, Chief Standardization & Special Projects Branch Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatocy Commission Washington, D. C.
20555
References:
(1) IP Letter U-0544, from G. E. Wuller to C. O. Thomas; dated 9/16/82 (2) Notes of Meeting between IP and NRC regarding CPS Outstanding Issues (IP letter Y-8671) dated 10/27/82.
Dear Mr. Thomas:
Clinton Power Station Unit 1 Docket No. 50-461 Containment Bypass Leakage Fraction Reference letter #1 transmitted the Illinois Power Company (IP) position on Outstanding Issue 10(e) of the Clinton Power Station Safety Evaluation Report (SER) (NUREG-0853, Sections 6.4 and 15.3) regarding the acceptability of the proposed 12%
containment bypass leakage fraction.
Reference #2 concerns a meeting held at the NB:'s Bethesda Offices on October 27, 1982 between representatives of IP and the NRC to discuss CPS-SER Outstanding Issues.
Jack Read, NRC AEB Reviewer for CPS, attendcd this meeting to discuss this issue.
Information provided by Mr. Read indicated that the proposed 12% bypass leakage resulted in offsite doses to the thyroid of 308 Rem which is in excess of the 300 Rem 10CFR100 requirement under post-accident conditions.
This result was obtained from NRC's " TACT-3" Code used to calculate offsite doses under accident conditions at CPS.
Based upon the above and additional information discussed at this meeting, IP proposes that an acceptable containment bypass leakage fraction would be 8% for CPS.
A bypass fraction of 8%
results in post-accident doses as follows:
r212070125 82113o I
{DRADOCK 05000461 MO PDR
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i U-0579 L30-82(ll-30)6 November 30, 1982 Page 2 Control Room Doses Evaluated Doses 10CFR50 Limits t
Thyroid Inhalation Dose (Iodine) 3.3 Rem 30 Rem 1
Whole Body Dose ()()
Skin Dose (f )
27.3 Rem 75 Rem As can be seen, all of these doses are significantly less than the 10CFR50 limits.
In addition, the post-accident offsite dose to the thyroid is approximately 240 Rem.
This is also significantly less than the 300 Rem limit of 10CFR100.
Technical justification for the proposed increase in the 1
bypass leakage fraction, to greater than 4%, was provided in reference letter #1.
The offsite doses have been shown to be in conformance with the 10CFR100 requirements.
It is IP's belief that this letter provides adequate information to justify use of an 8% bypass leakage fraction and thus close-out Outstanding Issue 10(e) in the next supplemental SER.
IP commits to changing our draft Technical Specifications and to revising Chapter 15 of the FSAR to reflect the new calculated post-accident doses.
Should you have any questions, please contact me at your earliest convenience.
Sincerely, E%da G. E. Wuller Supervisor - Licensing l
Nuclear Station Engineering TLR/jmm cc:
Mr. J. H. Williams, NRC Clinton Project Manager Mr. H. H. Livermore, NRC Resident Inspector l
Mr. Jack Read, NRC Accident Evaluation Branch l
Illinois Dept. of Nuclear Safety l
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