ML20151X632
| ML20151X632 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 04/22/1988 |
| From: | Johnson I COMMONWEALTH EDISON CO. |
| To: | Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 4510K, NUDOCS 8805040206 | |
| Download: ML20151X632 (12) | |
Text
{{#Wiki_filter:* Commonwea!b Edison One First National PLua, CNeago, IEnois Address Reply to: PW OHce Box 767 ~- CNcago,llEnois 60690 0767 ptIC911Y E00 TING QO7LL UL _41 --- April 22, 1988 y-a-- &+l Tpyrf iO / Mr. A. Bert Davis Regional Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Quad Cities Station Units 1 and 2 Transmittal of Information Pertaining to LER 87-023-Control Room Habitability NRC Docket Nos. 50-254 and 50-265
Dear Mr. Davis:
In a response to a request made by C. Gill of your staff, attached please find a copy of a safety significance evaluation performed by NUS Corporation. This evaluation was performed at the request of Commonwealth Edison in response to the above ieferenced LER. The evaluation was performed in order to determine if the Control Room Operator Dose would have been below the General Design Criterion (GDC) 19 limit had a Design Basis Accident (DBA) occurred when the Standby Gas Treatment System (S3GTS) efficiency was lower than that used in previous radiological analyses. The radiological analyses were based on a 99% SBGTS charcoal efficiency whereas the existing Quad Cities Technical Specifications allow the SBGTS efficiency to be 90%. Quad Cities Station personnel reviewed previous charcoal efficiency test results which showed that the efficiency was generally above 99%. However, at one time the test results showed a. efficiency of 92.871%. The safety significance evaluation determined what the effect would be if a DBA had occurred at the time that the charcoal efficiency was at this level. The analysis performed used a containment leakage rate of 1% per day of which 0.15% per day leakage is allowed through the Main Steam Line Isolation Valves (MSIV). Plant personnel have reviewed the results of past containment leak rate tests and have determined that the highest leakage rate as determined from the previous outage was 0.45% per day of which 0.062% per day leakage occurred via the MSIVs. The 30-day control room thyroid dose (had a DBA occurred at this time) would have been 16.3 rem using the actual containment leakage rates and the lower SBGTS efficiency (91.871% was conservatively used in this analysis to allor-for a 1% bypass penetration of the charcoal trays). \\ /} g/ k R g S Y.h ,CY \\ 8805040206 080422 PDR ADOCK 05000254 P PDR
A.B. Davis April 22, 1988 A second, and even more conservative calculation was done to verify that degradation of the leak tightness of the containment, between tests, would not have resulted in doses above the GDC limit. The analysis was also performed using a margin of 0.25% per day which was added to the actual containment leakage rate. This margin was utilized since it represents the same margin as presently allcwed by the vuu; 04*ies Technical Specifications when performing periodic testing. The acceptanco criteria in the Technical Specification is 75% of tha leck rate or 0.75% per day. With a margin of 0.25% per day (0.70% per day total leak rate of which 31.5 SCFH at 24 psig leaks through the MSIVs), the control room 30-day thyroid dose is still below the GDC-19 limit. In this case, the value calculated was 25.3 rem. The methodology employed in the safety significance evaluation was presented to Mr. C. Gill in an April 12, 1988 conference call. Attached for the independent review of your staff, is a copy of the two calculations that were performed as well as curves which show operator doses as a function of SBGTS efficiency. In consideration of the actual containment leakage rate, the control room operator doses would not have exceeded the GDC-19 limits had a design basis accident occurred when the SBGTS efficiency was 92.871%. Moreover, when an additional cafoty factor is included in the calculation for reasons of conservatism, the conclusions remain unchanged. Please direct any questions you r ay have regarding this matter to this office. Very truly yours, /t I. M. Johns Nuclear Licensing Administrator la cc: Quad Cities Resident Inspector (w/o Att.) 451dK
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