ML20212L265
| ML20212L265 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 01/23/1987 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20212L267 | List: |
| References | |
| NUDOCS 8701290395 | |
| Download: ML20212L265 (4) | |
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7590-01
_ UNITED STATES NUCLEAR REGULATORY COMMISSION-ILLINOIS POWER COMPANY DOCKET NO. 50-461 NOTICE OF CONSIDERATION OF ISSUANCE AMENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION f
TheU.S.NuclearRegulatoryCommission(theCommission)isconsidering issuance of an amendment to Facility Operating License No. NPF-55 issued to Illinois Power Company (the licensee) for operation of the Clinton Power i
Station located in Harp Township Dewitt County, Illinois.
The proposed amendment will modify Section 3/4.7.2, " Control Room j
Ventilation System" of the Technical Specifications for the Clinton Power Station's Low Power License. The modification will change the acceptance criteria for the control room HVAC system's allowable flow rate from 62,500 cubic feet per minute (CFM) 110% to 64,000 CFM 10%. The current value of I
62,500 CFM 10%, which was placed in the Technical Specifications as a preliminary value, was based on calculated flow rates which are not achievable on both trains of the system. The initial calculation utilized estimated flow resistance values for system components (ctarcoal absorbers); testing of the system had not been completed prior to the issuance of the low power operating license. The proposed value of 64,000 CFM 110% is based on flow rates measured in the as-built a'nd tested configuration of both trains of the control room HVAC system. Although one train of the control room HVAC system meets the current Technical Specifications, this change is needed before the plant can achieve initial criticality, since both trains of the system must b
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. satisfy the operational conditions prescribed in the Technical Specifications for entry into this operating condition, f.e., criticality. The amendment is supported by an analysis prepared by the licensee which shows that the increase
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in the air flow rate does not have any adverse impact on system performance.
The licensee using the standards in 10 CFR 50.92 has made a determination that the proposed change does not involve a significant hazards consideration, j
This revision to the Technical Specifications is being made in response to the licensee's application for amendment, dated January 20, 1987.
Before issuance of the proposed license amendment, the Comission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations.
The Comission has made a proposed deterinination that the amendment request involves no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in j
accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated; (2) create the possibility of a new or different kind of accident from any 4
accident previously evaluated; or (3) involve a significant reduction in a margin of safety. The basis for a proposed finding based on the above three criteria is given below.
l 1.
The thyroid dose for control room operators resulting from the proposed increase in the control room HVAC flow rate has been recalculated. The proposed increase in the system flow rate results in a slight decrease in calculated thyroid dose to control room operators due to recirculating a higher percentage of control room air through the filter unit (charcoal absorbers).
3-Therefore, this proposed amendment does not involve a significant increase in the consequences of an accident previously evaluated. Since there is no change in equipment or procedures for this system this change does not involve a significant increase in the probability of an accident previously evaluated.
2.
Since there are no changes to plant equipment or plant procedures, except for procedure test acceptance criteria, the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
L Although the proposed amendment will result in an increase in the control rnen WAC system flow rate to 64,000 CFM, the initial control room design was for a two unit control room utilizing a recirculation flow rate of approximately 71,000 CFM. The increased flow rate will result in an overall decrease in thyroid dose and a slight decrease in chloride removal (approximately 2%) from the values described in the Final Safety Analysis Report. The slight decrease in chloride removal capability is still well within acceptable limits. There-l fore, this change does not involve a significant reduction in the margin of safety.
Based on the review to the three criteria given above, the Comission has made a proposed determination that the amendment request involves no significant hazards consideration.
The Commission has determined that failure to act in a timely way would result in a delay in achieving initial criticality, which in turn will result in a delay in achieving full power operations. Thus, the Commission does not have sufficient time to issue its usual 30-day notice of the proposad action for public coment.
4 If the proposed determination becomes final, an opportunity for a hearing will be published in the FEDERAL REGISTER at a later date and any hearing request will~not delay the effective date of the amendment.
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- .' i If the Comission decides in its final determination that the amendment.
does involve a significant hazards consideration, a notice of opportunity for a prior hearing will be published in the FEDERAL REGISTER and, if a hearing is granted, it will be held before any amendment is issued.
The Commission is seeking public comments on this proposed determination of no significant hazards consideration. Comments on the proposed determination may be telephoned to Walter R. Butler, Director, BWR Project Directorate No. 4, by coll 3ct call to 301-492-7538 or submitted in writing to the Rules and Procedures Branch, Division of Rules and Records, Office of l
Administration, U. S. Nuclear Regulatory Commission, Washington, D. C.
- 20555, and should cite the publication date and page number of the FEDERAL REGISTER notice. All coments received by February 11, 1987 will be considered in reaching a final determination. A copy of the application may be examined at the commission's Public Document Room,1717 H Street, NW, Washington, D. C.
and at the Vespasian Warner Public Library, 120 We' Johnson Street, Clinton, Illinois 61727, the Local Public Document Room.
Dated at Bethesda, Maryland, this 23rd day of January, 1967.
FOR THE NUCLEAR REGillATOP.Y COMMISSION Walter R. Butler, Director BWR Project Directorate No. 4 Divsion of BWR Licensing l
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