ML022390518
| ML022390518 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 09/10/2002 |
| From: | Lyon C NRC/NRR/DLPM/LPD3 |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC MB6136, TAC MB6137 | |
| Download: ML022390518 (4) | |
Text
September 10, 2002 MEMORANDUM TO: Biweekly Notice Coordinator FROM: Carl F. Lyon, Project Manager, Section 2 /RA/
Project Directorate III Division of Licensing Project Management
SUBJECT:
REQUEST FOR PUBLICATION IN BIWEEKLY FR NOTICE -
NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING (TAC NOS. MB6136 AND MB6137)
Exelon Generation Company, LLC, Docket Nos. 50-254 and 50-265, Quad Cities Nuclear Power Station, Units 1 and 2, Rock Island County, Illinois Date of amendment request: August 22, 2002 Description of amendment request: The proposed change modifies the required surveillance interval for calibration of the trip units associated with the instrumentation channels of the Anticipated Transient Without Scram-Recirculation Pump Trip (ATWS-RPT) system from monthly to quarterly.
Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed TS [Technical Specification] change increases a STI [surveillance test interval] for ATWS-RPT System actuation instrumentation based on generic analyses completed by the Boiling Water Reactor Owners Group (BWROG). The NRC has reviewed and approved these generic analyses and has concurred with the BWROG that the proposed changes do not significantly affect the probability of failure or availability of the affected instrumentation systems. EGC [Exelon Generation Company, LLC] has determined these studies are applicable to QCNPS
[Quad Cities Nuclear Power Station], Units 1 and 2.
TS requirements that govern operability or routine testing of plant instruments are not assumed to be initiators of any analyzed event because these instruments are intended to prevent, detect, or mitigate accidents. Therefore, this change will not involve an increase in the probability of occurrence of an accident previously evaluated. Additionally, this change will not increase the consequences of an accident previously evaluated because the proposed change does not involve any physical changes to ATWS-RPT System components or the manner in which the ATWS-RPT System is operated. This change will not alter the operation of equipment assumed to be available for the mitigation of accidents or transients specified in the ATWS analysis contained in the QCNPS Updated Final Safety Analysis Report (UFSAR). As justified and approved in licensing topical reports endorsing extended AOTs [allowed out-of-service times] and STIs, the proposed change establishes or maintains adequate assurance that components are operable when necessary for the prevention or mitigation of accidents or transients, and that plant variables are maintained within limits necessary to satisfy the assumptions for initial conditions in the safety analyses. Furthermore, there will be no change in the types or significant increase in the amounts of any effluents released offsite. For these reasons, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated?
The proposed change does not involve any physical changes to the ATWS-RPT System or associated components, or the manner in which the ATWS-RPT System functions. Therefore, this change will not create the possibility of a new or different kind of accident from any accident previously evaluated. There is no change being made to the parameters within which the plant is operated. There are no setpoints at which protective or mitigative actions are initiated that are affected by the proposed change. This proposed change will not alter the manner in which equipment operation is initiated nor will the function demands on credited equipment be changed. The change in methods governing normal plant operation is consistent with the current ATWS analysis assumptions specified in the UFSAR. Therefore, this change will not create the possibility of a new or different kind of accident from any accident previously evaluated.
Does the proposed change involve a significant reduction in a margin of safety?
Margins of safety are established in the design of components, the configuration of components to meet certain performance parameters, and in the establishment of setpoints to initiate alarms or actions. The proposed change increases a STI for ATWS-RPT System actuation instrumentation based on generic analyses completed by the BWROG. The analyses determined that there is no significant change in the availability and/or reliability of ATWS-RPT instrumentation as a result of the proposed change in STI. The extended STI does not result in significant changes in the probability of ATWS-RPT instrument failure. Furthermore, the proposed change will not reduce the probability of test-induced ATWS-RPT transients and equipment failures. Therefore, it is concluded that the proposed change will not result in a
reduction in the margin of safety.
The NRC staff has reviewed the licensees analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the requested amendments involve no significant hazards consideration.
Attorney for licensee: Mr. Edward J. Cullen, Deputy General Counsel, Exelon BSC - Legal, 2301 Market Street, Philadelphia, PA 19101 NRC Section Chief: Anthony J. Mendiola
The NRC staff has reviewed the licensees analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the requested amendments involve no significant hazards consideration.
Attorney for licensee: Mr. Edward J. Cullen, Deputy General Counsel, Exelon BSC - Legal, 2301 Market Street, Philadelphia, PA 19101 NRC Section Chief: Anthony J. Mendiola DISTRIBUTION:
Non-Public PD3-2 r/f FLyon CRosenberg AMendiola Adams Accession Number: ML022390518 OFFICE PDIII-2/PM PDIII-2/LA PDIII-2/SC NAME FLyon CRosenberg AMendiola DATE 9/9/02 9/9/02 9/9/02 OFFICIAL RECORD COPY