ML20205D417
| ML20205D417 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/26/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20205D413 | List: |
| References | |
| NUDOCS 9904020200 | |
| Download: ML20205D417 (2) | |
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NUCLEAR REGULATORY. COMMISSION o
WASHINGTON, D.C. enmaa anni GAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.186 TO FACILITY OPERATING LICENSE NO. DPR-29 AND AMENDMENT NO.183 TO FACILITY OPERATING LICENSE NO. DPR-30 COMMONWEALTH EDISON COMPANY 6tiQ MIDAMERICAN ENERGY COMPANY
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QUAD CITIES NUCLEAR POWER STATION. UNITS 1 AND 2 DOCKET NOS 50-254 AND 50-265
1.0 INTRODUCTION
The Safe Shutdown Makeup Pump (SSMP) is an alteW.e system to the Reactor Core Isolation Cooling (RCIC) system pursuant to 10 CFR Part 50, Appendix R, paragraph lli.G.3. Both the SSMP and the RCIC systems are used to provide reactor makeup water during post-fire safe shutdown activities. However, the Quad Cities Technical Specifications (TSs) presently have a 67 day Allowed Outage Time (AOT) for the SSMP system and 14 day AOT for the RCIC system. This ameridment changes TS Section 3/4.8.J and Bases Section 3.8.J for the SSMP AOT from 67 days to 14 days to make it consistent with the RCIC AOT in order to assure equivalent pump availability.
2.0 EVALUATION The Safe Shutdown Analysis (SSA) for the Quad Cities facility utilizes two methods, either the use of the SSMP system or the RCIC system to provide make up inventory to the reactor depending on the fire area involved. The SSMP system consists of one pump which serves both Units 1 and 2. The Updated Final Safety Analysis Report (UFSAR) Section 5.4.6.5.1 states that the SSMP system is to provide cooling water to Units 1 and 2 reactor core in the event that the reactor becomes isolated from the main condenser simultaneously with a loss of the feedwater system. To achieve this purpose, the SSMP system was designed with the same capacity as tha RCIC system. UFSAR Section 5.4.6.5.2 further states that the SSMP system was installed as a common backup to Units 1 and 2 RCIC systems to satisfy the requirements of 10 CFR Part 50, Appendix R, Section Ill.G, " Fire Protection of Safe Shutdown Capability."
Although the TSs for the RCIC system, 3/4.5.D, " Reactor Core Isolation Cooling," states that the RCIC system when 1NOPERABLE must be restored to OPERABLE status within 14 days, TS Section 3/4.8.J, " Safe Shutdown Mskeup Pump," states that the SSMP system when INOPERABLE must be restored to OPERABLE status withh. 7 days. On July 2,1998, the k O M 54 A
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l NRC staff !ssued inspection report 50-254/98011; 50-265/98011 which stated that, "Since the SSMP and RCIC had the same post-fire shutdown functionality goals to provide reactor water makeup, it appeared that it was the NRC's expectation that the SSMP would have a 14 day AOT in its TS." Neither the SSMP nor RCIC has an Emergency Core Cooling System (ECCS) function. They are primarily used in the event the core is isolated due to loss of feedwater. The 4
Quad Cities SSA, depending on the location of the fire in the plant, relys on either the RCiC or the SSMP to establish core cooling during the initial phase of maintaining hot shutdown.
i On May 13,1998, the NRC staff met with the licensee where the licensee committed to change the SSMP AOT to 14 days. This change meets that commitment and should ensure that the non-unit specific post-fire safe shutdown equipment functions will be maintained OPERABLE under all unit shutdown and operating conditions. Therefore, to provide consistency regarding the AOT times for these systems, changing the SSMP AOT from 67 days to 14 days is conservative and appropriate. This change is acceptable.
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3.0 STATE CONSULTATION
in accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuance of the amendments. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to the installation or uso of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (64 FR 2246). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonabl; assurance that the health and safety of the public will not be endangered by opa ation in the proposed menner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amandments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor. Robert M. Pulsifer Date: March 26, 1999
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