ML20203G306
| ML20203G306 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/25/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20203G302 | List: |
| References | |
| NUDOCS 8608010068 | |
| Download: ML20203G306 (2) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 45 TO FACILITY OPERATING LICENSE N0. NPF-11 COMMONWEALTH EDIS0N COMPANY LA SALLE COUNTY STATION, UNIT 1 DOCKET NO. 50-373
1.0 INTRODUCTION
By letter dated June 10, 1986, Comonwealth Edison (the licensee) requested an amendment to the Technical Specifications for Facility Operating License NPF-11 for la Salle County Station Unit 1.
The amendment reflects the cor-rections to the Rod Block Monitor setpoints and a typographical error on Index page VI.
2.0 EVALUATION The NRC recently approved Amendment 40 dated May 9, 1986, to the Technical Specifications of La Salle Unit I relating to the Reload for Cycle 2.
It has subsequently been discovered by Comonwealth Edison (the licensee), and reported in a proposed amendment dated June 10, 1986, that the submittal for that Cycle 2 amendment did not include a necessary change to Table 3.3.6-2 for the Rod Block Monitor setpoints for single and two recircula-tion loop operation. This change is required by the selection of the rod block setpoint of 107 percent used in the rod withdrawal error at power analysis performed for the reload. The use of a 107 percent setpoint is within a normally expected range so that the requested change to Table 3.3.6-2 is acceptable.
Also in the June 10th submittal, it was indicated that an administrative error relating to the inclusion of a thermal-hydraulic stability section in the Index to the Technical Specifications should be corrected. This change does not affect plant operation and is also acceptable. The page number for Figure 3.4.1.1-1 was previously corrected by [[letter::05000373/LER-1986-015-02, :on 860425,full Scram Received During Performance of APRM Rod Block & Scram Function.Caused by Failure of Right Side Switches of Scram Contactor.Switches Realigned|letter dated May 19, 1986]].
3.0 ENVIRONMENTAL CONSIDERATION
i This amendment involves a change in the use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes in surveillance requirements and a typographical error. The staff has deter-mined that this amendment involves 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 cumula-i tive occupational radiation exposure. The Comission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public coment on such finding. Accord-1 ingly, this amendment meets the elioibility criteria for categorical exclusion set forth in 10 CFR 51.22lc)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
8608010068 860725 PDR ADOCK 05000373 P
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4.0 CONCLUSION
The Commission made a proposed determination that the amendment involves no significant hazards consideration which was published in the Federal Register (51 FR 23173) on June 25, 1986. No public comments were received, and the state of Illinois did not have any comments.
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
H. Richings, NRR l
Dated:
July 25,1986 4
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