ML20074A949
| ML20074A949 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/05/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20074A948 | List: |
| References | |
| NUDOCS 8305170023 | |
| Download: ML20074A949 (2) | |
Text
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UNITED 3TATEs y h.,- 4 e NUCLEAR REGULATORY COMMISSION
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SA:ETY EVALUATION'BY THE OFFICE OF NUCLEAR ~ REACTOR REGULATION '
IN RELATED TO AW.ENDMENT'NO.
TO FACILITY OPERATING LICENSE NO. DPR-75 PUklIC. SERVICE ELECfRIC AND. GAS COMPANY,
. PHILADELPHIA ELECTRIC COMPANY, DELMARVA POWER AND LIGHT COMPANY, AND ATLANTIC CITY ELECTRIC COMPANY SALEM NUCLdAR GhNERATING STATION. UNIT NO. 2 DOCKET NO. 50-3*.i Ir.:r:duc tion In a letter da'ted January 31, 1983, Public Service Electric and Gas Company submitted the results of a Reload Safety Evaluation (RSE) and a request for amendment to the Salem Unit 2 Technical Specifications. The Cycle 2 RSE was cer'ermed by Westinghouse using the methodology described in WCAP 9272.
The evaluation showed the need for cha.nges to the Fxy and rod insertion limit Technical 5:ecifications.
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Discussier A change to the Technical Specifications on F was requested to remove the cycle dependent values of F., as a function of core 3eight and provide these F,l,l, values x
by means of a Peaking factor Limit Report.
It is anticipated that F wi chan;e frn. cycle to cycle and this change wculd elir.nate the necesI5ty of making a Technical Specification change for each reload. A similar change has been approved on other plants.
A Radial Peaking Factor Limit Report was sub-mitted with the January 31,19S3 letter for Cycle 2.
We find this change acceptable. The rod insertion limit Technical Specification is also acceptable.
The dropped RCCA event was analyzed by the new Westinghouse Dropped Rod Method-ol ogy.
Results show the DNB design basis is met for all dropped rod events initiated from full power for Cycle 2.
Since the new Westinghouse Dropped Rod Methodology has been approved, the iriterim restrictions on power operation above 90 percent power may be removed. The new Westinghouse Dropped Rod Methodology must continue to be used to evaluate the dropped rod event for each cycle.
Sutrarv 3ased oh' our review we find that the proposed Technical Specification changes to the F,y and rod insertion limit are acceptable, y
8305170023 830505 PDR ADOCK 05000311 p
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2-Environmental Consideration We have determined that the amendment does not authorize a change-in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact.
Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR {51.5(d)(4), that an environmental impact statement or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance of this amendment.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated, does not create the possibility of an accident of a type different from any evaluated pre.viously, and does not involve a significan* reduction in a margin of safety, the amendment does not involve a significant hazards consideration. (2) there is reasonable assurance that the health and safety of the publi'c will not be endangered by operation in the proposed manner, and (3) 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 pubiic.
Date: May 5,1933 l
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