ML20044H409
| ML20044H409 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 05/28/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044H408 | List: |
| References | |
| NUDOCS 9306080353 | |
| Download: ML20044H409 (3) | |
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UNITED STATES j
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMEN 0 MENT NO. 48 TO FACILITY OPERATING LICENSE NO. NPF-58 THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.
PERRY NUCLEAR POWER PLANT. UNIT NO. 1 DOCKET NO. 50-440
1.0 INTRODUCTION
By letter dated June 30, 1992, the Cleveland Electric Illuminating Company, et al. (licensees), proposed changes to the Technical Specifications (TSs) for the Perry Nuclear Power Plant, Unit No.1.
The proposed changes would modify TSs 3.3.1, " Reactor Protection System Instrumentation," and 6.9.1.9, " Core Operating Limits Report (COLR)," to transfer the specific value of the simulated thermal power time constant from the Technical Specifications to the COLR. These changes are being made in accordance with guidance provided in NRC Generic Letter 88-16, " Removal of Cycle-Specific Parameter Limits from Technical Specifications," and supplement similar changes to the Technical Specifications made in Amendment No. 33.
2.0 EVALUATION In Amendment No. 33, the Commission approved the licensee's transfer of certain cycle-specific limits from the Technical Specifications to a Core Operating Limits Report. The licensee's establishment of the COLR included appropriate Technical Specification references to the COLR, as well as requirements for the submittal of the COLR to the NRC prior to operation with the new parameter limits. The currently proposed changes to the Technical Specifications would add the simulated thermal power time constant to the list of values included in the COLR.
Advances in fuel designs have led to the construction of fuel bundles with more individual fuel rods located within the same cross-sectional area.
In order to place additional fuel rods into the same area, the diameter of the fuel rods and fuel pellets must be decreased. The decrease in fuel pellet diameter reduces the simulated thermal power time constant, which is related to the amount of time needed for heat to travel from the center of the fuel pellet to the outer edge.
The Perry Nuclear Power Plant currently uses General Electric 8x8 array fuel bundles, although the licensee is contemplating the use of 9x9 or 10x10 array fuel bundles in upcoming cycles. Since the simulated thermal power time constant is different for the various fuel designs, the use of new fuel 93060B0353 930528 PDR ADDCK 05000440 P
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. designs in the future would necessitate changes to the simulated thermal power time constant on a cycle-specific basis. Therefore, the staff finds that the simulated thermal power time constant is a cycle-specific limit, and is eligible for relocation to the COLR.
The licensee proposes to make several changes to the TS in order to transfer the simulated thermal power time constant to the COLR. The changes would modify (1) the bases for the Reactor Protection System instrumentation setpoints, (2) the footnote to TS Table 3.3.1-2, and (3) the footnote to TS Table 4.3.1.1-1, to reference the simulated thermal power time constant as located in the COLR.
The amendment would also change TS 6.9.1.9, " Core Operating Limits Report," to specify that the COLR will contain the Simulated Thermal Power Time Constant. No other changes to the TSs are made by this amendment.
On the basis of information previously reviewed by the Commission in the Safety Evaluation for Amendment No. 33, the staff found that the licensee's implementation of the COLR adequately addressed the guidance provided in NRC Generic Letter 88-16. The currently proposed changes to the Technical Speci-fications are also consistent with the intent of GL 88-16.
Furthermore, because plant operation will continue to be limited in accordance with the values of cycle-specific parameter limits that are established using an NRC-approved methodology, the NRC staff concludes that this change is adminis-trative in nature and there is no impact on plant safety as a consequence.
Accordingly, the staff finds the proposed changes to be acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Ohio State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change to a requirement with respect to the instal-lation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes to surveillance requirements. The staff has determined that the 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 cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding (57 FR 37561). Accordingly, this amendment meets 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 this amendment.
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5.0 CONCLUSION
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, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) 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:
R. Stransky Date:
May 28, 1993 P