ML20236B300
| ML20236B300 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 10/14/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236B293 | List: |
| References | |
| NUDOCS 8710260067 | |
| Download: ML20236B300 (2) | |
Text
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION i2 WASHINGTON, D. C. 20555 o
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1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION l
RELATED TO AMENDMENT NO. 29 TO FACILITY OPERATING LICENSE NO. NPF-30 l
l UNION ELECTRIC COMPANY l
CALLAWAY PLANT, UNIT 1 l
l DOCKET NO. STN 50-483 I
1.0 INTRODUCTION
l In a letter dated June 18, 1987, Union Electric Company (the licensee) proposed l
changes to the Callaway Technical Specification 3.1.3.5 and to Figure 3.1-1.
The proposed changes stra that all shutdown rods shall be withdrawn 225 steps or higher, and revise Figure 3.1-1 to show 225 steps as fully withdrawn.
O 2.0 EVALUATION
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The licensee proposea the change to minimize localized rod cluster control i
assembly (RCCA) wear at the top of the control rods.
The proposed technical specification change will allow operatfor, with the RCCA's inserted three steps into the reactor from their normal withdrawn position of 228 steps.
At 225' l
steps withdrawn, the RCCA's are only 0.3 inchos into the active fuel region.
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Since the top region of the core has such low worth, the resultant power distribution perturbations are calculated to be negligible and can be accommo-dated with available margin.
Similarly, the effect on shutdown margin is minimal (0.02% Ap), and can be accommodated by available excess shutdown margin (1.95%
l Ap at 00L and 0.61% Ap at E0L).
I The, impact on other key safety parameters was found to be negligible in the j
licensee's analysis.
Because the proposed changed will insert the RCCA's so
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little into the active fuel region, the staff would expect essentially negligi-
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ble effects of the proposed change as reported in the licensee's evaluation.
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Based on the above evaluaticn, the staff agrees that the proposed change has essentially negligible effect and is, therefore, acceptable.
The staff did, l
however, suggest and the licensee agreed to slight changes in the wording of the technical specification.
By doing this, the Callaway technical specifi-l cations are consistent with those of other Westinghouse plants which have requested this change, i
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3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change to a requirement with respect to the instal-1 lation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and a change to a surveillance requirement.
The i
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 B710260067 871014 PDR ADOCK 05000403' 1
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, released offsite'and that there is ne 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.
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.
4.0. CONCLUSION l
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The staff has ccncluded, 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 i
l be conducted in comp'liance 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.
J Principal Contributors:
M. Chatterton, SRXB T.' Alexion,.PDIII-3 Dated: October 14, 1987 h
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