ML20059C467
| ML20059C467 | |
| Person / Time | |
|---|---|
| Site: | Callaway |
| Issue date: | 08/23/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059C461 | List: |
| References | |
| NUDOCS 9009050071 | |
| Download: ML20059C467 (2) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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l SAFETY EVALUATION BY'THE OFFICE OF NUCLEAR REACTOR REGULATION-RELAlto To Amtnumtni NO. 56 TO FACILITY OPtKATING LILLMbE NO. NPF-30 UNION ELECTRIC COMPANY CALLAWAY PLANT. UNIT 1 DOCKET NO. 5TN 50-483
1.0 INTRODUCTION
By letter dated March 6,1990, Union Electric Company requested a change to
-the' Technical Specifications for the Callaway Plant.. The change would delete the power range, neutron flux, high negative rate trip or negative' flux rate trip (NFRT)fromtheNuclearInstrumentationSystem. Technical Specifi-cations affected by this change include Tables 2.2-1, 3.3-1, 3.3-2 and 4.3-1 and their associated bases. This change is consistent with Westinghouse WCAP-11394(P) which was approved by NRC on October 23.-1989. Plant modifi-cations to. remove the trip circuitry will be completed in Refueling 4, which is scheduled for fall 1990.
2.0 EVALUATION In May 1987, the Westinghouse Owners Group submitted Topical Report WCAP-11394(P), " Methodology for the Analysis of the Dropped Rod-Event."
Westinghouse extended the methodology which was previously used to show thht the results of the dropped rod-event were acceptable without taking credit
-for any direct: trip due to the dropped rods and no autoinatic power reduction 1
was assumed due to the dropped rods. Thus, the NFRT could be removed.
As confirmation, and as part of each reload cycle, the Westinghouse method-ology will be used to demonstrate that the DNB design basis is not exceeded during the course of the dropped Rod Cluster Control Assembly (RCCA) tran-1 sient.
The analysis will be performed using the cycle-dependent control rod worth at full power insertion limits and the moderator temperature coef-ficient as input. This analysis produces a hot' channel factor which is used to calculate the limiting departure from nucleate boiling ratio (DNBR) during the transient and ensure that the DNB design basis is met.
The staff reviewed WCAP-11394(P) and found the methodology acceptable for
. referencing by letter dated October 23, 1989. Union Electric's request is an application of this methodology and is therefore, acceptable.
' Union Electric Company has copitted to perform an analysis for each Callaway. cycle to show that the DNB design basis is met. This analysis will be included as part of the Reload Safety Evaluation for each Callaway oper-ating cycle, 9009050o7i 9008 3 2
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3.0 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 or a change to a surveillance requirement. The staff has determined that the amendment involves no significant increase in 1
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. Accordingly.
-l 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 i
impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the will not be endangered by operation in the pro)osed manner; and (2) public such activities will be conducted in compliance wita the Comission's regulations j
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.
6.0 ACKNOWLEDGEMENT Principal Contributors:
M. Chatterton, SRXB/ DST Dated: August 23, 1990
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