ML20070K900
| ML20070K900 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/22/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070K897 | List: |
| References | |
| GL-88-16, NUDOCS 9407280043 | |
| Download: ML20070K900 (3) | |
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UNITED STATES
[ Y e tf i NUCLEAR REGULATORY COMMISSION g4'V-l WASHINGTON. D.C. 20%S 0001
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y SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
189 TO FACILITY OPERATING LICENSE NO. NPF-3 TOLEDO EDISON COMPANY I
CENTERIOR SERVICE COMPANY 8.@
THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DAVIS-BESSE_ NUCLEAR POWER STATION. UNIT NO. 1 DOCKET NO. 50-346
1.0 INTRODUCTION
By letter dated March 18, 1994, as supplemented by letter dated June 20, 1994 (Ref. 2), Toledo Edison Company (the licensee) proposed changes to the Technical Specifications (TS) for the Davis-Besse Nuclear Power Station i
(DBNPS), Unit 1.
The proposed changes would modify additional specifications having cycle-specific parameter limits by replacing the values of those limits with a reference to a Core Operating Limits Report (COLR) for the values of those limits in accordance with the guidance provided in Generic Letter 88-16,
" Removal of Cycle-Specific Parameter Limits from Technical Specifications."
The use of the COLR for DBNPS was previously approved by the NRC.
The June 20, 1994, letter provided supplemental information that did not change the intitial proposed no significant hazards consideration determination.
2.0 EVALUATION The proposed changes to the TS are in accordance with the guidance provided by-GL 88-16 and are addressed below.
t (1) The following additional specifications due to the new approved methodology for reload analyses were revised to replace the values of cycle-specific parameter limits with reference to the COLR that provides these limits.
(a)
Specification 2.1.2 Axial power imbalance protective limits in Figure 2.1-2 for this specification are specified in the COLR.
(b)
Specification 2.2.1 9407280043 940722 DR ADOCK 050003 6
4 a
.. d The reactor protective system trip setting limits in Table 2.2.1 Reactor Protection System Instrumentation Trip Setpoints and Figure 2.2.1 Trip Setpoint for flux -- 4 Flux / Flow for this specification are specified in the COLR.
(c)
Specification 3.2.2 The nuclear hot channel factor - F, limit for this specification is specified in the COLR.
(d)
Specification 3.2.3 The nuclear enthalpy rise hot channel factor - F",, limit for this specification is specified in the COLR The bases of affected specifications have been modified by the licensee to include appropriate reference to the COLR.
Based on our review, we conclude that the changes to these bases are acceptable.
(2) Specification 6.9.1.7 is revised to include currently proposed TS changes under the reporting requirements of the Administrative Control section of the TS. This specification requires that the COLR be submitted, upon issuance, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
The report provides i
the values of cycle-specific parameter limits that are applicable for the current fuel cycle. Furthermore, this specification requires that NRC-approved methodologies be used in establishing the values of these limits for the relevant specifications and that the values be consistent with all applicable limits of the safety analysis.
Those previously reviewed and approved methodologies in COLR TS are deleted and replaced by BAW-10179P-A, " Safety Criteria and Methodology for Acceptable Cycle Reload Analysis" and its future NRC-approved BAW-10179P-A revision.
- However, the applicable approved revision number for BAW-10179A shall be listed and identified in the COLR at the time the reload analyses are performed.
On the bases of the review of the above items, the NRC staff concludes that the licensee provided an acceptable response to those items as addressed in the NRC guidance in Generic letter 88-16 on modifying cycle-specific parameter limits in TS.
Because plant operation continues to be limited in accordance with the values of cycle-specific parameter limits that are established using NRC-approved methodologies, the NRC staff concludes that this change has no impact on plant safety. Accordingly, the staff finds that the proposed changes are acceptable.
We have reviewed the request by Toledo Edison Company to revise the TS of the Davis-Besse Nuclear Power Station, Unit 1 by removing the specific values of additional cycle-dependent parameters from the TS and placing the values in a COLR referenced by the specifications.
Based on the review, we conclude that these revisions are acceptable.
d'
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 changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
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 the amendment involves no significant hazards consideration and there has been no public r
comment on such finding (59 FR 22014).
The amendment also changes a reporting or recordkeeping requirement.
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (c)(10).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
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:
T. Huang Date:
July 22, 1994 l
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