ML17223B260
| ML17223B260 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 09/10/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17223B259 | List: |
| References | |
| NUDOCS 9109170331 | |
| Download: ML17223B260 (6) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555 SAFETY EVAI UATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
109 TO FACILITY OPERATING LICENSE NO.
DPR-67 FLORIDA POWER III LIGHT COMPANY ST.
LUCIE PLANT, UNIT NO.
1 DOCKET NO. 50-335
1.0 INTRODUCTION
By letter dated Apri 1 17, 1991, Florida Power and Light Company (FPL) requested an amendment to Facility Operating License No.
DPR-67 for St. Lucie Unit 1.
The amendment would delete the St. Lucie Unjt 1 Technical Specification 3/4.2.2, "Total Planar Radial Peaking Factor -
F
" and all of its references.
xy 2.0 EYALUATION For future reloads of the St.
I ucie Unit 1 core, the axial power distributions (APDs) will be generated by Advanced Nuclear Fuels (ANF) Corporation using a
three-dimensional core model (XTGPWR), rather than the synthesized one-dimensional axial and two-dimensional radial power distribution model previously used.
In this synthesis technique, the total peaking factor, F
, was determined by multi-plying the core average axial power distribution, F
, by F
, the maximum ratio of the peak-to-average power density of the in'dividtIal fueIyrods in any of the unrodded horizontal planes (planar radial peaking factor), excluding any azimuthal tilt effects.
Assurance that the resultant F
is not exceeded was obtained by limiting the maximum value of F at which th3 core can operate.
In the new three-dimensional model, the neQ for an F
limit is eliminated, since F
is calculated directly and is limited by adheQnce to the F
Technical Speci)ication limit.
The integrated radial peaking factor, F, is defined as the ratio of the peak pin power to the average pin power in the Eore, excluding tilt.
The ANF three-dimensional APD model has been previously reviewed and approved by the staff.
In a letter from M.
W. Hodges to R.
A Copeland (ANF) dated July 8, 1988, the staff stated that the ANF three-dimensional methodology given in ANF-507(P),
Addendum 1, may be referenced for licensing applications.
However, to justify removal of the Technical Specification F
limit, each application must provide assurance that the three-dimensionaPbased setpoints remain bounding.
The setpoint analysis for the local power density (LPD) limiting safety system settings (LSSS) and the LPD limiting conditions for operation (LCO) utilized F~ and Fr to establish the operational limits that qi09i7033i qi09i0 PDR ADOCK 05000335~
P PDR
ensure that the core thermal limits are not exceeded.
In addition, the assumptions used in the St. Lucie Unit 1 accident analysis bound the changes caused by the proposed Technical Specification modifications and the accident consequences remain acceptable.
3.0 TECHNICAL FINDING To delete the F
limit and replace it with the integrated radial peaking factor F
, the licensee proposed the following specific changes:
r'age Ia IV 1-7 3/4 2-2 3/4 2-6, 3/4 2-7 3/4 2-8 3/4 2-11 3/4 10-2
~Chan e
The reference to the "Unrodded Planar Radial Peaking Factor-F
" is deleted from the Index oP Definitions.
The reference to Technical Specification 3/4.2.2 is deleted from the Index of Limiting Conditions for Operation and Surveillance Requirements.
The definition 1.37 "Unrodded Planar Radial Peaking Factor-F
" is deleted.
xv The term "F
" in Surveillance Requirement P2.1.3 Item ~. is replaced with the term "F ".
The "TOTALTPLANAR RADIAL PEAKING FACTOR -
F
" Limiting Condition for OperatiQ 3.2.2 and Surveillance Requirements 4.2.2.1, 4.2.2.2, 4.2.2.3 and 4.2.2.4 are deleted.
The reference to "F
" is deleted Ia T Ia from FigureT3.2-3.
Qditionally, the term "F1" is deleted.
The references to the "Total Planar Radial Peaking Factor, F
" and to the limits of SpecificatiQ 3.2.2 are deleted from Technical Specification 3/4.2.4.
Revised text accounts for the deletions.
The references to Technical Specification 3.2.2 are deleted from Technical Specification 3/4.10.2.
~
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Page B 3/4 2-1 Change In the Technical Specification Bases for 3/4.2.1 for Linear Heat Rate, the word "PLANAR" is replaced with the word " INTEGRATED" and the reference to Technical Specification "3.2.2" is replaced with "3.2.3".
B 3/4 2-1, B 3/4 2-2 The Technical Specification Bases for 3/4.2.2 is deleted.
The text is corrected to a~count for the deletion of the F limit.
Additionally, the term "F " is being added to the text after the word "determine" in the second line of the second paragraph of Page B 3/4 2-2.
Based on the evaluation contained in Section 2.0 of this Safety Evaluation, the NRC staff finds the above Technical Specifications changes acceptable.
4.0 STATE CONSULTATION
Based upon the written notice of the proposed amendment, the Florida State official had no comments.
5.0 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 and changes surveillance requirements.
The NRC 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 (56 FR 22466).
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.
6.0 CONCLUSION
The Commission 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
0'
of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
L. Kopp Date:
September 10, 1991