ML20211J952
| ML20211J952 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/30/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211J951 | List: |
| References | |
| NUDOCS 9909070071 | |
| Download: ML20211J952 (3) | |
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g SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION BELATED TO AMENDMENT NO. 67 TO FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. 67 TO FACILITY OPERATING LICENSE NO. NPF-89 l
TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446 i
1.0 INTRODUCTION
By application dated May 24,1999, as supplemented by letter dated July 9,1999, Texas Utilities Electric Company (the licensee) requested changes to the Technical Specifications (TSs) for the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2. The proposed amendments would remove several cycle-specific parameter limits from the TSs. These parameter limits would be added to the Core Operating Limits Report (COLR) Appropriate references to the COLR would be inserted in the affected TSs. In addition, the core safety limit curves would be replaced with safety limits more directly applicable to the fuel and fuel cladding fission product barriers. The affected TSs are (1) TS 2.0, " Safety Limits (SLs)," (2) TS 3.3.1,
" Reactor Trip System instrumentation Setpoints," (3) TS 3.4.1, "RCS [ reactor coolant system]
Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits," and (4) TS 5.6.5, " Core Operating Limits Report."
2.0 EACKGROUND At the present time, the CPSES TSs contain parameters that are specifically applicable to the operation of CPSES for a particular fuel cycle. Guidance on the relocation of cycle specific TS parameters to the COLR was developed by the NRC. This guidance was provided to all power reactor licensees and applicants by Generic Letter (GL) 8816, dated October 4,1988.
Westinghouse Electric Company (Westinghouse) subsequently developed a topical report that describes how cycle-specific parameters, in TSs for facilities with nuclear steam supply systems designed by Westinghouse, can be transferred to the COLR. This topical report, WCAP-14483-A, " Generic Methodology for Expanding Core Operating Limits Report," was accepted for referencing by the NRC staff on January 19,1999, and referenced by the licensee in its May 24,1999, application.
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3.0 EVALUATION.
The following CPSES TSs have been evaluated concerning the transfer of cycle-specific parameters to the CPSES COLR:
Figure 2.1.1-1 for Units 1 and 2 (Reactor Core Safety Limits) would be transferred to the COLR.
The figure would be referenced in the Bases. The figure would be replaced by TS 2.1.1.1 which would state that in MODES 1 and 2 the departure from nucleate boiling ratio (DNBR) shall be maintained greater than or equal to the 95/95 DNB criterion for the DNB correlation (s) specified in TS 5.6.5, and by TS 2.1.1.2, which would state that in MODES 1 and 2, the peak
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fuel centerline temperature shall be maintained less than 4700 *F. Therefore, the figures would be replaced with more specific requirements regarding the safety limits (i.e., the fuel DNB ~
design basis and the fuel centerline melt design bass), conforming with WCAP-14483 A.
TS 3.3.1. Table 3.3.1-1. " Reactor Trio Svstem Instrumentation Tno Setooints" I
The licensee has proposed that the numerical values pertaining to the overtemperature N-16 reactor trip setpoint be relocated to the COLR. The NRC has previously approved COLR additions for relocating the Overtemperature Delta T and Overpressure Delta T setpoint parameter values to the COLR for the Catawba, McGuire, South Texas, and Seabrook nuclear stations. This allows these setpoints to be based on cycle-specific com design parameters, which are verified on a cycle-specific basis, thereby avoiding the necessity of overly.
conservative TS limits. The applicable NRC-approved setpoint methodology, RXE-90-006-P-A,.
" Power Distribution Control Analysis and Overtemperature N-16 and Overpower N 16 Trip Setpoint Methodology," dated June 1994, would be added to the list of approved analytical methods in TS 5.6.5.b.
TS 3.4.1. "RCS Pressure. Temoerature. and Flow Departure from Nucleate Boilina (DNB)
Limits" The licensee has proposed to relocate the pressurizer pressure, the RCS average temperature, and the RCS total flow rate to the COLR. These are cycle specific values based on the total RCS flow (i.e., the sum of all four loop flows) and includes an allowance of 1.8 percent for the uncertainty associated with the measurement of the RCS flow.
The minimum RCS total flow rate of 389,700 gallons per minute would be retained in TS 3.4.1.
This is the original licensed value approved by the NRC for CPSES, Unit 1, TS. Since this minimum value is retained in the TS, any reduction in RCS flow rate due to additional tube plugging or other physical plant change would have to be reviewed by the NRC staff.
TS 5.6.5. " Core Ooeratina Limits Reoort (COLR)"
~ The COLR would be modified to reflect the relocatior of the cycle-specific parameters, previously addressed, to the COLR and to add the appropriate approved references for the COLR parameters. In addition, the present references in TS 5.6.5.b would be updated to incorporate the approved versions, where appropriate.
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3-q The staff has reviewed the proposed TS revisions for CPSES, Units 1 and 2, and finds them in conformance with NRC GL 88-16 and with WCAP-14483-A and acceptable. Specifically, the revisions would relocate the reactor core limits figure for thermal power, pressurizer pressure, and the highest operating loop average coolant temperature for TS 2.1.1 to the COLR and replace the figure with the fuel integrity DNBR and peak fuel centerline melt temperature limits,
- which are the true safety limits. The numerical values pertaining to the overtemperature -16 trip setpoint values for TS 2.2 and the DNB-related parameters for RCS pressure, temperature, and flow would also be relocated to the COLR.
4.0 STATE CONSULTATION
. in accordance with the Commission's regulations, the Texas State official was notified of the proposed issuance of the amendments. The State official had no comments.
.5.0. ENVIRONMENTAL CONSIDERATION The amendments change 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 NRC staff has determined that the amendments involve 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 amendments involve no
'significant hazards consideration, and there has been no public comment on such finding (64 FR 35213 dated June 30,1999, and 64 FR 40908 dated July 28,1999). Accordingly, the amendments meet 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 the amendments.
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 of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: L.Kopp Date:
August 30, 1999
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