ML20082V258
| ML20082V258 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 09/09/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082V257 | List: |
| References | |
| NUDOCS 9109230183 | |
| Download: ML20082V258 (4) | |
Text
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- ,gv.....f SAFETY EVALVATION BY THE Of flCE Or NUCLEAR REACTOR REGUL ATION REL ATED TO AMENDMENT NOS. 27 AND 17 TO FAClllTY OPERATING LICENSE N05. NPF-76 AND NPF-80 HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DOCKET N05. 50-498 AND 50-499 SOUTH TEXAS PROJECT, UNITS 1 AND 2
1.0 INTRODUCTION
By letters dated September 15, 1989, and January 8, 1991, as amended by letter dated May 23, 1991, Houston Lighting & Power Company (HLEP) (the licensee) proposed changes to the Technical Specifications (TS) for the South Texas Project Units 1 and 2 (STP).
The proposed changes would modify additional specifications which have cycle-specific parameter limits by replacing the values of those limits with a reference to a Core Operating Limits Report (COLR).
The use of the COLR for STP was previously approved by the NRC.
Guidance on the proposed changes was developed by NRC on the basis of the review of a lead plant proposal submitted by Duke Power Company for the Oconee plant.
This guidance was provided to all power reactor licensees and applicants by Generic Letter 88-16, " Removal of Cycle-Specific Parameter Limits from Technical Specifications," dated October 4,1988.
The May 23, 1991, letter provided clarifying information that did not alter the action noticed or change the initial proposed no significant hazards consideration determination.
2.0 EVALUATION The licensee's proposed additional changes to the TS are in accordance with the guidance provided by Generic Letter 88-16 and are addressed below.
(1)
In addition to the approved cycle-specific core operating limits, in Amendment No. 9 (Unit 1) and Amendment No. 1 (Unit 2) dated July 31, 1989, the following specifications were revised to replace the values of cycle-specific parameter limits with a reference to the CCLR that provides these limits.
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(a) Specification 3.1.1.3 and Surveillance Requirement 4.1.1.3 The moderator temperature coefficient (MTC) limits for this specification and for this requirement are specified in the COLR.
(b) Specification 3.1.3.5 The shutdown rod insertion limit for this specification is specified in the COLR.
(c) Specification 3.2.1 The axial flux difference limits and target band for this specification are specified in the COLR.
(d) Specification 3.2.2 and Surveillance Requirement 4.2.2 1he heat flux hot channel factor (F ) limit at rated thermal power, n
the normalized F limit as a function of core height K(z), and the Fxy 9
limits for rated thermal power for this specification and for this surveillance requirement are specified in the COLR.
(c) Specification 3.2.3 The nuclear enthalpy rise hot channel factor (F H) for this specification is specified in the COLR.
The Bases for the af fected specifications have been modified by the licensee to include appropriate reference to the COLR.
Based on its review, the staff concludes that the changes to t.nese Bases are acceptable.
(2) Specification 6.9.1.6, Core Operating Limits Report, of the Administrative Controls section of the TS, is revised to include currently proposed TS chang?s in Specification 6.9.1.6.a and to ado additional NRC approved methodologies in Specification 6.9.1.6.b to support the values of cycle-specific parameter limits that are applicable for the current fuel cycle.
The approved methodologies are the following:
(a) WCAP-9272-P-A, " Westinghouse Reload Safety Evaluation Methodology,"
July 1985 (W Proprietary).
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Rod Insertion Limit, 3.1.3.6 -
Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
3-(b) WCAP-8385, " Power Distribution and Load following Procedures Topical Report," September 1974 (W Proprietary).
(Methodology for Specification 3.2.1 - Axial flux Difference (Constant Axial Offset Control]).
1 (c) 'w*6tinghouse letter NS-TMA-2198,1.M. Anderson (Westinghouse) to K. Kniel (Chief of Core Performance Branch, NRC) January 31, 1980 -
Attachment:
Operation and Safety Analysis Aspects of an Improved Load follow Package, (Methodology for Specification 3.2.1 - Axial flux Difference b
[ Constant Axial Offset Control).
Approved by NRC Supplement No. 4 to NUREG-0422. January 1981, Docket Nos. 50-369 and $0-370.)
(d) NUREG-0800, Standard Review Plan, U.S. Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July 1981.
Branch Technical Position CPB 4.3-1, Westinghouse Constant Axial Of fset Control (CAOC), Rev. 2, i
July 1981.
(Methodology for Specification 3.2.1 - Axial flux Difference
[ Constant Axial Offset Control]).
(c) WCAP-9220-P-A, Rev. 1 " Westinghouse ECCS Evaluation Model-1981 Version," February 1982 (W Proprietary).
(Methodology for Specification 3.2.2 - Heat flux Hot Channel factor.)
(f) WCAP-9561 A, Add. 3, Rev. 1, "BART A-1:
A Computer Code for the Best Estimate Analysis of Reflood Transients - Special Report:
Thimble Modeling W ECCS Evaluation Model," July 1986, (W Proprietary).
(Methodology for Specification 3.2.2 - Heat flux Hot Channel factor,)
' Finally, the specification requires that all changes in cycle specific parameter limits be documented in the COLR before each reload cycle or remaining part of a reload cycle and submitted upon issuance to NRC.
On the basis 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 parameters 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 the proposed changes are acceptable.
3.0 STATE CONSULTATION
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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.
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4 4.0 ENVIRONMENTAt 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 staf f 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 (56 FR 9380).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
These amendments also relate to changes in recordkeeping or reporting requirements.
Accordingly, with respect to these items, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(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 amendments.
5.0 CONCtUSION The Commission has concluded, based on the consideration 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:
T. Huang Date:
September 9, 1991 o
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