ML20064A288
| ML20064A288 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 08/24/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064A287 | List: |
| References | |
| NUDOCS 9008310052 | |
| Download: ML20064A288 (3) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SyPPORTINGAMENDMENTNO.126 TO FACILITY OPERATING LICENSE NO. DPR-28 I
VERMONT VANVEE NUCLEAR POWEP CORPORATION
. VERMONT'IANKEE NUCLEAR POWER STATION DOCKET N0. 50-271 l
1.0 INTRODUCTION
By letter dated June 11, 1990, Vermont Yankee Nuclear Power Corporation (the licensee) proposed changes to the Technical Specifications (TS) for Vermont Yankee. The proposed changes would add to Technical Specification 6.7.A.4 six NRC reviewed and approved methodologies for use in generating l
the limits in the Core Operating Limits Report (COLR). Technical Specification i
6.7.A.4 presently requires that certain core operating limits be established and documented in the COLR before each reload cycle. These requirements pertain to:
(a)TheAveragePlanarLinearHeatGenerationRates(APLHGR)for Specifications 3.11.A and 3.6.G.la, (b) The Kg core flow adjustment factor for Specification 3.11.C., (c) The Minimum Critical Power Ratio i
(MCPR) for Specifications 3.11.C and 3.6.G.la, and (d) The Linear Heat Generation Rates (LHGR) for Specifications 2.1.A.la, 2.1.B.1, and 3.11.B.
Technical Specification 6.7.A.4 further requires that these limits be determined by certain methods which have been previously reviewed and approved by the NRC, and which are listed in Technical Specification 6.7.A.4 i
r In addition, the licensee e.dvised of a needed deletion of Basis page 67a for Technical Specification 4.2, Protective Instrumentation by letter dated November 28, 1989.
2.0 EVALUATION i
Technical Specification 6.7.A.4 requires that the COLR be submitted, upon i
issuance, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector. The report provides the values of cycle-specific parameter limits that are applicable for the current fuel cycle.
Furthermore, this specification requires that the values of these limits are established using NRC approved methodology and be consistent with all applicable limits of the safety analysis. The proposed additions to the approved methodologies are the following:
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9008310052 900824 PDR ADOCK 05000271 P
2 a.
Report, A. A. F. Ansari, " Methods for the Analysis of Boiling Water Reactors: Steady-StateCoreFlowDistributionCode(FIBWR),"YAEC 1234, December 1980.
b.
Report A. $. DiGiovine, et al., CASMO-3G Validation, YAEC-1363-A, April 1988 c.
Report A. S. DiGiovine, J. p. Gorski, and M. A. Tremblay, SIMULATE-3 Validation and Verification, YAEC-1659-A, September 1988 d.
Report, R. A. Woehlke, et al., MICBURN-3/CASMO-3/ TABLES-3/ SIMULATE-3 Benchmarking of Vermont Yankee Cycles 9 through 13, YAEC-1683-A, March 1989 e.
Report, J. T. Cronin, Method for Generation of One-Dimensional Kinetics Data for RETRAN-02, YAEC-1694-A, June 1989 f.
Reporte V. Chandola, M. P. LeFrancois, and J. D. Robichaud, LAlication of One-Dimensional Xinetics to Boiling Water Reactor TransCnt Analysis Methods, YAEC-1693-A, Revision 1, November 1989 All of the above methodologies have been reviewed and approved by the NRC staff. Accordingly, the staff finds that the proposed c1anges are acceptable.
page 67a of the Basis to TS 4.2 has been deleted to reflect current design.
The complete deletion of this Basis page removes language that is no longer applicable to the plant.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change in a requirement with respect to the 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 a;nounts, 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 published a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eli categorical exclusion set forth in 10 CFR 51.22(c)(gibility criteria for 9). Pursuant to 10 CFR 51.22(b),noenvironmentalim3actstatementorenvironmentalassessmentneedbe prepared in connection with tie issuance of this amendment.
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4.0 CONCLUSION
S We have reviewed the request by the Vermont Yankee Nuclear Power Corporation to modify the Technical Specifications of the Vermont Yankee plant that would add six NRC reviewed and approved methodologies for use in generating the limits in the COLR. Based on this review, we conclude that the addition of these six reports to the TS is acceptable.
The Comission made a proposed determination that the amendment involves no significant hazards consideration which was published in the Federal Register (55 FR 30315) on July 25, 1990, and consulted with the State of Vermont. No public coments were received and the State of Vermont did not have any comments.
The staff concludes that the proposed change to the Technical Specifications is acceptable.
Principal Contributor:
V. t..
Rooney Dated: August 24, 1990