ML20044H127

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Safety Evaluation Supporting Amend 135 to License DPR-28
ML20044H127
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 05/28/1993
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20044H126 List:
References
NUDOCS 9306070446
Download: ML20044H127 (4)
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WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.135 TO FACILITY OPERATING LICENSE NO. DPR-28 VERMONT YANKEE NUCLEAR POWER CORPORATION VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

1.0 INTRODUCTION

By letter dated March 26, 1993, the Vermont Yankee Nuclear Power Corporation proposed changes to the Vermont Yankee Nuclear Power Station, Technical Specifications (TS).

The proposed changes would add 21 NRC reviewed and approved methodologies for use in generating the limits in the Core Operating Limits Report (COLR) to TS 6.7.A.4.

Technical Specification 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) The Average Planar Linear Heat Generation Rates (APLHGR) for Specifications 3.II. A and 3.6.G.la, (b) The K, core flow adjustment factor for Spe,-ification 3.ll.C., (c) The Minimum Critical Power Ratio (MCPR) for Specifications 3.ll.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 ll.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.

2.0 EVALVATION

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Technical Specification 6.7. A.4 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 pr,ovides 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 be established using NRC-approved methodology and be consistent with all applicable limits of the safety analysis. The proposed additions to the approved nethodologies are the following:

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1. Report, L. H. Steves, et al. "HUXY: A Generalized Multirod Heatup Code with 10 CFR 50, Appendix K Heatup Option: User's Manual," XN-CC-33 (A),

Revision 1, dated November 14, 1975 (Approved by NRC SER, dated March 6, 1975).

2. Report, "RELAPSYA, A Computer Program for Light-Water Reactor System Thermal-Hydraulic. Analysis," YAEC-1300P, October 1982 (Approved by NRC SERs, dated August 25, 1987 and October 21, 1992).
3. Report, R. T. Fernandez and H. C. daSilva, Jr., " Vermont Yankee BWR Loss-of-Coolant Accident Licensing Analysis Method," YAEC-1547, June 1986 (Approved by NRC SER, dated October 21, 1992).
4. Letter from R. W. Capstick (VYNPC) to USNRC, "HUXY Computer Code Information for the Vermont Yankee BWR LOCA Licensing Analysis Method," FVY 87-63, dated June 4, 1987 (Approved by NRC SER, dated February 27, 1991).
5. Letter from R. W. Capstick (VYNPC) to USNRC, " Request for Supplemental Safety Evaluation Report Supporting the Use of RELAP5YA for Vermont Yankee Nuclear Power Station," FVY 88-006, dated January 26, 1988 (Approved by NRC SERs, dated February 27, 1991 and October 21,1992).
6. Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, " Supplementary -Information Regarding NRC LOCA Analysis Review Effort," BVY 89-91, dated October 6, 1989 (Approved by NRC SER, dated October 21, 1992).

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Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, " Supplementary Information Regarding NRC LOCA Analyses Review Effort," BVY 90-028, dated March 9, 1990 (Approved by NRC SER, dated October 21,1992).

8. Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, " Response to Second Request for Additional Information on the Use of RELAP5YA," BVY 90-067, dated June 8, 1990 (Approved by HRC SER, dated February 27, 1991).
9. Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, " Response to Request fe' Additional Information on the Use of RELAP5YA," BVY 90-087, dated August 28, 1990 (Approved by NRC SER, dated October 21, 1992).
10. Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, " Response to Second Request for Additional Information on the Use of RELAP5YA," BVY, 91-05, dated January 9, 1991 (Approved by NRC SER, dated October 21, 1992).
11. Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, " Response to Third Request r

for Additional Information on the Use of RELAP5YA," BYV 91-41, dated April 19, 1991 (Approved by HRC SER, dated October 21, 1992).

12. Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, " Supplementary Information Regarding the Use of RELAP5YA," BVY 92-12, dated February 7, 1992 (Approved by NRC SER, dated October 21, 1992).

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13. Letter from R. W. Capstick (VYNPC) to USNRC, " Vermont Yankee LOCA Analysis Method FROSSTEY Fuel Performance Code (FROSSTEY-2)," FVY 87-116, dated December 16, 1987 (Approved by NRC SER, dated September 24, 1992).
14. Letter from R. W. Capstick (VYNPC) to USNRC, " Response to NRC Request for Additional Information on the FROSSTEY-2 Fuel Performance Code," BVY 89-65, dated July 14, 1989 (Approved by NRC SER, dated September 24, 1992).
15. Letter from R. W. Capstick (VYNPC) to USNRC, " Supplemental Information on the FROSSTEY-2 Fuel Performance Code," BVY 89-74, dated August 4, 1989 (Approved by NRC SER, dated September 24, 1992).
16. Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, " Responses to Request for Additional Information on FROSSTEY-2 Fuel Performance Code," BVY 90-045, dated April 19, 1990 (Approved by NRC SER, dated September 24, 1992).
17. Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, " Supplemental Information to VYNPC April 19, 1990 Response Regarding FROSSTEY-2 Fuel Performance Code,"

BVY 90-054, dated May 10, 1990 (Approved by NRC SER, dated September 24, i

1992).

18. Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, " Responses to Request for Additional Information on FROSSTEY-2 Fuel Performance Code," BVY 91-024, dated March 6, 1991 (Approved by NRC SER, dated September 24, 1992).
19. Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, "LOCA-Related Responses to Open Issues on FROSSTEY-2 Fuel Performance Code," BVY 92-39, dated March 27, 1992 (Approved by NRC SER, dated September 24, 1992).
20. Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, "FROSSTEY-2 Fuel Performance Code - Vermont Yankee Response to Remaining Concerns," BVY 92-54, dated May 15, 1992 (Approved by NRC SER, dated September 24,1992).
21. Report, " General Electric Standard Application for Reactor Fuel (GESTARII),"

NEDE-EC011-P-A, GE Company Proprietary (the latest.NRC-approved version will be listed in the COLR).

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All of the above methodologies have been reviewed and approved by the NRC staff.

Accordingly, the staff finds that the proposed changes are acceptable.

3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Vermont State Official was notified of the proposed issuance of the amendment.

The State Official had no comments.

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4.0 ENVIRONMENTAL CONSIDERATION

This amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements.

Accordingly, the amendment meets 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 amendment.

5.0 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 amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor:

David H. Moran Date: May 28, 1993 l

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