ML20036C202
| ML20036C202 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 06/11/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20036C203 | List: |
| References | |
| NUDOCS 9306150229 | |
| Download: ML20036C202 (3) | |
Text
kw OO Report, L. H. Steves, et. al, "HUXY:
A Generalized Multirod Heatup Code with 10CFR50. Appendix K Qff Heatup Option:
User's Manual," XN-CC-33(A), Revision 1 dated November 14 1975 (Approved by NRC SER, dated March 6, 1975).
oo uta OO Report. "RELAPSYA, A Computer Program for Light-Water Reactor System Thermal-Hydraulic Analysis."
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YAEC-1300P. October 1982 (Approved by NRC SERs, dated August 25, 1987 and October 21, 1992).
2N 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).
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).
Letter from R. W. Capstick (VYNPC) to USNRC, " Request for Supplemental Safety Evaluation Report Supporting the Use of RELAPSYA 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).
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).
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).
Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, " Response to Second Request for Additional Information on the Use of RELAPSYA." BVY 90-067, dated June 8, 1990 (Approved by NRC SER, dated February 27, 1991).
Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, " Response to Request for Additional Information on the Use of RELAPSYA." BVY 90-087, dated August 28, 1990 (Approved by NRC SER, dated October 21, 1992).
Amendment No. 126 135 209b b
VYNP5 (Cuntinued) letter from L. A. Tremblay, Jr. (VYNPC) to USNRC. " Response to Second Request for Additional Information on the U'e of RELAPSYA." BVY 91-05, dated January 9, 1991 (Approved by NRC SER. dated s
Octuber 21. 1992).
Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC " Response to Third Request for Additional Information on the Use of RELAPSYA.* BVY 91 41. dated April 19, 1991 (Approved by NRC SER. dated October 21, 1992).
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 HRC SER, dated October 21, 1992).
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).
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).
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).
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).
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 HRC SER. dated September 24, 1992).
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).
Amendment No.135 209c l
VYNPS (Continued) letter f rom L. A. Tremblay. Jr. (VYNPC) to llSNRC. "l0CA-Related Responses to Open issues on FROSSll'Y 7 Fuel Performance Code." BVY 92-39. dated March 21 1992 (Approved by NRC SER. dated September 24 1992).
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).
Report.
Loss-of-Coolant Accident Analysis for Vermont Yankee Nuclear Power Station." NE00-21697 August 1977, as amended (Approved by NRC SER, dated November 30. 1977).
Report. General Electric Standard Application for Reactor fuel (GESTARil)." NEDE-24011 P-A. GE Company Proprietary (the latest NRC-approved version will be listed in the COLR).
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits. ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
The COLR.
including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident inspector.
B.
Reportable Occurrences This section deleted.
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4 Amendment No 135 7090 l
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