ML20217P933
| ML20217P933 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 04/07/1998 |
| From: | Thomas C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217P937 | List: |
| References | |
| NUDOCS 9804100237 | |
| Download: ML20217P933 (5) | |
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UNITED STATES s
P; NUCLEAR REGULATORY COMMISSION WASNINGToN D.C. asseHOM 49.....
VERMONT YANKFF NUCLEAR POWER CORPORATION DOCKET NO. 50-271 VERMONT YANKFF NUd FAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.157 License No. DPR-28
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1.
The Wuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Vermont Yankee Nuclear Power Corporation (the licensee) dated June 9,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's rcgulations; D.
The issuance of'this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-28 is hereby amended to read as follows:
I 9804100237 900407
'r DR ADOCK 05000271 p
PDR I
2-I (B)
Technical Specht;ons The Technical Speerfications contained in Appendix A, as revised through Amendment No. 157, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, i
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This license amendment is effective as of its date of issuance to be implemented within 30 days ofissuance.
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FOR THE NUCLEAR REGULATORY COMMISSION
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Cecil O. Thomas, Director Project Directorate 1-3 Division of Reactor Projects - t/il Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: Apri1 7, 1998 i
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1 ATTACHMENT TO LICENSE AMENDMENT NO.15 7 FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271 Replace the following page of Appendix A Technical Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 270-270 270s (new page)
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WNPS Letter from L.*A.
Tremblay, Jr. (VYNPC) to USNRC,
' Supplemental Information to WNPC April 19, 1990 Response Regarding FROSSTEY-2 Fuel Performance Code.*
BW 90-054, dated May 10, 1990 (Approved by NRC SER, l.
dated September 24, 1992).
Letter from L. A. Tremblay, Jr. (WNPC) to USNRC,
' Responses to Request for Additional Information on FROSSTEY-2 Fuel Performance Code.
- BW 91-024, dated March 6, 1991 (Approved by NRC SER, dated l
September 24, 1992),
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Letter from L. A. Tremblay, Jr. (WNPC) to USNRC, "LOCA-Related Responses to Open Issues on FROSSTEY-2 Fuel Performance Code *. BW 92-39, dated March 27,-1992-(Approved by NRC SER, dated September 24, 1992).
i Letter from L. A. Tremblay, Jr. (VYNRC) to USNRC, "FROSSTEY-2 Fuel Perfoz1 nance Code - Vermont Yankee i
Response to Remaining Concerns,* BVY 92-54, dated May 15, 1992 (Approved by NRC SER, dated September 24, 1991).
Report, " Loss-of-Coolant Accident Analysis for Vermont Yankee Nuclear Power Station," NEDO-21697,' August 1977, as amended (Approved by NRC SER, dated November 30, 1977).
Report, " General Electric Standard Application for Reactor Fuel (GESTARII),' NEDE-24011-P-A, GE Company Proprietary (the latest NRC-approved version will be listed in the COLR).
Report, General Electric Nuclear Energy, "BWR Owner's Group Long-Term Solutions' Licensing Methodology,*
NEDO-31960, June 1991 (Approved by NRC SER, dated July.12, 1993).
Report, General Electric Nuclear Energy, "BWR Owner's Group Long-Term Solutions Licensing Methodology,*
NEDO-31960, Supplement 1,-March 1992 (Approved by NRC SER, dated July 12, 1993).
Report, N. Fujita,' et al., " Method for Power / Flow Exclusion Region Calculation Using the LAPUR5 Computer Code,* YAEC-1926-A (Approved by NRC SER, dated November 5, 1996).
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical-limits, core thermal-hydraulic limits, ECCS limits,
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nuclear limits such as shutdown margin, and transient.
j and accident analysis limits) of the safety analysis are met.
The COLR, including any mid-cycle revisions or J
' supplements thereto, shall be provided upon issuance, i
for each reload cycle, to the NRC Document Control Desk l
with copies to the Regional Administrator _and Resident i
Inspector.
l-B.
Reportsole Occurrences This section deleted.
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4 Amendment No. M, G, M, 4M, 4M, 4M, H4, 4M,15 7 270
4 VYNPS C.
Uniaue Reportina Recuirements 1.
Annual Radioactive Effluent Release Report Within 90 days after January 1 of each year, a a.
report shall be submitted covering the radioactive content of effluents released to unrestricted areas during the previous calendar year of operation.
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Amendment No. 157 270a a
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