ML20087A169
| ML20087A169 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/27/1995 |
| From: | Matthews D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20087A173 | List: |
| References | |
| NUDOCS 9508040213 | |
| Download: ML20087A169 (7) | |
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UNITED STATES j
j NUCLEAR REGULATCRY COMMISSION t
WASHINGTON, D.o. 20665-4001 49.....,o VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION. UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 202 1.icense No. DPR-32 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated November 29, 1994, 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 Comission; 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 regulations; D.
The issuance of this amendment will not be inimical to the comon 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.
9508040213 950727 ADOCK0500g0 DR
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-32 is hereby anended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 202, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/
David B. Matthews, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 27, 1995
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UNITED STATES l
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NUCLEAR HEGULATORY COMMISSION WASHINGTON, D.C. 2088HOO1 4,..... s/
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 202 License No. DPR-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
f A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated November 29, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as 6
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 (1) 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 regulations; 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.
l l
1 i
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-37 is hereby amended to read as follows:
(B)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 202, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 27,1995 4
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 202 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 202 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Paaes Insert Paaes TS 5.3-1 TS 5.3-1 TS 6.2-3 TS 6.2-3 I
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TS 5.3-1 5.3 flEAClOld i
ADaliGabiktX Applies to the reactor core, Reactor Coolant System, and Safety injection System.
Objective To define those design features which are essential in providing for safe system operations.
Specifications A.
Reactor Core 1.
The reactor core contains approximately 176,200 lbs of uranium dioxide in the form of slightly enriched uranium dioxide pellets.
The pellets are encapsulated in Zircaloy-4 or ZlRLO tubing to form fuel rods.
All fuel rods are pressurized with helium during fabrication. The reactor core is made up of 157 fuel assemblies.
Each fuel assembly contains 204 fuel rods except for fuel assemblies which may be reconstituted to replace leaking fuel rods with non-fueled rods (e.g. zircaloy or stainless steel).
2.
The average enrichment of the initial core is 2.51 weight percent of U-235. Three fuel enrichments are used in the initial core. The highest enrichment is 3.12 weight percent of U-235.
Amendment Hos. 202 aid 202
TS 6.2-3 1
2d.
WCAP-10054-P-A, " Westinghouse Small Break ECCS Evaluation Model i
Using the NOTRUMP Code," August 1985 (W Proprietary)
+
(Methodology for TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 2e.
WCAP-10079-P-A, "NOTRUMP, A Nodal Transient Small Break and General Network Code," August 1985 (W Proprietary)
(Methodology for TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor) i 2f.
WCAP-12610, " VANTAGE + Fuel Assembly Report," June 1990 (Westinghouse Proprietary).
(Methodology for TS 3.12.B.1 and TS 3.12.B.2 - Heat Flux Hot Channel Factor) 3a.
VEP-NE-2-A, "Sta'...tical DNBR Evaluation Methodology," June 1987 (Methodology for TS 3.12.B.1 and TS 3.12.B.2 - Nuclear Enthalpy Rise Hot Channel Factor) 36.
VEP-NE-3-A, " Qualification of the WRB-1 CHF Correlation in the Virginia Power COBRA Code," July 1990 (Methodology for TS 3.12.B.1 and TS 3.12.B.2 - Nuclear Enthalpy Rise Hot Channel Factor)
Amendment Nos. '202 and 202 i
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