ML062230114
| ML062230114 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/10/2006 |
| From: | NRC/NRR/ADRO/DORL/LPLII-1 |
| To: | |
| Monarque, S R, NRR/DORL, 415-1544 | |
| Shared Package | |
| ML062220140 | List: |
| References | |
| TAC MC8315, TAC MC8316 | |
| Download: ML062230114 (3) | |
Text
3.
This renewed license shall be deemed to contain and Is subject to the conditions specified In the following Commission regulations: 10 OFR Part 20, Section 30.34 of 10 CFR Part S0, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 7.0.32 of 10 CFR Part 70; and is subject to all.applicable provisions of the Act and the..
rules, regulations, and orders of the Commission now or hereafter In effect; and Is subject to the additional conditions specified below:
A.
Maximum Power Level The licensee Is authorized to operate the facility at steady state reactor core power levels not In excess of 2546 niegawatts (thermal).
B.
Technical Stecificatlions The Technical Specificatlons.contalhed In Appendix A, as revised through Amendment No. 249 are hereby Incorporated In the renewed license.
The licensee shall 6perate thb facility In accordance Wth the Technical Specificallons.
C.
Beoorts The licensee shall make certain reports In accordance with the requirements of the Technical Specifications.
D.
Records The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.
E.
Deleted bynAmendment 65 F.
Deleted by Amendment 71 G.
Deleted byAmendment 227 H.
Deleted byAmendment 227
- 1.
Rire.Prote ion The licenses shall Implemeht and maintain in effect the provisions of the approved Eire protection program as described In the Updated Final SatetyAnalysls Report and as approved In the SER dated September 19, 197%, (and Supplements dated May 29, 1980, October 9, 1980, December 18, 1980, February 13, 1981, December 4, 1981, April 27, 1982, November 1B, 1982, January 17, 1984, February 25, 1988, and Renewed License No. flPR-32 Amendment No. 249 E.
Pursuant to the Act and 10 OFR Parts 30 and 70, to possess, but not separate, such byproddct and special nuclear materials as may be produced by the operation of the facility.
. This renewed license shall be deemed to contain and Is subject to. the conditions.
specified In the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 OFR Part 30, Section 40.41 of 10"OFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 OFR Part 70; and Is subject to all applicable provislons of the Act and the rules, regulations, and orders of the Commission now or hereafter In effect; and Is subject to the additional conditions specified below:
A.
Maximum Power Level The licensee Is authorized to operate the facility at steady stale reaolor core power levels not In excess of 2546 megawatts (thermal).
B.
Technical Specifications The Te~hnlcal Sp.clfif3tions contained In Appendix A, as revised through Amendment No. 248 are hereby Incorporated In this renewed license.
The licensee shail operate the facllty In accordance with the Technical Specifications.
- 0.
Reports The licensee shall make certain reports In accordance wilh the requirements of the Technical Specifications.
D.
.. ecords The licensee shall keep factity operating records In accordance with the
.requirements of the Technical Specifications.
E.
Deleted by Amendment 54 F.
Deleted by Amendment 59 and Amendment 65 G.
Deleted by Amendment 227 H.
Deleted by Amendment 227 Renewed License No. DPR-37 Amendment No, 248
TS 5.1-1 5.0 DESIGN FEATURES 5.1 SITE Applicability Applies to the location and boundaries of the site for the Surry Power Station.
Obiective To define those aspects of the site which will affect the overall safety of the installation.
Specification The Surry Power Station is located in Surry County, Virginia, on property owned by Virginia Electric and Power Company on a point of land called Gravel Neck which juts into the James River. It is approximately 46 miles SE of Richmond, Virginia, 17 mniles NW of Newport News, Virginia, and 25 miles NW of Norfolk, Virginia. The site exclusion area boundary is defined by the site boundary line shown on the site map in TS Figure 5.1-1. The minimum distance from a reactor centerline to the site exclusion area boundary as defined in 10 CFR 100 is 1,650 ft. This is the distance for Unit 1, which is controlling.
References FSAR section 2.0 Site FSAR Section 2.1 General Description AmendmentNos. 249, 248