ML072490614

Technical Specifications, Issuance of Amendments Regarding Use of Westinghouse Best-Estimate Large Break Loss-of-Coolant (TAC Nos. MD3609 & MD3610)

ML072490614
Person / Time
Site:	Surry
Issue date:	09/06/2007
From:	NRC/NRR/ADRO/DORL/LPLII-1
To:
Lingam, Siva NRR/DORL 415-1564
Shared Package
ML071430067	List: ML071430074 ML072490614
References
TAC MD3609, TAC MD3610
Download: ML072490614 (3)

Text

.--

T.i renewed ic me shall be deemed to ontai Md k sdubJot to the conditions specfied Inthe f1obing Oommlson r ~la . 10 CR Part 10, Section 80.84 of 10 CFR Part s0, Section 40.41 of 10 IFI Pat 40, Secilons 50.54 amd05D9 of 10 O=: Part 50, and Secion 7.0.2 of 10 CFR Pad 7W; end Is subJc t to allapplble provisions ofIe At and Iw..

rules, regulallons, and orders of the Commission now or hereaflerin effect; and

-I-s-ubJd tdi-he-addit"ril Uons-di-il-d-b - -

A. Mxmm er Leve The IOsenee 1s aulhorized to operate the facy at steady state reactor core power levels not In excess of 26 nriegawatts (thermal).

B. TechrluesIoedloatlona The Todvftd Splbdko*s.contalhed InAppendbc A.as revised through Amendment No. 2 5 4 are hereby Incorporated Inthe renewed iconse.

The lcensea staeD operate thb facility inaccordance Wig1 the Technical

0. ReArld The icensee shaW make certain reports in accordance with the r"irements of the Technical SpecIicalon.

D. ,,o '.

The licensee shall keep facityoperatng records In accordance with the requirements of the Technical Specifications.

E. Deleted by Amendment 65 F. Deleted by Amendment 71 (1. Deleted by Amendment 227 Deleted by Amendment 227

1. .ire * ..:.f The licnsee slid Implemeit and maintain In effect the provisions of the approved Wire proteclon program as described In the Updated Final Safety Analsis Report and as approved Inthe SER dated September 19, 1979, (and Supplements dated May 29, 1980, October 9,1980, Dece-M I81990, FebSaiy-13,.1991.De ceber-4,-1981,-Ai--r 27,-7 1982, November lB, 1982, January17, 1984, Februafy 2S, 1988, and Renewed Ucense No. PPR-32 Amendment No. 254

E. Pursuant to the Act and 10 CFR Parts,0 and 70, to possess, but not separate, such byproddct and special nudlear materials as may be produced by the operaton of the facility.

U renewed license shae be deemed to contain and Is subjec tQ the conditions.

.his speclledIn theblowling Commlmsuon reguiations:-10a FR-Pad-.20,- -

Section 80.84 of 10 OFR Part 80, Section 40.41 of 1O0GFR Pat 40, Secilons 50.54 and 50.89 of 10 CFR Part 50, and Section 70.32 of 10 CFR Pat 70oand Is subject to a applicable pvons of the Act and eh rules, regutetlons, and orders of the Comiession now or hereafter Ineffect; and is subject to the additional conditions specified bebw.

A. f Power LAW Theiloensee Inauthorized to operate the fedty at steady folee reatr core power levels not Inexoess of 2548 megawatts (hera).

B. Technical Soeciflaattonu The Tehnlcul Speciftcatlons contained InAppendbc A,-as revied Ihrough Amendment No. 2 5 3 ie hereby Incorporated In this renewed Mese.

The licensee shau operate the facility Inaccordance with the Technical Specifications.

C. R82E211 The licensee shah make certain reports Inaccordance with the requirements of the Technical Spiedfloaloom.

D. .

The licensee shal keep facility operating records Inaccordance with the requirements of the Technical Speciflcations.

E. Deleted by Amendment 54 F. Deleted by Amendment 59 and Amendment 65 G. Deleted by Ameidment 227 H. Deleted by Amendment 227 Renewed License Amendment io,.No. DPR-37 253

TS 6.2-2 The analytical methods used to determine the core operating limits identified above shall be those previously reviewed and approved by the NRC, and identified below.

The COLR will contain the complete identification for each of the TS referenced topical reports used to prepare the COLR (i.e., report number, title, revision, date, and any supplements). The core operating limits-shall be determined so that applicable

....-- limits_(e.g.,_fuelthermal_-mechanicaLlimits,_corre thermal-hydraulic limits, ECCS_

limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided for information for each reload cycle to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

REFERENCES

1. VEP-FRD-42-A, "Reload Nuclear Design Methodology" 2a. WCAP- 16009-P-A, "Realistic Large Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM),"

(Westinghouse Proprietary).

2b. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," (W Proprietary) 2c. WCAP-10079-P-A, "NOTRUMP, A Nodal Transient Small Break and General Network Code," (W Proprietary) 2d. WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Report," (Westinghouse Proprietary) 3a. VEP-NE-2-A, "Statistical DNBR Evaluation Methodology" 3b. VEP-NE-3-A, "Qualification of the WRB-I CHF Correlation in the Virginia Power COBRA Code" Amendment Nos. 2 54 , 2 53