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MONTHYEARML0709300842007-03-29029 March 2007 Proposed Technical Specification Change Addition of Astrum Methodology to Core Operating Limits Report References and Revised Large Break LOCA Analysis Request for Additional Information Project stage: Request ML0721904822007-07-31031 July 2007 Proposed Technical Specifications Change Addition of Astrum Methodology to Core Operating Limits Report References and Revised Large Break LOCA Analysis Supplemental Information Project stage: Request ML0724906142007-09-0606 September 2007 Technical Specifications, Issuance of Amendments Regarding Use of Westinghouse Best-Estimate Large Break Loss-of-Coolant (TAC Nos. MD3609 & MD3610) Project stage: Approval ML0714300742007-09-0606 September 2007 License Amendment, Issuance of Amendments Regarding Use of Westinghouse Best-Estimate Large Break Loss-of-Coolant (TAC Nos. MD3609 & MD3610) Project stage: Approval 2007-07-31
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Category:Technical Specifications
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MF9124 and MF9125; EPID L-2017-LLA-0166) ML15245A4822015-10-0707 October 2015 Millstone Power Station, Surry Power Station, and North Anna Power Station - Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses ML14169A3592014-08-12012 August 2014 Stations, Units 1 and 2, Issuance of Amendments Regarding Addition of an Analytical Methodology to the Core Operating Limits Reports and an Increase to the Surry Minimum Temperature for Criticality ML14148A2352014-07-0303 July 2014 Issuance of Amendment to Extend the Containment Type a and Type C Leak Rate Test Frequency ML13260A2502013-09-0909 September 2013 Proposed License Amendment Request Regarding Relocation of Snubber Surveillance Requirements from Technical Specifications 4.17 to Snubber Program - Supplement ML12279A2822012-09-26026 September 2012 Proposed License Amendment Request Regarding Temporary Service Water Jumper to the Component Cooling Heat Exchangers ML12222A3402012-07-31031 July 2012 Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process ML12109A2702012-04-17017 April 2012 Issuance of Amendments Regarding Virginia Electric and Power Company License Amendment Request for Permanent Alternate Repair Criteria for Steam Generator Tube Inspection and Repair ML12081A0162012-03-14014 March 2012 Supplemental Response to Request for Additional Information Related to License Amendment Request for Permanent Alternate Repair Criteria for Steam Generator Tube Inspection and Repair ML1106602302011-03-0404 March 2011 Supplemental Information &Typed TS Pages for Proposed License Amendment Request Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirement to Licensee Controlled Program (Adoption of TSTF-425, Rev 3) ML1035502062010-12-16016 December 2010 Proposed Technical Specification Change Temporary Alternate Repair Criteria for Steam Generator Tube Repair for Unit 2 ML1030502732010-11-0202 November 2010 Correction to Amendment Regarding Technical Specification Revisions Related to the Measurement Uncertainty Recapture (Mur) Power Uprate ML1027203442010-09-28028 September 2010 Attachment 2 to Email Regarding Typed Page 2.3-2 for Surry Dnbcolr LAR ML1013106042010-05-0606 May 2010 License Amendment Request Revised Cumulative Core Burnup Applicability Limit for Heatup and Cooldown Curves, Low Temperature Overpressure Protection System Setpoint, and Ltops Enable Temperature ML1001405592010-02-26026 February 2010 License Amendment, Correction of Technical Specification Table 3.7.1 Operator Action 3.b ML0929606162009-10-16016 October 2009 Proposed License Amendment Request Relocation of Core Operating Limits to the Core Operating Limits Report (COLR) and Addition of COLR References ML0910401472009-04-13013 April 2009 Proposed License Amendment Request Correction to Technical Specification Table 3.7-1 Operator Action 3.b ML0822500262008-09-17017 September 2008 Units, 1 and 2, Tech Spec Pages for Amendments 261 and 261 Regarding the Revision to Various Setting Limits and the Overtemperature T/Overpower T Time Constants ML0817506992008-07-0707 July 2008 Tech Spec Pages for Amendments 260 & 260 Regarding Control Room Habitability ML0814200442008-06-17017 June 2008 Tech Spec Pages for Amendments 259 and 259, Regarding the Increase of Maximum Service Water Temperature Limit from 95 F to 100 F ML0813401152008-05-16016 May 2008 Technical Specifications - 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Text
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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