NRC 2009-0087, License Amendment Request 258, Lncorporate Best Estimate Large Break Loss of Coolant Accident (LBLOCA) Analyses Using ASTRUM
| ML092590389 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/15/2009 |
| From: | Meyer L Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2009-0087 | |
| Download: ML092590389 (4) | |
Text
September 15, 2009 POINT BEACH NRC 2009-0087 10 CFR 50.90 U. S. Nuclear Regulatory Commission A n N : Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 License Amendment Request 258 lncor~orate Best Estimate Large Break Loss Of Coolant Accident (LBLOCA)
Analvses Using ASTRUM
References:
(I) FPL Energy Point Beach, LLC, Letter to NRC dated November 25, 2008, License Amendment Request 258, lncorporate Best Estimate Large Break Loss Of Coolant Accident (LOCA) Analyses Using ASTRUM (ML083330160)
(2)
FPL Energy Point Beach, LLC, Letter to NRC dated April 8, 2009, Supplement to License Amendment Request 258, lncorporate Best Estimate Large Break Loss Of Coolant Accident (LOCA) Analyses Using ASTRUM (ML091000170)
(3)
TSTF-363-A, Revision 0, "Revise Topical references in ITS 5.6.5, COLR Pursuant to 10 CFR 50.90, NextEra Energy Point Beach, LLC (NextEra), hereby submits a supplement to License Amendment Request (LAR) 258 for Point Beach Nuclear Plant (PBNP)
Units I and 2 (Reference I). The amendment requests use of NRC-approved WCAP-16009-P-A, Realistic Large Break LOCA Evaluation Methodology Using Automated Statistical Treatment of Uncertainty Method (ASTRUM), and revises Technical Specification (TS) 5.6.4.b to reference WCAP-I 6009-P-A.
In order to facilitate NRC staff review, NextEra is withdrawing the request to adopt Technical Specification Task Force (TSTF)-363-A (Reference 3) that was previously submitted in Reference (1).
Enclosure I provides a new TS markup that eliminates the previously proposed administrative changes to TS 5.6.4, Core Operating Limits Report (COLR), which would implement TSTF-363-A.
The information contained in this supplement does not further alter the proposed changes, the no significant hazards consideration contained in Reference (I), and continues to satisfy the criteria of 10 CFR 51.22 for categorical exclusion from the requirement for an environmental assessment previously provided in Reference (1).
NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241
Document Control Desk Page 2 In accordance with 10 CFR 50.91, a copy of this supplement is being provided to the designated Wisconsin Official.
This letter contains no new regulatory commitments and no revisions to existing regulatory commitments.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on this day, September 15, 2009.
Very truly yours, NextEra E n
w t
Beach, LLC Enclosures cc:
Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW
ENCLOSURE I NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS I AND 2 LICENSE AMENDMENT REQUEST 258 INCORPORATE BEST ESTIMATE LARGE BREAK LOSS OF COOLANT ACCIDENT (LBLOCA) ANALYSES USING ASTRUM PROPOSED REVISED TECHNICAL SPECIFICATION CHANGES (MARKUP COPY) 1 page follows
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.4 CORE OPERATING LIMITS REPORT (COLR) (continued)
(4)
WCAP-14787-P, Rev. 2, "Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wisconsin Electric Power Company Point Beach Units 1 & 2 (Fuel Upgrade &
Uprate to 1656 MWt-NSSS Power with Feedwater Venturis, or 1679 MWt-NSSS Power with LEFM on Feedwater Header)",
October, 2002 (approved by NRC Safety Evaluation, November 29, 2002).
(5)
WCAP-I 0054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using The NOTRUMP Code," August 1985.
(6)
WCAP-10054-P-A, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code:
Safety Injection into the Broken Loop and COSl Condensation Model," Addendum 2, Revision 1, July 1997.
(7)
WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"
September 1986.
(8)
WCAP-I 0216-P-A, "Relaxation of Constant Axial Offset Control," Revision IA, February 1994.
(9)
WCAP-10924-P-A, "Large Break LOCA Best Estimate Methodology, Volume 2: Application to Two-Loop PWRs Equipped with Upper Plenum Injection," and Addenda, December 1988. (cores not containing 422 V+ fuel)
(1 0)
WCAP-10924-P-A, "LBLOCA Best Estimate Methodology:
Model Description and Validation: Model Revisions," Volume 1, Addendum 4, August 1990. (cores not containing 422 V+ fuel)
( I 1) Caldon, Inc., Engineering Report-80P, "TOPICAL REPORT:
Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM JTM System," Revision 0, March 1997.
(1 2) Caldon, Inc., Engineering Report-I GOP, "Supplement to Topical Report ER-80P: Basis for a Power Uprate With the LEFMJTM System," Revision 0, May 2000.
(1 3) WCAP-16009 P "Reallstlc Larae-Break LOCA Evaluation ethodologv Uslna the Automated Stat~stlcal Treatment of Uncertaintv Method (ASTRUM)," Revls~on 0. Januarv 2005,
- c.
The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d.
The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC Point Beach 5.6-4 Unit I - Amendment No.
Unit 2 - Amendment No. Z W