ML032450157
Letter Sequence Other | |
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TAC:MB7746, (Open) | |
Initiation
Administration | |
MONTHYEARML0325803892003-05-28028 May 2003
[Table View]Enclosure 2 - Responses to the NRC Request for Additional Information on the RFA-2 Licensing Submittal (WBN-TS-02-13) for the Watts Bar Nuclear Plant Project stage: Request ML0316106592003-06-0505 June 2003 Technical Specification (TS) Change No. TS-02-13 - Robust Fuel Assembly (RFA)-2 Upgrade - Response to NRC Request for Additional Information Project stage: Response to RAI ML0324501572003-08-21021 August 2003 Technical Specification (TS) Change No. TS-02-13 - Robust Fuel Assembly (RFA)-2 Upgrade - Revised Page Project stage: Other ML0327509252003-09-30030 September 2003 Tech Spec Pages for Amendment No. 46, Modifying TS 5.9.5 to Add Three Additional Methodologies in Support of the Westinghouse 17X17 Rf A-2 Fuel Design with Intermediate Flowmixers Project stage: Other 2003-06-05 |
ML032450157 | |
Person / Time | |
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Site: | Watts Bar |
Issue date: | 08/21/2003 |
From: | Pace P Tennessee Valley Authority |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
TAC MB7746, TS-02-13, TVA-WBN-TS-02-13 | |
Download: ML032450157 (5) | |
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Category:Letter
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Supplemental Response to Second-Round NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2 (WBN-TS-18-09) CNL-17-149, Revised Additional Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)2017-12-27027 December 2017 Revised Additional Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) ML17321A0332017-11-16016 November 2017 Additional Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) NL-17-128, Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23)2017-10-11011 October 2017 Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23) CNL-17-128, Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23)2017-10-11011 October 2017 Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23) CNL-17-123, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)2017-09-29029 September 2017 Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) CNL-17-044, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (Abgts), for Watts Bar Nuclear Plant, Units 1 and 22017-05-0505 May 2017 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (Abgts), for Watts Bar Nuclear Plant, Units 1 and 2 CNL-15-133, Response to Request for Additional Information Related to Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08)2015-07-15015 July 2015 Response to Request for Additional Information Related to Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08) CNL-15-088, Application to Revise Technical Specifications for Component Cooling Water Snd Essential Raw Cooling Water to Support Dual Unit Operation (TS-WBN-15-13)2015-06-17017 June 2015 Application to Revise Technical Specifications for Component Cooling Water Snd Essential Raw Cooling Water to Support Dual Unit Operation (TS-WBN-15-13) CNL-14-218, Application to Modify Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08)2015-04-0606 April 2015 Application to Modify Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08) CNL-15-001, Application to Revise Technical Specification 4.2.1, Fuel Assemblies, (WBN-TS-15-03)2015-03-31031 March 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies, (WBN-TS-15-03) ML14170A0462014-06-16016 June 2014 Attachment 2 - TS Bases Developmental Revision I Changes (Mark-Up) for WBN Unit 2 ML14170A0452014-06-16016 June 2014 Attachment 1 - TS Developmental Revision I Changes (Mark-Up) for WBN Unit 2 ML14170A0442014-06-16016 June 2014 Attachment 5 - WBN Unit 2 TS and Tsb Through Developmental Revision I, and Trm and Trmb Through Developmental Revision D ML11228A0472011-08-10010 August 2011 Technical Specifications (Developmental Revision F), Enclosure 1 ML1022900752010-08-16016 August 2010 Unit 2 - Change to Developmental TS Section 4.2.2, Control Rod Assemblies ML1005504412010-02-0202 February 2010 Developmental Revision B - Technical Specifications 2.0 - Safety Limits ML1005503672010-02-0202 February 2010 Developmental Revision B - Technical Specifications Table of Contents ML1005504742010-02-0202 February 2010 Developmental Revision B - Technical Specifications 5.0 - Administrative Controls ML1005504712010-02-0202 February 2010 Developmental Revision B - Technical Specifications 4.0 - Design Features ML1005504012010-02-0202 February 2010 Developmental Revision B - Technical Specifications 1.0 - Use and Application ML1005504472010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.0 - Limiting Condition for Operation (LCO) Applicability ML1005504642010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.9 - Refueling Operations ML1005504492010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.1 - Reactivity Control Systems ML1005504622010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.8 - Electrical Power Systems ML1005504612010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.7 - Plant Systems ML1005504502010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.2 - Power Distribution Limits ML1005504512010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.3 - Instrumentation ML1005504532010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.4 - Reactor Coolant System ML1005504562010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.5 - Emergency Core Cooling Systems ML1005504582010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.6 - Containment Systems ML0929503402009-10-20020 October 2009 License Amendment Request for Adoption of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 - Browns Ferry TS Change 469; Sequoyah Change 09-04; and Watts Change 09-19 ML0913205622009-04-30030 April 2009 Application for Technical Specification Change to Correct Minor Error in Amendment 70 ML0900900442008-12-31031 December 2008 Revised Technical Specifications Change WBN-TS-08-04 - Revision to the Maximum Number of TPBARS That Can Be Irradiated in the Reactor Core Per Cycle ML0831708612008-11-12012 November 2008 License Amendment Request TS-08-11 to Revise Reactor Coolant System Leakage Detection Systems - Exigent Change Request ML0712106042007-04-25025 April 2007 (WBN) Unit 1 - Technical Specification Change 07-01, Revision of Number of Tritium Producing Burnable Absorber Rods (TPBARS) in the Reactor Core ML0616502672006-06-12012 June 2006 Technical Specifications (TS) Change WBN-TS-05-10 - Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity - Request for Additional Information ML0526500612005-09-20020 September 2005 T.S. for License Amendment, Regarding Alternative Means for Monitoring Control or Shutdown Rod Position ML0509802082005-03-21021 March 2005 Tech Spec Pages for Amendment No. 57, Elimination of Monthly Report Requirement on Operating & Occupational Reports (TS-04-15) 2024-04-04 |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000
'AUG 21 2003 TVA-WBN-TS-02-13 U.S. Nuclear Regulatory Commission 10 CFR 50.90 ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:
In the Matter of ) Docket No. 50-390 Tennessee Valley Authority )
WATTS BAR NUCLEAR PLANT (WBN) - UNIT 1 - TECHNICAL SPECIFICATION (TS) CHANGE NO. TS-02 ROBUST FUEL ASSEMBLY (RFA)-2 UPGRADE - REVISED PAGE (TAC-MB7746)
Reference:
TVA Letter to NRC, 'WBN - UNIT 1 - Technical Specification (TS) Change No.
TS-02 Revise Section 5.9.5 to Incorporate Analytical Methods for Robust Fuel Assembly (RFA)-2 Upgrade," February 14, 2003.
The purpose of this letter is to provide a revised replacement page for the referenced TS amendment request, as recently discussed with NRC Staff. The revised page is provided in the Enclosure and replaces Page 7-6 in the Attachment (Safety Evaluation) of the referenced letter. This revision removes the description of TPBAR impact on post-LOCA subcriticality (last paragraph of Section 7.5.2.3), since the RFA-2 with 1FM fuel product is independent of this analysis. This change does not impact the "No Significant Hazards Criteria Evaluation" provided in the referenced amendment request.
There are no regulatory commitments associated with this submittal. If you have any questions about this proposed change, please contact me at (423) 365-1824.
Pnnled wecn d pap
U.S. Nuclear Regulatory Commission Page 2
'AUG 2 1 2003 I declare under penalty of perjury that the foregoing is true and correct. Executed on this 21st day of August. 2003.
Sincerely, P. .e Manager, Site Licensing and Industry Affairs Enclosure Robust Fuel Assembly (RFA)-2 Fuel Upgrade - TS-02-13 (TAC-MB7746) - Replacement Page cc: Seepage 3
U.S. Nuclear Regulatory Commission Page 3
'AUG 21 2003 cc (Enclosure):
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Ms. Margaret H. Chernoff, Project Manager U.S. Nuclear Regulatory Commission MS 08G9 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303
ENCLOSURE TENNESSEE VALLEY AUTHORITY WVATTS BAR NUCLEAR PLANT (WBN)
UNIT 1 DOCKET NO. 390 ROBUST FUEL ASSEMBLY (RFA)-2 FUEL UPGRADE - TS-02-13 (TAC-MB7746)
REPLACEMENT PAGE Remove Page 7-6, Revision 1, in the Attachment to TVA's February 14, 2003, Letter to NRC, and replace with the attached Page 7-6, Revision 2.
concentration was increased from 2400 ppm to 3500,ppm..--With the increases in minimum boron concentration in the RWST and accumulators, a new post-LOCA sump boron curve was calculated. This new curve will serve as the reload limit for future Watts Bar core designs.
The introduction of RFA-2 fuel has a negligible impact on the core reactivity and, therefore, has no effect on the post-LOCA subcriticality evaluation.
7.5.2A Hot Leg Switchover to Prevent Potential Boron Precipitation The hot leg switchover (HISO) procedure is initiated to preclude the possibility of boron precipitation in the reactor vessel core region following a LOCA. The key inputs to this calculation include:
- the maximum volumes and boron concentrations of the various sources of borated water which could arrive in the sump post-LOCA,
- the minimum volumes of various dilution sources which could arrive in the sump post-LOCA,
- the mixing volume of the core region in the vessel, and,
- the maximum core power level (prior to the LOCA).
For the implementation of TPBARs, the maximum RWST and accumulator boron concentrations were increased from 2700 ppm to 3800 ppm. With the increases in maximum boron concentration in the RWST and accumulators, a new HLSO time was calculated. The evaluation, which used the new RWST and accumulator boron concentrations and the Appendix K decay heat assumption, resulted in a HLSO time of 4.16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />, which was reduced to 3.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> for further margin to the boron precipitation limit. The minimum flow requirements were evaluated at the new hot leg switchover time. It was determined that the minimum flow requirements were satisfied for a HLSO time of 3.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. This calculation is applicable to both V5H and RFA-2 fuel types.
7-6 Rev. 21