Letter Sequence RAI |
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MONTHYEARCP-201201212, Spent Fuel Pool Criticality Analysis2012-10-0909 October 2012
Spent Fuel Pool Criticality Analysis
Project stage: Request
CP-201300257, License Amendment Request (LAR) 13-01, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage, 4.3, Fuel Storage, and 5.5 Programs & Manuals2013-03-28028 March 2013
License Amendment Request (LAR) 13-01, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage, 4.3, Fuel Storage, and 5.5 Programs & Manuals
Project stage: Request
ML13175A2252013-06-27027 June 2013
Supplemental Information Needed for Acceptance of Application to Revise TS 3.7.16, Fuel Storage Pool Boron Concentration, TS 3.7.17, Spent Fuel Assembly Storage, and TS 5.5, Programs and Manuals
Project stage: Acceptance Review
CP-201300826, Supplemental Information Supporting LAR 13-01, Spent Pool Criticality Analysis2013-07-16016 July 2013
Supplemental Information Supporting LAR 13-01, Spent Pool Criticality Analysis
Project stage: Supplement
ML13253A0052013-09-11011 September 2013
Acceptance Review Following Supplement, Amendment Request to Revise TS 3.7.16, Fuel Storage Pool Boron Concentration, TS 3.7.17, Spent Fuel Assembly Storage, and TS 5.5, Programs and Manuals
Project stage: Acceptance Review
ML13253A0062013-09-26026 September 2013
Request for Withholding Information from Public Disclosure, 3/18/13 Affidavit Executed by J. Gresham, Westinghouse Regarding WCAP-17728-P, Revision 0
Project stage: Withholding Request Acceptance
CP-201301215, License Amendment Request (LAR) 13-01 Supplement Spent Fuel Pool Criticality Analysis Removal Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage, 4.32013-10-22022 October 2013
License Amendment Request (LAR) 13-01 Supplement Spent Fuel Pool Criticality Analysis Removal Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage, 4.3
Project stage: Supplement
ML13309A0272013-10-31031 October 2013
WCAP-17728-NP, Rev. 1, Comanche Peak Nuclear Power Plant Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis
Project stage: Other
ML13301A6452013-11-0505 November 2013
Redacted, Request for Additional Information, Amendment Request to Revise TS 3.7.16, Fuel Storage Pool Boron Concentration, TS 3.7.17, Spent Fuel Assembly Storage, and TS 5.5, Programs and Manuals
Project stage: RAI
ML13317B7032013-11-19019 November 2013
Non-proprietary, Request for Additional Information Round 2, Amendment Request to Revise TS 3.7.16, Fuel Storage Pool Boron Concentration, TS 3.7.17, Spent Fuel Assembly Storage, and TS 5.5, Programs and Manuals
Project stage: RAI
CP-201301332, License Amendment Request (LAR) 13-01 Supplement Spent Fuel Pool Criticality Analysis Removal Technical Specifications 3.7.17, Spent Fuel Assembly Storage,4.3, Fuel Storage, and 5.5 Programs and Manuals2013-11-26026 November 2013
License Amendment Request (LAR) 13-01 Supplement Spent Fuel Pool Criticality Analysis Removal Technical Specifications 3.7.17, Spent Fuel Assembly Storage,4.3, Fuel Storage, and 5.5 Programs and Manuals
Project stage: Supplement
ML14016A1242013-12-17017 December 2013
License Amendment Request (LAR) 13-01 Spent Fuel Pool Criticality Analysis, Response to Requests for Additional Information Round 2
Project stage: Response to RAI
ML14027A7052013-12-17017 December 2013
Responses to LAR 13-01 Request for Additional Information (RAI) - Round 2
Project stage: Request
CP-201301411, Response to Requests for Additional Information Round 2, on License Amendment Request (LAR) 13-01 Spent Fuel Pool Criticality Analysis,2013-12-17017 December 2013
Response to Requests for Additional Information Round 2, on License Amendment Request (LAR) 13-01 Spent Fuel Pool Criticality Analysis,
Project stage: Response to RAI
ML14015A5472014-01-15015 January 2014
NRR E-mail Capture - Request for Additional Information - License Amendment Request 13-01 to Revise Technical Specifications 3.7.16, 3.7.17, 4.3 and 5.5 - TACs MF1365 and MF1366
Project stage: RAI
CP-201400074, License Amendment Request (LAR) 13-01 Spent Fuel Pool Criticality Analysis, Response to Request for Additional Information2014-01-16016 January 2014
License Amendment Request (LAR) 13-01 Spent Fuel Pool Criticality Analysis, Response to Request for Additional Information
Project stage: Response to RAI
ML14007A0392014-02-0606 February 2014
Request for Withholding Information from Public Disclosure - 11/22/13 Affidavit Executed by J. Gresham, Westinghouse Responses to 11/5/13 NRC Requests for Additional Information
Project stage: RAI
ML14058A0892014-02-27027 February 2014
Request for Additional Information Round 3, Amendment Request to Revise TS 3.7.16, Fuel Storage Pool Boron Concentration, TS 3.7.17, Spent Fuel Assembly Storage, and TS 5.5, Programs and Manuals
Project stage: RAI
ML14022A0462014-03-19019 March 2014
Request for Withholding Proprietary Information from Public Disclosure
Project stage: Other
ML13318A0292014-03-19019 March 2014
Request for Withholding Information from Public Disclosure, 10/14/13 Affidavit Executed by J. Gresham, Westinghouse Regarding WCAP-17728-P, Revision 1
Project stage: Withholding Request Acceptance
ML14097A5132014-04-0707 April 2014
NRR E-mail Capture - Request for Additional Information - License Amendment Request for Spent Fuel Pool Criticality Analysis - TACs MF1365 and MF1366
Project stage: RAI
CP-201400503, Response to Requests for Additional Information on License Amendment Request 13-01 Spent Fuel Pool Criticality Analysis2014-04-17017 April 2014
Response to Requests for Additional Information on License Amendment Request 13-01 Spent Fuel Pool Criticality Analysis
Project stage: Response to RAI
CP-201400619, License Amendment Request (LAR) 13.01, Spent Fuel Pool Criticality Analysis, Supplemental Information to Requests for Additional Information2014-05-0101 May 2014
License Amendment Request (LAR) 13.01, Spent Fuel Pool Criticality Analysis, Supplemental Information to Requests for Additional Information
Project stage: Supplement
ML14150A1382014-06-30030 June 2014
Request for Withholding Information from Public Disclosure - 7/12/13 Affidavit Executed by B. Maurer, Westinghouse; Supplemental Information Supporting Amendment Request Question 1, 2, and 4 (TAC MF1365-MF1366)
Project stage: Withholding Request Acceptance
ML14150A1422014-06-30030 June 2014
Request for Withholding Information from Public Disclosure - 4/17/14 Affidavit Executed by J. Gresham, Westinghouse; Responses to Request for Additional Information SFP Configuration Interfaces (TAC MF1365-MF1366)
Project stage: RAI
ML14160A0352014-07-0101 July 2014
Redacted, Issuance of Amendment No. 162, Revise TS 3.7.16, Fuel Storage Pool Boron Concentration, TS 3.7.17, Spent Fuel Assembly Storage, and TS 5.5, Programs and Manuals
Project stage: Approval
2013-09-11
[Table View] |
Text
Mr. Rafael Flores Senior Vice President and Chief Nuclear Officer UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 27, 2014 Attention: Regulatory Affairs Luminant Generation Company LLC P.O. Box 1002 Glen Rose, TX 76043
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING REVISED TECHNICAL SPECIFICATIONS 3.7.16, "FUEL STORAGE POOL BORON CONCENTRATION,"
- 3. 7.17, "SPENT FUEL ASSEMBLY STORAGE," 4.3, "FUEL STORAGE," AND 5.5, "PROGRAMS AND MANUALS" (TAC NOS. MF1365 AND MF1366)
Dear Mr. Flores:
By letter dated March 28, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13095A023), as supplemented by letters dated July 16, October 22, November 26, and December 17, 2013(ADAMS Accession Nos. ML13205A056, ML13309A026, ML13346A175, and ML14016A124, respectively), and January 16, 2014 (ADAMS Accession No. not available at this time)) Luminant Generation Company LLC (the licensee) submitted a license amendment request for revision to the Facility Operating License Nos. NPF-87 and NPF-89 for Comanche Peak Nuclear Power Plant (CPNPP), Units 1 and 2, respectively. The amendment also seeks revision of the CPNPP, Units 1 and 2, Technical Specifications based on an updated criticality analysis methodology for the spent fuel pool.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your application and determined that additional information is required in order to complete its review. A draft copy of the enclosed request for additional information (RAI) was provided to Mr. Jimmy Seawright of your staff via e-mail on February 12, 2014. An RAI clarification call was held on February 20, 2014. The licensee agreed to provide the RAI response within 60 days from the date of the call.
If you have any questions, please contact me at 301-415-3016 or balwant.singal@nrc.gov.
Docket Nos. 50-445 and 50-446
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv Sincerely,
-Bo<:.O. ~~ ~
~-?---
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
REQUEST FOR ADDITIONAL INFORMATION REGARDING REVISED TECHNICAL SPECIFICATIONS 3.7.16, "FUEL STORAGE POOL BORON CONCENTRATION," 3. 7.17, "SPENT FUEL ASSEMBLY STORAGE,"
4.3, "FUEL STORAGE," AND 5.5, "PROGRAMS AND MANUALS" LUMINANT GENERATION COMPANY LLC COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446 By letter dated March 28, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13095A023), as supplemented by letters dated July 16, October 22, November 26, and December 17, 2013 (ADAMS Accession Nos. ML13205A056, ML13309A026, ML13346A175, and ML14016A124, respectively), and January 16, 2014 (ADAMS Accession No. not available at this time)) Luminant Generation Company LLC (the licensee) submitted a license amendment request for revision to the Facility Operating License Nos. NPF-87 and NPF-89 for Comanche Peak Nuclear Power Plant (CPNPP), Units 1 and 2, respectively. The amendment also seeks revision of the CPNPP, Units 1 and 2, Technical Specifications based on an updated criticality analysis methodology for the spent fuel pool (SFP).
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your application and determined that the following additional information is required in order to complete its review.
Request for Additional Information {RAI)
- 1.
WCAP-17728-P (Enclosure 2 to letter dated March 28, 2013) indicates that periodic boundary conditions are used for all storage array models in the x-y plane including Array 11-A. The NRC staff believes that using a periodic boundary condition for the x-direction would be inappropriate as it would be simulating a water/wall boundary condition for Array 11-B which is required to border Array 11-A. Please describe the boundary conditions were used in the Array II-A analysis for normal, accident, and interface conditions.
- 2.
Please describe how the interface conditions were modeled for all of the Region I and Region II interface calculations. Please also describe how many of each array were modeled in the x-y plane and what boundary conditions were used.
Enclosure
- 3.
It appears that the methodology used in WCAP-17728-P for addressing the interface between rack designs, between storage arrays within a rack design, and within a storage array itself are not consistent with the guidance in Interim Staff Guidance (ISG) DSS ISG-201 0-01, "Staff Guidance Regarding the Nuclear Criticality Safety Analysis for Spent Fuel Pools" (ADAMS Accession No. ML110620086), which states, in part, that Absent a determination of a set of biases and uncertainties specifically for the combined interface model, use of the maximum biases and uncertainties from the individual storage configurations should be acceptable in determining whether the keff of the combined interface model meets the regulatory requirements.
Please either revise the analysis to be consistent with DSS ISG-2010-01 or provide the justification for the methodology used in WCAP-17728-P, including the results of the analyses performed to support that methodology. Also, please include the analysis results for the Array II-A and Array 1-A interface calculation.
- 4.
WCAP-17728-P uses the FIGHTH code in the criticality safety analysis to determine the fuel assembly axial and radial temperature distribution used in the depletion analysis.
Please justify the use of FIGHTH for this application and explicitly explain how fuel thermal conductivity degradation is addressed. If FIGHTH is NRC-approved for this application, please cite the reference and address any limitations.
- ML14058A089
- via email OFFICE NRR/DORLILPL4-1/PM NRR/DORL/LPL4-1/LA*
NRR/DSS/SRXB/BC NAME BSingal JBurkhardt CJackson DATE 2/27/14 2/27/14 2/27/14 OFFICE NRR/DORLILPL4-1/BC NRR/DORLILPL4-1/PM NAME MMarkley (Flyon for)
BSingal DATE 2/27/14 2/27/14
