Letter Sequence Request |
|---|
|
|
MONTHYEARCNS-13-005, License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology2013-11-14014 November 2013
License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology
Project stage: Request
ML14010A3422014-01-14014 January 2014
Acceptance of Requested Licensing Action License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety
Project stage: Acceptance Review
ML14105A4842014-04-21021 April 2014
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML14128A3522014-05-22022 May 2014
RAI LAR Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology
Project stage: RAI
CNS-14-081, License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology (Proprietary) Response to NRC Request for Additional Information (RAI)2014-06-27027 June 2014
License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology (Proprietary) Response to NRC Request for Additional Information (RAI)
Project stage: Response to RAI
ML14295A4542014-10-24024 October 2014
RAI Information Regarding License Amendment Request Conditional Exemption of the End of Cycle Moderator Temperature Coefficient Measurement Methodology
Project stage: RAI
CNS-14-114, Units 1 & 2 - License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters - Response to NRC Request for Additional Information2014-11-10010 November 2014
Units 1 & 2 - License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters - Response to NRC Request for Additional Information
Project stage: Response to RAI
CNS-14-127, Proposed Technical Specifications (TS) Amendment TS 3.1.3, Moderator Temperature Coefficient (Mtc) TS 5.6.5, Core Operating Limits Report (Colr), License Amendment Request for Conditional Exemption of the End of Cycle (EOC) Mtc Measuremen2014-11-25025 November 2014
Proposed Technical Specifications (TS) Amendment TS 3.1.3, Moderator Temperature Coefficient (Mtc) TS 5.6.5, Core Operating Limits Report (Colr), License Amendment Request for Conditional Exemption of the End of Cycle (EOC) Mtc Measurement
Project stage: Request
ML14324A9682014-12-29029 December 2014
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML15035A5752015-03-17017 March 2015
Transmittal of Draft Safety Evaluation Regarding License Amendment Request Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology
Project stage: Draft Approval
ML15027A3662015-03-25025 March 2015
Issuance of Amendments DPC-NE-3001-P, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology
Project stage: Approval
2014-12-29
[Table View] |
Proposed Technical Specifications (TS) Amendment TS 3.1.3, Moderator Temperature Coefficient (Mtc) TS 5.6.5, Core Operating Limits Report (Colr), License Amendment Request for Conditional Exemption of the End of Cycle (EOC) Mtc Measurement| ML14332A301 |
| Person / Time |
|---|
| Site: |
Mcguire, Catawba, McGuire  |
|---|
| Issue date: |
11/25/2014 |
|---|
| From: |
Henderson K
Duke Energy Carolinas |
|---|
| To: |
Document Control Desk, Office of Nuclear Reactor Regulation |
|---|
| References |
|---|
| CNS-14-127, TAC MF3119, TAC MF3120, TAC MF3121, TAC MF3122 |
| Download: ML14332A301 (3) |
|
|
|---|
Category:Letter type:CNS
MONTHYEARCNS-18-008, License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing2018-07-19019 July 2018
License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing
CNS-18-032, Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report2018-07-12012 July 2018
Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report
CNS-18-031, Notice of Enforcement Discretion (NOED) Request2018-06-18018 June 2018
Notice of Enforcement Discretion (NOED) Request
CNS-18-028, 2017 Annual Radiological Environmental Operating Report2018-05-14014 May 2018
2017 Annual Radiological Environmental Operating Report
CNS-18-026, Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report2018-05-10010 May 2018
Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report
CNS-18-023, (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System2018-05-0808 May 2018
(Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System
CNS-18-025, Submittal of 2017 Annual Radioactive Effluent Release Report2018-04-30030 April 2018
Submittal of 2017 Annual Radioactive Effluent Release Report
CNS-18-022, Submittal of Emergency Plan Implementing Procedure2018-04-12012 April 2018
Submittal of Emergency Plan Implementing Procedure
CNS-18-017, Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-22018-03-24024 March 2018
Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-2
CNS-18-015, Commitment Change Evaluation Report for 20172018-03-22022 March 2018
Commitment Change Evaluation Report for 2017
CNS-18-005, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-02-0808 February 2018
Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes
CNS-18-006, Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days2018-01-23023 January 2018
Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days
CNS-17-058, Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukus2017-12-28028 December 2017
Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushi
CNS-17-061, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information2017-12-21021 December 2017
Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information
CNS-17-056, Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-22017-11-0101 November 2017
Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-2
CNS-17-056, Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-22017-10-23023 October 2017
Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-2
CNS-17-053, Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement2017-10-12012 October 2017
Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement
CNS-17-048, Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-1222017-09-29029 September 2017
Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-122
CNS-17-051, Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask2017-09-28028 September 2017
Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask
CNS-17-049, Submittal of Ufsar/Selected Licensee Commitment Changes Manual2017-09-28028 September 2017
Submittal of Ufsar/Selected Licensee Commitment Changes Manual
CNS-17-014, License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time2017-09-14014 September 2017
License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time
CNS-17-050, ISFSI - Registration of Spent Fuel Storage Cask2017-09-12012 September 2017
ISFSI - Registration of Spent Fuel Storage Cask
CNS-17-047, Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding2017-08-29029 August 2017
Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding
CNS-17-041, ISFSI - Registration of Spent Fuel Storage Cask2017-08-15015 August 2017
ISFSI - Registration of Spent Fuel Storage Cask
CNS-17-040, Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump2017-08-14014 August 2017
Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump
CNS-17-039, Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump2017-07-27027 July 2017
Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump
CNS-17-036, Mid-Cycle Power Uprate Ascension Startup Report2017-06-29029 June 2017
Mid-Cycle Power Uprate Ascension Startup Report
CNS-17-033, Technical Specification Bases Changes2017-06-27027 June 2017
Technical Specification Bases Changes
CNS-17-029, Flood Hazard Mitigating Strategies Assessment Report Submittal2017-06-20020 June 2017
Flood Hazard Mitigating Strategies Assessment Report Submittal
CNS-17-030, Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core2017-06-20020 June 2017
Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core
CNS-17-024, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations2017-05-25025 May 2017
Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations
CNS-17-031, Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report2017-05-24024 May 2017
Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report
CNS-17-027, Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report2017-05-10010 May 2017
Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report
CNS-17-015, Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report2017-04-27027 April 2017
Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report
CNS-17-021, Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days2017-04-20020 April 2017
Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days
CNS-17-020, Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing2017-04-11011 April 2017
Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing
CNS-17-008, Commitment Change Evaluation Report for 20162017-03-16016 March 2017
Commitment Change Evaluation Report for 2016
CNS-17-004, Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants.2017-01-26026 January 2017
Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants.
CNS-17-002, End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report2017-01-0606 January 2017
End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report
CNS-16-080, Submittal of Emergency Plan Implementing Procedure2016-12-20020 December 2016
Submittal of Emergency Plan Implementing Procedure
CNS-16-077, Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-12-0808 December 2016
Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
CNS-16-066, Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task..2016-10-20020 October 2016
Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task..
CNS-16-068, Submittal of Emergency Plan Implementing Procedure Revisions2016-10-10010 October 2016
Submittal of Emergency Plan Implementing Procedure Revisions
CNS-16-069, Submittal of Emergency Plan, Revision 16-22016-10-10010 October 2016
Submittal of Emergency Plan, Revision 16-2
CNS-16-064, License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 242016-09-0707 September 2016
License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 24
CNS-16-061, Submittal of Design Basis Specification for the Plant Fire Protection Revision 252016-08-12012 August 2016
Submittal of Design Basis Specification for the Plant Fire Protection Revision 25
CNS-16-051, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) an2016-08-0202 August 2016
License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) and
CNS-16-049, ISFSI Registration of Spent Fuel Storage Cask2016-07-14014 July 2016
ISFSI Registration of Spent Fuel Storage Cask
CNS-16-056, Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/00682016-07-13013 July 2016
Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/0068
CNS-16-050, Unit 2 - Ufsar/Selected Licensee Commitment Changes2016-07-12012 July 2016
Unit 2 - Ufsar/Selected Licensee Commitment Changes
2018-07-19
[Table view] |
Text
Kelvin Henderson Vice President
@ENERGY, Catawba Nuclear Station Duke Energy CNO1VP I 4800 Concord Road York, SC 29745 ATTACHMENT 1 TO THIS SUBMITTAL CONTAINS PROPRIETARY INFORMATION AND IS REQUESTED o: 803.701.4251 TO BE WITHHELD FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFR 2.390.
f: 803.701.3221 CNS-14-127 November 25, 2014 10 CFR 50.90 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Carolinas, LLC (Duke Energy)
Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414, Renewed Facility Operating License Nos. NPF-35 and NPF-52 McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370, Renewed Facility Operating License Nos. NPF-9 and NPF-17 Proposed Technical Specifications (TS) Amendment TS 3.1.3, "Moderator Temperature Coefficient (MTC)"
TS 5.6.5, "CORE OPERATING LIMITS REPORT (COLR)"
License Amendment Request for Conditional Exemption of the End of Cycle (EOC) MTC Measurement Methodology Response to NRC Request for Additional Information Dated October 24, 2014 (TAC Numbers MF3119, MF3120, MF3121, and MF3122)
References:
- 1. Letter from Duke Energy to NRC dated May 31, 2012
- 2. Letter from NRC to Duke Energy dated January 22, 2013
- 3. Letter from Duke Energy to NRC dated March 13, 2013
- 4. Letter from NRC to Duke Energy dated October 24, 2014 Reference 1 requested amendments to Catawba Renewed Facility Operating Licenses NPF-35 and NPF-52 and to McGuire Renewed Facility Operating Licenses NPF-9 and NPF-1 7 and the subject TS to modify the EOC MTC Surveillance Requirement (SR) by allowing an exemption to the SR if certain conditions are met. This conditional exemption from the SR will be determined on a cycle-specific basis. Reference 2 transmitted NRC Requests for Additional Information (RAIs) associated with the Reference 1 amendment request. Reference 3 transmitted Duke Energy's response to these RAIs. Reference 4 transmitted additional NRC RAIs associated with the Reference 1 amendment request. froOI www.duke-energy.com
U.S. Nuclear Regulatory Commission Page 2 November 25, 2014 ATTACHMENT 1 TO THIS SUBMITTAL CONTAINS PROPRIETARY INFORMATION AND IS REQUESTED TO BE WITHHELD FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFR 2.390.
The purpose of this letter is to respond to the additional NRC RAIs. Attachment 1 to this letter contains Duke Energy's responses. The format of Attachment 1 is to restate each RAI, followed by its associated response.
As Attachment 1 to this letter contains information proprietary to Duke Energy, it is supported by an affidavit signed by Duke Energy, the owner of the information. The attached affidavit (Attachment 2) sets forth the basis on which the information may be withheld from public disclosure by the NRC and address with specificity the considerations listed in paragraph (b)(4) of 10 CFR 2.390. Accordingly, it is requested that the information that is proprietary to Duke Energy be withheld from public disclosure in accordance with 10 CFR 2.390. Regarding the information that is proprietary to Duke Energy, correspondence with respect to the proprietary aspects of the information listed above or the supporting affidavit should reference the applicable Duke Energy Methodology Report number and should be addressed to the regulatory contact listed at the end of this letter.
The conclusions of the original regulatory evaluation and environmental consideration contained in Reference 1 are not impacted and continue to remain valid as a result of this RAI response.
There are no regulatory commitments contained in this letter or its attachments.
In accordance with 10 CFR 50.91, Duke Energy is notifying the applicable state officials of this RAI response by transmitting a copy of this letter and its non-proprietary attachment to the designated officials.
Should you have any questions concerning this information, please contact L.J. Rudy at (803) 701-3084.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on November 25, 2014.
Very truly yours, Kelvin Henderson Vice President, Catawba Nuclear Station LJR/s Attachments
U.S. Nuclear Regulatory Commission Page 3 November 25, 2014 ATTACHMENT 1 TO THIS SUBMITTAL CONTAINS PROPRIETARY INFORMATION AND IS REQUESTED TO BE WITHHELD FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFR 2.390.
xc (with all attachments):
V.M. McCree Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 G.A. Hutto, III Senior Resident Inspector (Catawba)
U.S. Nuclear Regulatory Commission Catawba Nuclear Station J. Zeiler Senior Resident Inspector (McGuire)
U.S. Nuclear Regulatory Commission McGuire Nuclear Station G.E. Miller (addressee only)
NRC Project Manager (Catawba and McGuire)
U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8-G9A 11555 Rockville Pike Rockville, MD 20852-2738 xc (with attachment 2 only):
S.E. Jenkins Manager Radioactive and Infectious Waste Management Division of Waste Management South Carolina Department of Health and Environmental Control 2600 Bull St.
Columbia, SC 29201 W.L. Cox, III Section Chief Division of Environmental Health Radiation Protection Section North Carolina Department of Health and Human Services 1645 Mail Service Center Raleigh, NC 27699