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| {{#Wiki_filter:(-, DUKE CNS-17-040 August 14, 2017 U.S. Nuclear Regulatory Commission Attention: | | {{#Wiki_filter:Tom Simril |
| Document Control Desk Washington, D.C. 20555-0001 | | (-, DUKE Vice President Catawba Nuclear Station ENERGY~ |
| | Duke Energy CN01VP 14800 Concord Road York, SC 29745 o: 803.701.3340 I: 803.701 .3221 tom .simril@duke-energy.com CNS-17-040 10 CFR 50.55a August 14, 2017 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 |
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| ==Subject:== | | ==Subject:== |
| Duke Energy Carolinas, LLC (Duke Energy) Catawba Nuclear Station, Unit 1 Docket Number 50-413 Tom Simril Vice President Catawba Nuclear Station Duke Energy CN01VP 14800 Concord Road York, SC 29745 o: 803.701.3340 I: 803.701.3221 tom .simril@duke-energy | | Duke Energy Carolinas, LLC (Duke Energy) |
| .com 10 CFR 50.55a Withdrawal of lnservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for testing Chemical and Volume Control Pump
| | Catawba Nuclear Station, Unit 1 Docket Number 50-413 Withdrawal of lnservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for testing Chemical and Volume Control Pump |
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| ==Reference:== | | ==Reference:== |
| | Duke Energy letter CNS-17-039 to U.S. Nuclear Regulatory Commission, Catawba Nuclear Station, Unit 1, Request for Alternative Method to Establish New lnservice Testing Values fora Chemical and Volume Control Pump, dated July 27, 2017 (ADAMS Accession No. ML172088024) |
| | By letter dated July 27, 2017, Pursuant to 10 CFR 50.55a(z)(2), Duke Energy requested relief from ASME OMb-2006, Section ISTB-3320; specifically, the requirement in paragraph one, which states: *1f it is necessary or desirable, for some reason other than stated in ISTB-3310, to establish an additional set of reference values, a Group A or comprehensive test shall be run at the conditions of an existing set of reference values and the results analyzed. n On August 3, 2017, a conference call was held with the NRC to discuss whether relief was required. The first topic of discussion centered on whether ISTB-3320 imposed any specific requirements on timing or when the test at the conditions of the existing set of reference values had to be run. Catawba explained that based on the absence of more explicit detail in the requirements, it was taken that the test should be run immediately prior to the test at new reference values and this was the basis for Duke Energy requesting for relief. It was agreed during the call that the code does not explicitly state any time requirements and that previous Group A or Comprehensive tests may be analyzed to determine the current pump operation to be acceptable. |
| | Following the initial discussion on the timing aspect of ISTB-3320, discussion shifted to ISTB-3320(a) which discusses establishing an additional set of reference values using the pump curve established with Preservice Testing. Catawba explained that the code of record at the tom .simril@duke-energy .corn |
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| Duke Energy letter CNS-17-039 to U.S. Nuclear Regulatory Commission, Catawba Nuclear Station, Unit 1, Request for Alternative Method to Establish New lnservice Testing Values fora Chemical and Volume Control Pump, dated July 27, 2017 (ADAMS Accession No. ML172088024)
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| By letter dated July 27, 2017, Pursuant to 10 CFR 50.55a(z)(2), Duke Energy requested relief from ASME OMb-2006, Section ISTB-3320; specifically, the requirement in paragraph one, which states: *1f it is necessary or desirable, for some reason other than stated in ISTB-3310, to establish an additional set of reference values, a Group A or comprehensive test shall be run at the conditions of an existing set of reference values and the results analyzed.
| | ...... ..... - ----- .....-.-*---* ...... |
| n On August 3, 2017, a conference call was held with the NRC to discuss whether relief was required.
| | U.S. Nuclear Regulatory Commission CNS-17-040 August14, 2017 Page 2 time of installation of NV Pump 1A did not require a Preservice Test with a minimum of five points. Furthermore, Catawba explained that a four point head curve was performed to satisfy system requirements after installation and that a "shop curve" of 10 points was performed by the manufacturer at their facilities prior to shipment to Catawba. The two curves were in close agreement in the flow range considered for the new reference value (-150-160 gpm). Catawba will use these curves to establish the new reference values and will run a test in accordance with ISTB-3320 to verify the new reference values before their implementation. |
| The first topic of discussion centered on whether ISTB-3320 imposed any specific requirements on timing or when the test at the conditions of the existing set of reference values had to be run. Catawba explained that based on the absence of more explicit detail in the requirements, it was taken that the test should be run immediately prior to the test at new reference values and this was the basis for Duke Energy requesting for relief. It was agreed during the call that the code does not explicitly state any time requirements and that previous Group A or Comprehensive tests may be analyzed to determine the current pump operation to be acceptable.
| | Conclusion of the call and discussion was that relief from the code requirements was not required. As a result, Duke Energy is hereby withdrawing CNS relief request 17-CN-002. |
| Following the initial discussion on the timing aspect of ISTB-3320, discussion shifted to ISTB-3320(a) which discusses establishing an additional set of reference values using the pump curve established with Preservice Testing. Catawba explained that the code of record at the tom .simril@duke-energy .corn U.S. Nuclear Regulatory Commission CNS-17-040 August14, 2017 Page 2 ...... _ ..... -------..... -.-*---* ...... time of installation of NV Pump 1A did not require a Preservice Test with a minimum of five points. Furthermore, Catawba explained that a four point head curve was performed to satisfy system requirements after installation and that a "shop curve" of 10 points was performed by the manufacturer at their facilities prior to shipment to Catawba. The two curves were in close agreement in the flow range considered for the new reference value (-150-160 gpm). Catawba will use these curves to establish the new reference values and will run a test in accordance with ISTB-3320 to verify the new reference values before their implementation.
| | There are no regulatory commitments contained in this letter. |
| Conclusion of the call and discussion was that relief from the code requirements was not required. | | If you have any questions regarding this submittal, please contact Tolani E. Owusu at (803) 701-5385. |
| As a result, Duke Energy is hereby withdrawing CNS relief request 17-CN-002. | | Sincerely, Tom Simril Vice President, Catawba Nuclear Station |
| There are no regulatory commitments contained in this letter. If you have any questions regarding this submittal, please contact Tolani E. Owusu at (803) 701-5385. | | |
| Sincerely, Tom Simril Vice President, Catawba Nuclear Station U.S. Nuclear Regulatory Commission CNS-17-040 August 14, 2017 Page3 XC: (with Enclosure) | | U.S. Nuclear Regulatory Commission CNS-17-040 August 14, 2017 Page3 XC: (with Enclosure) |
| C. Haney, Regional Administrator U.S. Nuclear Regulatory Commission | | C. Haney, Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 J. D. Austin, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station M. Mahoney, NRC Project Manager (Catawba) |
| -Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 J. D. Austin, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station M. Mahoney, NRC Project Manager (Catawba) | | U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mailstop 0-8H4A Rockville, MD 20852-2738 S. E. Jenkins, Manager S.C DHEC Radioactive & Infectious Waste Management jenkinse@dhec.sc.gov}} |
| U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mailstop 0-8H4A Rockville, MD 20852-2738 S. E. Jenkins, Manager S.C DHEC Radioactive | |
| & Infectious Waste Management jenkinse@dhec.sc.gov}} | |
Letter Sequence Withdrawal |
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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-17-049, Submittal of Ufsar/Selected Licensee Commitment Changes Manual2017-09-28028 September 2017 Submittal of Ufsar/Selected Licensee Commitment Changes Manual 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-17-014, 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-16-069, Submittal of Emergency Plan, Revision 16-22016-10-10010 October 2016 Submittal of Emergency Plan, Revision 16-2 CNS-16-068, Submittal of Emergency Plan Implementing Procedure Revisions2016-10-10010 October 2016 Submittal of Emergency Plan Implementing Procedure Revisions 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
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Text
Tom Simril
(-, DUKE Vice President Catawba Nuclear Station ENERGY~
Duke Energy CN01VP 14800 Concord Road York, SC 29745 o: 803.701.3340 I: 803.701 .3221 tom .simril@duke-energy.com CNS-17-040 10 CFR 50.55a August 14, 2017 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke Energy)
Catawba Nuclear Station, Unit 1 Docket Number 50-413 Withdrawal of lnservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for testing Chemical and Volume Control Pump
Reference:
Duke Energy letter CNS-17-039 to U.S. Nuclear Regulatory Commission, Catawba Nuclear Station, Unit 1, Request for Alternative Method to Establish New lnservice Testing Values fora Chemical and Volume Control Pump, dated July 27, 2017 (ADAMS Accession No. ML172088024)
By letter dated July 27, 2017, Pursuant to 10 CFR 50.55a(z)(2), Duke Energy requested relief from ASME OMb-2006, Section ISTB-3320; specifically, the requirement in paragraph one, which states: *1f it is necessary or desirable, for some reason other than stated in ISTB-3310, to establish an additional set of reference values, a Group A or comprehensive test shall be run at the conditions of an existing set of reference values and the results analyzed. n On August 3, 2017, a conference call was held with the NRC to discuss whether relief was required. The first topic of discussion centered on whether ISTB-3320 imposed any specific requirements on timing or when the test at the conditions of the existing set of reference values had to be run. Catawba explained that based on the absence of more explicit detail in the requirements, it was taken that the test should be run immediately prior to the test at new reference values and this was the basis for Duke Energy requesting for relief. It was agreed during the call that the code does not explicitly state any time requirements and that previous Group A or Comprehensive tests may be analyzed to determine the current pump operation to be acceptable.
Following the initial discussion on the timing aspect of ISTB-3320, discussion shifted to ISTB-3320(a) which discusses establishing an additional set of reference values using the pump curve established with Preservice Testing. Catawba explained that the code of record at the tom .simril@duke-energy .corn
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U.S. Nuclear Regulatory Commission CNS-17-040 August14, 2017 Page 2 time of installation of NV Pump 1A did not require a Preservice Test with a minimum of five points. Furthermore, Catawba explained that a four point head curve was performed to satisfy system requirements after installation and that a "shop curve" of 10 points was performed by the manufacturer at their facilities prior to shipment to Catawba. The two curves were in close agreement in the flow range considered for the new reference value (-150-160 gpm). Catawba will use these curves to establish the new reference values and will run a test in accordance with ISTB-3320 to verify the new reference values before their implementation.
Conclusion of the call and discussion was that relief from the code requirements was not required. As a result, Duke Energy is hereby withdrawing CNS relief request 17-CN-002.
There are no regulatory commitments contained in this letter.
If you have any questions regarding this submittal, please contact Tolani E. Owusu at (803) 701-5385.
Sincerely, Tom Simril Vice President, Catawba Nuclear Station
U.S. Nuclear Regulatory Commission CNS-17-040 August 14, 2017 Page3 XC: (with Enclosure)
C. Haney, Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 J. D. Austin, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station M. Mahoney, NRC Project Manager (Catawba)
U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mailstop 0-8H4A Rockville, MD 20852-2738 S. E. Jenkins, Manager S.C DHEC Radioactive & Infectious Waste Management jenkinse@dhec.sc.gov