ML19296D119
| ML19296D119 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/31/2020 |
| From: | Michael Mahoney Plant Licensing Branch II |
| To: | Simril R Duke Energy Carolinas |
| Mahoney M | |
| References | |
| EPID L-2019-LLA-0191 | |
| Download: ML19296D119 (14) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 31, 2020 Mr. Tom Simril Site Vice President Catawba Nuclear Station, Units 1 and 2 Duke Energy Carolinas, LLC 4800 Concord Road York, SC 29745
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 ISSUANCE OF AMENDMENT NOS. 305 AND 301 TO REVISE TECHNICAL SPECIFICATION 3.0, "SURVEILLANCE REQUIREMENT (SR) APPLICABILITY" (EPID L-2019-LLA-0191)
Dear Mr. Simril:
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment Nos. 305 and 301 to Renewed Facility Operating License Nos. NPF-35 and NPF-52 for the Catawba Nuclear Station, Units 1 and 2, respectively. The amendments revise the Technical Specifications (TSs) in response to the application from Duke Energy Carolinas, LLC (the licensee) dated September 4, 2019. The amendments correct an editorial error in TS 3.0, "Surveillance Requirement (SR) Applicability," that was introduced in SR 3.0.5 by the issuance of Amendment Nos. 235 and 231.
Specifically, existing SR 3.0.5 incorrectly refers to Limiting Condition for Operation (LCO) 3.0.8 (LCO applicability when one or more required snubbers are unable to perform their associated support function). The amendments correct SR 3.0.5 to refer to LCO 3.0.9 {exceptions to LCOs and Actions applying to each unit individually).
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
If you have any questions, please contact me at 301-415-3867 or Michael.Mahoney@nrc.gov.
Docket Nos. 50-413 and 50-414
Enclosures:
- 1. Amendment No. 305 to NPF-35
- 2. Amendment No. 301 to NPF-52
- 3. Safety Evaluation cc: Listserv Since,jly, j
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Michael Mahoney, Proje Manager Plant Licensing Branc 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS. LLC DOCKET NO. 50-413 CATAWBA NUCLEAR STATION. UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 305 Renewed License No. NPF-35
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility), Renewed Facility Operating License No. NPF-35, filed by Duke Energy Carolinas, LLC (licensee), dated September 4, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-35 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 305 which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 120 days of issuance.
Attachment:
FOR THE NUCLEAR REGULATORY COMMISSION
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Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Changes to the Renewed License No. NPF-35 and TechnicalSpecifications Date of Issuance: January 31, 2020
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 301 Renewed License No. NPF-52
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility), Renewed Facility Operating License No. NPF-52, filed by Duke Energy Carolinas, LLC (licensee), dated September 4, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and {ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-52 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 301 which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 120 days of issuance.
Attachment:
FOR THE NUCLEAR REGULATORY COMMISSION
- 1
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Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Changes to the Renewed License No. NPF-52 and Technical Specifications Date of Issuance: January 31, 2020
ATTACHMENT AMENDMENT NO. 305 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-35 AMENDMENT NO. 301 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-52 CATAWBA NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 Operating Licenses Replace the following pages of the Renewed Facility Operating Licenses with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove NPF-35, page 4 NPF-52, page 4 Insert NPF-35, page 4 NPF-52, page 4 Appendix A, "Technical Specifications," of Operating Licenses Replace the following page of the Appendix A Technical Specifications (TSs) with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Remove 3.0-6 Insert 3.0-6 (2)
Technical Specifications The Technical Specifications contained in Appendix A. as revised through Amendment No. 305 which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC shall operate the facility in accordance with the Technical Specifications.
(3)
Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation. Duke shall complete these activities no later than December 6, 2024, and shall notify the NRG in writing when implementation of these activities is complete and can be verified by NRG inspection.
The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4),
following issuance of this renewed operating license. Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 1 O CFR 50.59 and otherwise complies with the requirements in that section.
(4)
Antitrust Conditions (5)
Duke Energy Carolinas, LLC shall comply with the antitrust conditions delineated in Appendix C to this renewed operating license.
Fire Protection Program Duke Energy Carolinas, LLC shall implement and maintain in effect all provisions of the approved fire protection program that complies with 1 O CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment request dated September 25, 2013; as supplemented by letters dated January 13, 2015; January 28, 2015; February 27, 2015; March 30, 2015; April 28, 2015; July 15, 2015; August 14, 2015; September 3, 2015; December 11, 2015; January 7, 2016; March 23, 2016; June 15, 2016; August 2, 2016; September 7, 2016; and, January 26, 2017, as approved in the SE dated February 8, 2017. Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c),
the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.
Renewed License No. NPF-35 Amendment No. 305
(2)
(3) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 301 which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC shall operate the facility in accordance with the Technical Specifications.
Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation. Duke shall complete these activities no later than December 6, 2024, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4),
following issuance of this renewed operating license. Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change.
pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
(4)
Antitrust Conditions (5)
Duke Energy Carolinas, LLC shall comply with the antitrust conditions delineated in Appendix C to this renewed operating license.
Fire Protection Program Duke Energy Carolinas, LLC shall implement and maintain in effect all provisions of the approved fire protection program that complies with 1 O CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment request dated September 25, 2013; as supplemented by letters dated January 13, 2015; January 28, 2015; February 27, 2015; March 30, 2015; April 28, 2015; July 15, 2015; August 14, 2015; September 3, 2015; December 11, 2015; January 7, 2016; March 23, 2016; June 15, 2016; August 2, 2016; September 7, 2016; and, January 26, 2017, as approved in the SE dated February 8, 2017. Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c),
the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.
Renewed License No. NPF-52 Amendment No. 301
SR Applicability 3.0 3.0 SR APPLICABILITY (continued)
SR 3.0.4 SR 3.0.5 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4 This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.
Surveillance Requirements shall apply to each unit individually unless otherwise indicated as stated in LCO 3.0.9 for individual Specifications or whenever certain portions of a Specification contain surveillance parameters different for each unit, which will be identified in parentheses or footnotes.
Catawba Units 1 and 2 3.0-6 Amendment Nos. 305/301
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 305 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-35 AND AMENDMENT NO. 301 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-52 DUKE ENERGY CAROLINAS. LLC CATAWBA NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414
1.0 INTRODUCTION
By letter dated September 4, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML19247B321), Duke Energy Carolinas, LLC {the licensee) submitted a license amendment request to change the Technical Specifications (TSs) for the Catawba Nuclear Station (Catawba), Units 1 and 2. The amendments correct an editorial error in Technical Specification (TS) 3.0, "Surveillance Requirement [SR)," that was introduced in SR 3.0.5 by the issuance of Amendment Nos. 235 and 231. Specifically, existing SR 3.0.5 refers incorrectly to Limiting Condition for Operation (LCO) 3.0.8 (LCO applicability when one or more required snubbers are unable to perform their associated support function). Instead, SR 3.0.5 is proposed to be re-numbered to refer to LCO 3.0.9 (exceptions to LCOs and Actions applying to each unit individually).
2.0 REGULATORY EVALUATION
2.1 Description of Proposed Changes Current TS SR 3.0.5 is as follows:
Surveillance Requirements shall apply to each unit individually unless otherwise indicated as stated in LCO 3.0.8 for individual Specifications or whenever certain portions of a Specification contain surveillance parameters different for each unit, which will be identified by parentheses or footnotes.
Revised TS SR 3.0.5 would state (deletions are shown in double strike-out and additions shown in underlined text):
Surveillance Requirements shall apply to each unit individually unless otherwise indicated as stated in LCO 3.0.S~ for individual Specifications or whenever certain portions of a Specification contain surveillance parameters different for each unit, which will be identified by parentheses or footnotes.
2.2 Applicable Regulations and Guidance In Title 10 of the Code of Federal Regulations (CFR) 50.36, the Commission established its regulatory requirements related to the content of TSs. Pursuant to 10 CFR 50.36(c), TS are required to include items in the following categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; (3) Surveillance Requirements (SRs); (4) design features; and (5) administrative controls.
3.0 TECHNICAL EVALUATION
3.1 Change to SR 3.0.5 By letter dated March 19, 2007 (ADAMS Accession Package No. ML063100443), the NRC approved license Amendment Nos. 235 and 231, which added a new TS Limiting Condition for Operation (LCO) 3.0.8. The existing TS LCO 3.0.8 at that time was renumbered to TS LCO 3.0.9. However, the corresponding change to SR 3.0.5, which referenced the old TS LCO 3.0.8 {the current TS LCO 3.0.9) was missed inadvertenatly.
The proposed change to SR 3.0.5 would correct the above editorial error to refer to LCO 3.0.9 instead of the referencing to the current LCO 3.0.8 in SR 3.0.5. The proposed change does not affect compliance with 1 O CFR 50.36 and will ensure that the necessary quality of systems and components is maintained, the facility operation is within safety limits and that the limiting conditions for operation will be met. Therefore, the NRC staff concludes that the proposed change corrects an editorial error and does not affect the no significant hazards considerations published for license Amendment Nos. 235 and 251, and is, therefore, acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the NRC staff notified the South Carolina State official on January 9, 2020 of the proposed issuance of the amendments. The NRC staff confirmed on January 21, 2020, that the South Carolina State official had no comments (ADAMS Accession No. ML20021A197).
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and change inspections or SRs. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there were no public comments on this finding (84 FR 59657; November 5, 2019). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b ), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: M. Mahoney, NRR Date:
January 31, 2 O 2 O
ML19296D119 OFFICE DORL/LPL2-1/PM DORL/LPL2-1/LA*
NAME MMahoney KGoldstein DATE 01/08/2020 01/08/2020 FFICE DORL/LPL2-1 /BC DORL/LPL2-1 /PM NAME MMarkley MMahoney DATE 01/31/2020 01/31/2020