ML17261B290
| ML17261B290 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/23/2017 |
| From: | Michael Mahoney Plant Licensing Branch II |
| To: | Simril T Duke Energy Carolinas |
| Mahoney M | |
| References | |
| CAC MF8962, CAC MF8963, EPID L-2017-LLA-0024 | |
| Download: ML17261B290 (14) | |
Text
Mr. Tom Simril Site Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 23, 2017 Catawba Nuclear Station, Units 1 and 2 Duke Energy Carolinas, LLC 4800 Concord Road York, SC 29745
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1AND2-ISSUANCE OF AMENDMENTS ADOPTING TECHNICAL SPECIFICATION TASK FORCE TRAVELER TSTF-142-A, REVISION 0 (CAC NOS. MF8962 AND MF8963; EPID L-2016-LLA-0024)
Dear Mr. Simril:
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 296 to Renewed Facility Operating License No. NPF-35 and Amendment No. 292 to Renewed Facility Operating License No. NPF-52 for the Catawba Nuclear Station, Units 1 and 2, respectively. The amendments are in response to your application dated December 15, 2016.
The amendments modify Technical Specification 3.1.2, "Core Reactivity, to revise the Completion Times of Required Actions A.1 and A.2 from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days. The proposed changes are consistent with NRG-approved Technical Specifications Task Force (TSTF)
Traveler TSTF-142-A, Revision 0, "Increase the Completion Time when the Core Reactivity Balance is Not Within Limit."
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Docket Nos. 50-413 and 50-414
Enclosures:
- 1. Amendment No. 296 to NPF-35
- 2. Amendment No. 292 to NPF-52
- 3. Safety Evaluation cc: Listserv 1chael Mahoney, Project Manager Plant Licensing Branch 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 NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 296 Renewed License No. NPF-35
- 1.
The 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 December 15, 2016, 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 1 O 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 set forth in 1 O CFR Chapter I; 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. 296, 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
~z.4 Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Changes to Renewed License No. NPF-35 and Technical Specifications Date of Issuance: October 23, 2017
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 292 Renewed License No. NPF-52
- 1.
The 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 the Duke Energy Carolinas, LLC (the licensee), dated December 15, 2016, 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 1 O 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 set forth in 1 O CFR Chapter I; 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 1 O 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. 292, 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
~
,,., fa.JtA-tJ Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Changes to Renewed License No. NPF-52 and Technical Specifications Date of Issuance:* October 23-, 2017
ATTACHMENT CATAWBA NUCLEAR STATION. UNITS 1 AND 2 LICENSE AMENDMENT NO. 296 RENEWED FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND LICENSE AMENDMENT NO. 292 RENEWED FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 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 Replace the following page of the Appendix A Technical Specifications (TS} with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove TS 3.1.2-1 Insert TS 3.1.2-1 (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 296, 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 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 Duke Energy Carolinas, LLC shall comply with the antitrust conditions delineated in Appendix C to this renewed operating license.
(5)
Fire Protection Program Duke Energy Carolinas, LLC shall implement and maintain in effect all provisions of the approved fire protection program that complies with 10 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 296 (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 292, 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 Duke Energy Carolinas, LLC shall comply with the antitrust conditions delineated in Appendix C to this renewed operating license.
(5)
Fire Protection Program Duke Energy Carolinas, LLC shall implement and maintain in effect all provisions of the approved fire protection program that complies with 10 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
. NRG 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 NRG 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 292
3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Core Reactivity Core Reactivity 3.1.2 LCO 3.1.2 The measured core reactivity shall be within +/- 1 % ~k/k of predicted values.
APPLICABILITY:
MODES 1 and 2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Measured core reactivity A.1 Re-evaluate core design 7 days not within limit.
and safety analysis, and determine that the reactor core is acceptable for continued operation.
AND A.2 Establish appropriate 7 days operating restrictions and SRs.
B.
Required Action and B.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.
Catawba Units 1 and 2 3.1.2-1 Amendment Nos. 296/292
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 296 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-35 AND AMENDMENT NO. 292 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-52 DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION, UNITS 1AND2 DOCKET NOS. 50-413 AND 50-414
1.0 INTRODUCTION
By letter dated December 15, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16350A422), Duke Energy Carolinas, LLC (the licensee), submitted a license amendment request (LAR) for the Catawba Nuclear Station, Units 1 and 2 (Catawba),
to adopt multiple Technical Specification Task Force (TSTF) Travelers. This safety evaluation specifically evaluates the adoption of TSTF-142-A, Revision 0, "Increase the Completion Time when the Core Reactivity Balance is Not Within Limit," for Catawba.
This LAR revises Technical Specification (TS) 3.1.2, "Core Reactivity," to revise the Completion Times of Required Actions A.1 and A.2 from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days. The licensee stated that the proposed changes are consistent with TSTF-142-A, Revision 0, dated April 2, 1998 (ADAMS Accession No. ML040490204).
Technical Specification Task Force Travelers are generic changes to the Improved Standard Technical Specifications (STSs). A list of the Travelers proposed for adoption is included in of the LAR. The licensee stated that the proposed amendments will bring the Catawba TSs into closer alignment with NUREG-1431, Revision 4.0, "Standard Technical Specifications - Westinghouse Plants," April 2012 (ADAMS Accession No. ML12100A222).
The NRC did not issue a letter approving TSTF-142, Revision O; however, TSTF-142, Revision 0, was incorporated into Revision 2 of the STSs issued in April 2001 (ADAMS Accession No. ML011840211 and ML011840219).
2.0 REGULATORY EVALUATION
2.1 Applicable Regulations and Guidance In Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, "Technical Specifications," the NRC established its regulatory requirements related to the content of TSs.
Pursuant to 10 CFR 50.36(c), TSs are required to include items in the following five specific categories related to plant operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls. However, the regulation does not specify the particular requirements to be included in a plant's TSs. The LCOs are the lowest functional capability, or performance levels, of equipment required for safe operation of the facility. When an LCO of a nuclear reactor is not met, the licensee shall follow any remedial actions permitted by the TS until the condition can be met or shall shut down the reactor.
2.2 Licensee's Proposed Changes Catawba's current TS LCO 3.1.2, "Core Reactivity," states that Condition A, "Measured core reactivity not within limit," Required Action A.1, "Re-evaluate core design and safety analysis, and determine that the reactor core is acceptable for continued operation," and Required Action A.2, "Establish appropriate operating restrictions and SRs," have Completion Times of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Revised TS LCO 3.1.2 Condition A, Required Actions A.1 and A.2 Completion Times would be extended from "72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />" to "7 days."
3.0 TECHNICAL EVALUATION
The license proposed to extend the Completion Times for TS LCO 3.1.2, Condition A, Required Actions A.1 and A.2 from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days, which is consistent with TSTF-142-A, Revision 0.
The NRC did not issue a letter approving this change to Revision 1 of the STS; however, this change was incorporated by the NRC into Revision 2 of the STS. Revision 0 of TSTF-142-A extended the STS LCO 3.1.3 (equivalent to Catawba TS 3.1.2) Condition A, Required Actions A.1 and A.2 Completion Times from "72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />" to "7 days." The licensee stated that upon the determination that the reactivity balance is not within the specified limit of predicted values, the proposed TS change would allow Catawba TSs 7 days to reevaluate core design and safety analyses to determine if the core is acceptable for continued operation, and to establish appropriate operating restrictions and perform appropriate SRs.
Under the current TSs, had the reactivity balance been outside its limits, Catawba would have to be in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. In the LAR, the licensee justified this extension by stating, in part, that "[r]esolving a predicted versus measured reactivity anomaly is very complex. Data must be gathered, transmitted to the core design organization (which may be an offsite vendor, which would require additional administrative actions), evaluation by the core design organization, and implementation of appropriate controls." The licensee also stated, in part, that "because exceeding this limit is very unlikely, it is important to allow sufficient time to properly analyze the causes."
In TSTF-142-A, Revision 0, the NRC approved the 7-day period for incorporation into the STS based on the conservatisms used in designing the reactor core and performing the safety analyses, and because of the low probability of a design basis accident or anticipated transient approaching the core design limits occurring during the proposed extended 7-day period.
3.1 NRC Staff's Conclusion Based on the above, the NRC staff concludes that the proposed TS changes, consistent with TSTF-142-A, Revision 0, would continue to meet the requirements of 10 CFR 50.36(c)(2)(i) and are, therefore, acceptable, since the minimum performance level of equipment needed for safe operation of the facility is contained in the LCO, and the appropriate remedial measures are specified if the LCO is not met.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the NRC staff notified the South Carolina State official of the proposed issuance of the amendments on September 11, 2017. The State official confirmed on September 25, 2017, that the State of South Carolina had no comments.
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. 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 has been no public comment on this finding (82 FR 17 457; April 11, 2017). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). 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 Contributors: D. Woodyatt, NRR D~e:October 23, 2017
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS ADOPTING TECHNICAL SPECIFICATION TASK FORCE TRAVELER TSTF-142-A, REVISION 0 (CAC NOS. MF8962 AND MF8963; EPID L-2016-LLA-0024) DATED OCTOBER 23, 2017 DISTRIBUTION:
PUBLIC RidsACRS_MailCTR Resource RidsNrrDorlLpl2-1 Resource RidsNrrDssStsb Resource RidsNrrDssSrxb Resource RidsNrrPMCatawba Resource RidsRgn2MailCenter Resource RidsNrrLAKGoldstein Resource RidsNrrLAJBurkhardt Resource DWoodyatt, NRR ADAMS A ccess1on N ML172618290 o.:
OFFICE NRR/DORL/LPL2-1 /PM NRR/DORL/LPL2-1 /LA NAME MMahoney KGoldstein (JBurkhardt for)
DATE 9/25/17 9/22/17 OGC - NLO (subject to OFFICE comments)
NRR/DORL/LPL2-1 /BC NAME A Ghosh MMarkley DATE 10/11/17 10/23/17 NRR/DSS/SRXB/BC*
EOesterle 07/19/17 NRR/DORL/LPL2-1 /PM MMahoney 10/23/17 OFFICIAL RECORD COPY
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1y memoran um NRR/DSS/STSB/BC(A)
JWhitman 9/26/17