ML17257A297
| ML17257A297 | |
| 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 MF8979, CAC MF8980, EPID L-2017-LLA-0043 | |
| Download: ML17257A297 (16) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 23, 2017 Mr. Tom Simril Site Vice President Catawba Nuclear Station, Units 1 and 2 Duke Energy Carolinas, LLC 4800 Concord Road York, SC 297 45
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1AND2- ISSUANCE OF AMENDMENTS ADOPTING TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-340-A, REVISION 3 (CAC NOS. MF8979 AND MF8980; EPID L-2016-LLA-0043)
Dear Mr. Simril:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 295 to Renewed Facility Operating License No. NPF-35 and Amendment No. 291 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 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16350A422).
The amendments modify technical specification (TS) limiting condition for operation (LCO) 3. 7.5, "Auxiliary Feedwater (AFW) System," Condition A and Required Action A.1.
Condition A is revised to include the situation when one turbine-driven AFW pump is inoperable in MODE 3, immediately following a refueling outage, only applicable if MODE 2 has not been entered following the refueling outage. Required Action A.1 is revised to include the turbine-driven AFW addition to Condition A.
The changes are consistent with Technical Specifications Task Force (TSTF) Traveler TSTF-340-A, Revision 3, "Allow 7 day Completion Time for a turbine-driven AFW pump inoperable."
T. Simril A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincer y, Jf~
l\Aichael Mahoney, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414
Enclosures:
- 1. Amendment No. 295 to NPF-35
- 2. Amendment No. 291 to NPF-52
- 3. Safety Evaluation cc: Listserv
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. 295 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 (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 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 set forth in 10 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.
Enclosure 1
- 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. 295, 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.
FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
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. 291 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 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 set forth in 10 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.
Enclosure 2
- 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. 291, 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.
FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed License No. NPF-52 and Technical Specifications Date of Issuance: oct ob er 2 3 , 2O1 7
ATTACHMENT CATAWBA NUCLEAR STATION, UNITS 1 AND 2 LICENSE AMENDMENT NO. 295 RENEWED FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND LICENSE AMENDMENT NO. 291 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 Insert NPF-35, page 4 NPF-35, page 4 NPF-52, 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 Insert TS 3.7.5-1 TS 3.7.5-1
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 295, 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 295
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 291, 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-52 Amendment 291
AFW System 3.7.5
- 3. 7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System LCO 3.7.5 Three AFW trains shall be OPERABLE.
NOTE--------------------------------------------------
Only one AFW train, which includes a motor driven pump, is required to be OPERABLE in MODE 4.
APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.
ACTIONS
NOTE----------------------------------------------------------
LCO 3.0.4.b is not applicable when entering MODE 1.
CONDITION REQUIRED ACTION COMPLETION TIME A. One steam supply to A.1 Restore affected 7 days turbine driven AFW equipment to OPERABLE pump inoperable. status. AND OR 10 days from
NOTE----------- discovery of Only applicable if MODE failure to 2 has not been entered meet the LCO following refueling.
One turbine driven AFW pump inoperable in MODE 3 following refueling.
B. One AFW train B.1 Restore AFW train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable in MODE 1, 2 OPERABLE status.
or 3 for reasons other AND than Condition A.
10 days from discovery of failure to meet the LCO (continued)
Catawba Units 1 and 2 3.7.5-1 Amendment Nos. 295/291
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 295 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-35 AMENDMENT NO. 291 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 to the U.S. Nuclear Regulatory Commission (NRC, Commission) dated December 15, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16350A422), Duke Energy Carolinas, LLC (Duke Energy, the licensee), submitted an application to seek approval to change the technical specification (TSs) for Catawba Nuclear Station, Units 1 and 2 (Catawba).
The amendments modify TS limiting condition for operation (LCO) 3.7.5, "Auxiliary Feedwater (AFW) System," Condition A and Required Action A.1. Condition A is revised to include the situation when one turbine-driven AFW pump is inoperable in MODE 3, immediately following a refueling outage, only applicable if MODE 2 has not been entered following the refueling outage.
Required Action A.1 is revised to include the turbine-driven AFW addition to Condition A.
The changes are consistent with Technical Specifications Task Force (TSTF) Traveler TSTF-340-A, Revision 3, "Allow 7 day Completion Time for a turbine-driven AFW pump inoperable" (ADAMS Accession No. ML003687327). The NRC approved TSTF-340, Revision 3, by letter dated March 16, 2000 (ADAMS Accession No. ML003694199).
2.0 REGULATORY EVALUATION
2.1 Applicable Regulations and Guidance The proposed license amendment involves a change to the content of the TSs. The NRC staff reviews the proposed TS changes for compliance with applicable regulations and conformance with associated regulatory 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 Enclosure 3
limiting control settings; (2) LCOs; (3) surveillance requirements; (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 Guidance for staff review of TSs is contained in NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-water Reactor]
Edition," Section 16.0, Technical Specifications." The NRC staff has prepared standard technical specifications (STS) for each of the LWR nuclear steam supply systems and associated balance-of-plant equipment systems. The guidance specifies that the NRC staff reviews whether the content and format are consistent with the applicable STS. Where TS provisions depart from the reference TSs, the staff determines whether proposed differences are justified by uniqueness in plant design or other considerations. The applicable current STS for Catawba are contained in NUREG-1431, Revision 4, "Standard Technical Specifications -
Westinghouse Plants," April 2012 (ADAMS Accession No. ML 121 OOA222).
2.2 Description of Auxiliary Feedwater System The Catawba AFW system is described in Section 10.4.9 of the Catawba Updated Final Safety Analysis Report (UFSAR). The AFW assures there is sufficient feedwater supply to the steam generators (SGs) to remove energy stored in the core and primary coolant, in the event of the loss of the normal feedwater system. The AFW system is designed to start automatically in the event of a loss of offsite power, a trip of all operating main feedwater pumps, a safety injection signal, or a low-low SG level.
Each unit at Catawba has a dedicated AFW system consisting of one turbine-driven AFW pump, two motor-driven AFW pumps, and associated piping, valves, and instrumentation. The motor-driven pumps normally each deliver flow to two SGs. The turbine-driven pump receives steam supplied via separate lines from the B and C SGs, and the motor-driven pumps receive electrical power from separate electrical divisions.
The AFW system is credited in accident analyses for a loss of offsite power, a loss of normal feedwater, and cooldown following a loss-of-coolant accident trough a small break, including an SG tube rupture. The alternating current (AC) power-independent turbine-driven AFW pump is relied upon to deliver adequate feedwater to cool the primary system following a loss of all onsite and offsite AC electrical power.
2.3 Licensee's Proposed Changes Current TS LCO 3.7.5, Condition A, currently states, CONDITION REQUIRED ACTION COMPLETION TIME A. One steam supply to A.1 Restore steam supply 7 days turbine driven AFW to OPERABLE status.
pump inoperable. AND 10 Days from discovery of failure to meet the LCO Revised TS LCO 3.7.5, Condition A, will state:
CONDITION REQUIRED ACTION COMPLETION TIME A. One steam supply to A.1 Restore affected 7 days turbine driven AFW equipment to pump inoperable. OPERABLE status. AND OR 10 Days from discovery of failure to
NOTE ------- meet the LCO Only applicable if MODE 2 has not been entered following refueling.
One turbine driven AFW pump inoperable in MODE 3 following refueling.
3.0 TECHNICAL EVALUATION
3.1 NRC Staff's Technical Evaluation of Licensee's Proposed Changes The NRC approved this change to STS NUREG-1431, Revision 1, on March 16, 2000. This traveler revised Westinghouse Owners Group (WOG) STS 3.7.5, "Auxiliary Feedwater System,"
to extend Condition A Completion Time to 7 days to restore an inoperable turbine-driven AFW steam supply, and to expand Condition A by adding an OR statement and a NOTE in the Condition. The added statement states, "One turbine driven AFW pump inoperable in MODE 3 following refueling," and the NOTE states, "Only applicable if MODE 2 has not been entered following refueling."
The TS LCO 3.7.5 currently allows a Completion Time of 7 days and 10 days from discovery of failure to meet the LCO; therefore, this part of the TSTF-340-A, Revision 3 change is not adopted by the licensee.
However, the licensee proposed to modify TS 3.7.5, Condition A, so as to allow a 7-day Completion Time for the turbine-driven AFW pump being inoperable in MODE 3, immediately
following a refueling outage, if MODE 2 has not been entered. This change was proposed on the basis that it could reduce the number of unnecessary mode changes by providing added flexibility in MODE 3 to repair and test the turbine-driven AFW pump, if the pump were to be declared inoperable following a refueling outage. In the proposed condition, there is minimal decay heat for the AFW system to have to remove through the SGs due to the time that irradiated fuel has decayed during the refueling outage and the replacement of irradiated fuel with un-irradiated fuel. The NRC staff agrees with that basis and concludes that the change is reasonable, given the redundant capabilities afforded by the AFW system, the time needed to perform repairs and testing of the turbine-driven pump, and the low probability of an accident occurring during this time period that would require the operation of the turbine-driven pump. In addition, there are alternate methods, such as feed and bleed, available to remove decay heat if necessary.
3.2 NRC Staff's Conclusion Based on the above, the NRC staff concludes that the proposed TS changes, consistent with TSTF-340-A, Revision 3, would continue to meet the requirements of 10 CFR 50.36(c)(2) 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, 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 22, 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 19100; April 25, 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: S. Jones, NRA M. Hamm, NRA Date of issuance: October 23, 2017
ML17257A297 *b memorandum OFFICE NRR/DORL/LPL2-1 /PM NRR/DORL/LPL2-1 /LA NRR/DSS/STSB/BC(A)* NRR/DSS/SBPB/BC*
NAME MMahoney KGoldstein (JBurkhardt for) JWhitman RDennig DATE 9/22/17 9/21 /17 7/12/17 4/26/17 OFFICE OGC- NLO NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME AGhosh MMarkley MMahoney DATE 10/6/17 10/23/17 10/23/17