ML17165A441
| ML17165A441 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/21/2017 |
| From: | Michael Mahoney Plant Licensing Branch II |
| To: | Simril T Duke Energy Carolinas |
| Miller G, 415-3867 | |
| References | |
| CAC MF8983, CAC MF8984 | |
| Download: ML17165A441 (17) | |
Text
Mr. Tom Simril Site Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 21, 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 SPECIFICATIONS TASK FORCE TRAVELER TSTF-269-A, REVISION 2 (CAC NOS. MF8983 AND MF8984)
Dear Mr. Simril:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 290 to Renewed Facility Operating License No. NPF-35 and Amendment No. 286 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 Accession No. ML16350A422).
The amendments modify Technical Specification (TS) 3.6.3, "Containment Isolation Valves," to add a Note to TS Limiting Condition for Operation 3.6.3 Required Actions A.2, C.2, and E.2 to allow isolation devices that are locked, sealed, or otherwise secured to be verified by use of administrative means. The changes are consistent with NRG-approved Technical Specifications Task Force (TSTF) Traveler TSTF-269-A, Revision 2, "Allow administrative means of position verification for locked or sealed valves."
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. 290 to NPF-35
- 2. Amendment No. 286 to NPF-52
- 3. Safety Evaluation cc w/enclosures: Distribution via Listserv Michael Mahoney, oject 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. 290 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.
- 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. 290 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 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: Ju 1 y 2 1, 2 O 1 7
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. 286 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 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 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. 286, 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 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: July 21, 2017
ATTACHMENT TO CATAWBA NUCLEAR STATION, UNITS 1 AND 2 LICENSE AMENDMENT NO. 290 RENEWED FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND LICENSE AMENDMENT NO. 286 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 pages of the Appendix A Technical Specifications (TS) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove TS 3.6.3-2 TS 3.6.3-3 TS 3.6.3-4 Insert TS 3.6.3-2 TS 3.6.3-3 TS 3.6.3-4 (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 290 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 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 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-35 Amendment 290 (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 286, 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 1 O 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 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 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 1 O 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 286
ACTIONS CONDITION A.
(continued)
A.2 B.
N 0 TE------------
B.1 Only applicable to penetration flow paths with two containment isolation valves.
One or more penetration flow paths with two containment isolation valves inoperable except for purge valve or reactor building bypass leakage not within limit.
Catawba Units 1 and 2
- 1.
- 2.
Containment Isolation Valves 3.6.3 REQUIRED ACTION COMPLETION TIME
NOTES------------
Isolation devices in high radiation areas may be verified by use of administrative means.
Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected Once per 31 days for penetration flow path is isolation devices isolated.
outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment Isolate the affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
(continued) 3.6.3-2 Amendment Nos. 290/286
ACTIONS (continued)
CONDITION C.
NOTE------------
Only applicable to penetration flow paths with only one containment isolation valve and a closed system.
One or more penetration flow paths with one containment isolation valve inoperable.
D.
Reactor building bypass leakage not within limit.
E.
One or more penetration flow paths with one or more containment purge, hydrogen purge, or containment air release and addition valves not within leakage limits.
Catawba Units 1 and 2 C.1 AND C.2
- 1.
- 2.
D.1 E.1 AND Containment Isolation Valves 3.6.3 REQUIRED ACTION COMPLETION TIME Isolate the affected 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
N 0 TES-------------
Isolation devices in high radiation areas may be verified by use of administrative means.
Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected Once per 31 days penetration flow path is isolated.
Restore leakage within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> limit.
Isolate the affected 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
(continued) 3.6.3-3 Amendment Nos. 290/286
ACTIONS CONDITION E.
(continued)
F.
Required Action and associated Completion Time not met.
Catawba Units 1 and 2 E.2
- 1.
- 2.
AND E.3 F.1 AND F.2 Containment Isolation Valves 3.6.3 REQUIRED ACTION COMPLETION TIME
N 0 TES------------
Isolation devices in high radiation areas may be verified by use of administrative means.
Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected Once per 31 days for penetration flow path is isolation devices isolated.
outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment Perform SR 3.6.3.6 for the Once per 92 days resilient seal purge valves closed to comply with Required Action E.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 /> Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> 3.6.3-4 Amendment Nos. 290/286
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 290 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-35 AND AMENDMENT NO. 286 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 Commision (NRC, the Commision) 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 amend the Technical Specifications (TSs) for Catawba Nuclear Station (CNS),
Units 1 and 2.
This license amendment request (LAA) would modify TS 3.6.3, "Containment Isolation Valves,
to add a Note to TS Limiting Condition for Operation (LCO) 3.6.3 Required Actions A.2, C.2, and E.2 to allow isolation devices that are locked, sealed, or otherwise secured to be verified by use of administrative means. The licensee stated that this change is consistent with NRG-approved Technical Specifications Task Force (TSTF} Traveler TSTF-269-A, Revision 2, "Allow administrative means of position verification for locked or sealed valves."
The amendments would adopt previously NRG-approved TSTF-269-A, Revision 2 (ADAMS Legacy Accession No. 9907300113), in order to bring the CNS, Units 1 and 2 TSs, into closer alignment with NUREG-1431, "Standard Technical Specifications - Westinghouse Plants" (Westinghouse Owners Group (WOG) Standard Technical Specifications (STS) - hereafter "WOG STS" or "STS").
2.0 REGULATORY EVALUATION
In Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, the Commission established its regulatory requirements related to the content of TSs. Pursuant to 1 O CFR 50.36, TSs are required to include items in the following categories related to station 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. The regulation does not specify the particular requirements to be included in a plant's TSs.
On July 22, 1993, the Commission published in the Federal Register (FR) the "Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors" (58 FR 39132). This Final Policy Statement discussed criteria for determining which items should be included in the TSs as LCOs. These criteria were subsequently incorporated into 10 CFR 50.36 (60 FR 36953; July 19, 1995). Specifically, 10 CFR 50.36(c)(2)(ii) requires that an LCO be established for each item meeting one or more of the following criteria:
Criterion 1: Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.
Criterion 2: A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
Criterion 3: A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
Criterion 4: A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
The NRC staff used Revision 3 of the WOG STS (ADAMS Accession No. ML041830612) in its review of the TS changes proposed for CNS, Units 1 and 2. The NRC staff also referred to the TSTF Traveler associated with the STS changes proposed for CNS, Units 1 and 2.
3.0 TECHNICAL EVALUATION
3.1 Licensee's Proposed Changes Current TS LCO 3.6.3, Condition A states, "One or more penetration flow paths with one containment isolation valve inoperable except for purge valve or reactor building bypass leakage not within limit." Required Action A.2 states, Verify the affected penetration flow path is isolated.
With a Completion Time of:
Once per 31 days for isolation devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment.
Current TS LCO 3.6.3, Condition C states, "One or more penetration flow paths with one containment isolation valve inoperable." Required Action C.2 states, Verify the affected penetration flow path is isolated.
With a Completion Time of:
Once per 31 days.
Current TS LCO 3.6.3, Condition E states, "One or more penetration flow paths with one or more containment purge, hydrogen purge, or containment air release and addition valves not within leakage limits." Required Action E.2 states, Verify the affected penetration flow path is isolated.
With a Completion Time of:
Once per 31 days for isolation devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment.
Revised TS LCO 3.6.3 would add the following NOTE (as NOTE 2) under Required Actions A.2, C.2, and E.2. The current NOTE for Required Actions A.2, C.2, and E.2 would be renumbered to be NOTE 1.
Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
3.2 NRC Staff's Technical Evaluation of Licensee's Proposed Changes TSTF-269-A, Revision 2, revised WOG STS 3.6.3, "Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual)," by adding a note under Required Actions A.2, C.2, and E.2 that isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
The NRC staff has reviewed the proposed changes to TS LCO 3.6.3 and has determined that the licensee's proposed use of administrative controls provide adequate assurance to ensure that the valves are maintained in the positions required by the plant safety analyses when primary and secondary containment are required to be operable.
Additionally, the NRC staff concludes that the requirements of 10 CFR 50.36(c)(2) continue to be met. Based on the above, the NRC staff concludes that the proposed changes to TS LCO 3.6.3 are acceptable.
3.3 NRC Staff's Conclusion The NRC staff concludes that the proposed TS changes, consistent with TSTF-269-A, Revision 2, are acceptable. The NRC concludes that the proposed administrative controls provide reasonable assurance of plant safety and the requirements of 10 CFR 50.36 continue to be met.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments on June 12, 2017. On July 18, 2017, the State official confimed that she 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 19098; 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 Contributor: A. Smith, NRR Date: July 21, 2017
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1AND2 - ISSUANCE OF AMENDMENTS ADOPTING TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-269-A, REVISION 2 (CAC NOS. MF8983 and MF8984)
DATED JULY 21, 2017 DISTRIBUTION:
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OFFICE DORL/LPL2-1/PM DORL/LPL2-1/LA NAME MMahoney KGoldstien DATE 06/22/17 06/22/17 OFFICE DSS/SBPB/BC OGC (NLO)
NAME RDennig JWachutka DATE 06/22/17 07/05/17
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1y memoran um DSS/STSB/BC*
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