ML17254A144
| ML17254A144 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/23/2017 |
| From: | Michael Mahoney Plant Licensing Branch II |
| To: | Simril T Duke Energy Carolinas |
| Miller G | |
| References | |
| CAC MF8969, CAC MF8970, EPID L-2017-LLA-0031 | |
| Download: ML17254A144 (16) | |
Text
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- ~~ 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-352-A, REVISION 1 (CAC NOS. MF8969 AND MF8970; EPID L-2016-LLA-0031)
Dear Mr. Simril:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 294 to Renewed Facility Operating License No. NPF-35 and Amendment No. 290 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 (TS) limiting condition for operation (LCO) 3.4.10, "Pressurizer Safety Valves," Required Action B.2, TS LCO 3. 7.4, "Steam Generator Power Operated Relief Valves (SG PORVs)," Required Action C.2, and TS LCO 3.7.6, "Condensate Storage System (CSS)," Required Action B.2 by extending the Completion Time for these Required Actions from 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The changes are consistent with Technical Specifications Task Force (TSTF) Traveler TSTF-352-A, Revision 1, "Provide Consistent Completion Time to Reach MODE 4."
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
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Michael 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. 294 to NPF-35
- 2. Amendment No. 290 to NPF-52
- 3. Safety Evaluation cc w/enclosures: Distribution via 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. 294 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. 294, 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 REGULA TORY 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. 290 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. 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.
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: October 23, 2017
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 LICENSE AMENDMENT NO. 294 RENEWED FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND LICENSE AMENDMENT NO. 290 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 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 Insert TS3.4.10-1 TS3.4.10-1 TS 3.7.4-1 TS 3.7.4-1 TS 3.7.6-1 TS 3.7.6-1
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 294, 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 294
(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 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 290
Pressurizer Safety Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves LCO 3.4.1 O Three pressurizer safety valves shall be OPERABLE with lift settings
~ 2435 psig and ~ 2559 psig.
APPLICABILITY: MODES 1, 2, and 3, MODE 4 with all RCS cold leg temperatures> 210°F.
NOTE--------------------------------------------
The lift settings are not required to be within the LCO limits during MODES 3 and 4 for the purpose of setting the pressurizer safety valves under ambient (hot) conditions. This exception is allowed for 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> following entry into MODE 3 provided a preliminary cold setting was made prior to heatup.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable. OPERABLE status.
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. AND OR B.2 Be in MODE 4 with any 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> RCS cold leg temperatures Two or more pressurizer ~ 210°F.
safety valves inoperable.
Catawba Units 1 and 2 3.4.10-1 Amendment Nos. 294/290
- 3. 7 PLANT SYSTEMS 3.7.4 Steam Generator Power Operated Relief Valves (SG PORVs)
LCO 3. 7.4 Four SG PORV lines shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SG PORV line A.1 Restore SG PORV line to 7 days inoperable. OPERABLE status.
B. Two or more SG PORV B.1 Restore all but one SG 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> lines inoperable. PORV line to OPERABLE status.
C. Required Action and C.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. AND C.2 Be in MODE 4 without 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> reliance upon steam generator for heat removal.
Catawba Units 1 and 2 3.7.4-1 Amendment Nos. 294/290
css 3.7.6
- 3. 7 PLANT SYSTEMS 3.7.6 Condensate Storage System (CSS)
LCO 3.7.6 The CSS inventory shall be,::: 225,000 gal.
APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. CSS inventory not within A.1 Verify by administrative 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> limit. means OPERABILITY of assured water supply. AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND A.2 Restore CSS inventory to 7 days within limit.
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. AND B.2 Be in MODE 4, without 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> reliance on steam generator for heat removal.
Catawba Units 1 and 2 3.7.6-1 Amendment Nos. 294/290
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 294 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-35 AMENDMENT NO. 290 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 specifications (TSs) for Catawba Nuclear Station, Units 1 and 2 (Catawba).
The amendments modify technical specification (TS) limiting condition for operation (LCO) 3.4.10, "Pressurizer Safety Valves," Required Action 8.2, TS LCO 3.7.4, "Steam Generator Power Operated Relief Valves (SG PORVs)," Required Action C.2, and TS LCO 3.7.6, "Condensate Storage System (CSS)," Required Action B.2 by extending the completion time (CT) for these Required Actions from 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The changes are consistent with Technical Specifications Task Force (TSTF) Traveler TSTF-352-A, Revision 1, "Provide Consistent Completion Time to Reach MODE 4," (ADAMS Accession No. ML040630065).
The amendments adopt previously NRG-approved TSTF-352-A, Revision 1, in order to bring the Catawba TSs into closer alignment with NUREG-1431, 'Standard Technical Specifications -
Westinghouse Plants' (Westinghouse Owners Group (WOG) Standard Technical Specifications (STS), hereafter referred to as "WOG STS" or "STS").
The NRC did not issue a letter approving the TSTF-352-A, Revision 1; however, this change was incorporated by the NRC into Revision 2 of the STS (ADAMS Accession No. ML011840211 and ML011840219).
2.0 REGULATORY EVALUATION
In Title 1O 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.
Enclosure 3
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 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.
2.1 Licensee's Proposed Changes The current CT for TS LCO 3.4.10 Required Action B.2, "Be in MODE 4 with any RCS [reactor coolant system] cold leg temperatures:::; 210 °F [degrees Fahrenheit]" is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The current CT for TS LCO 3.7.4 Required Action C.2, "Be in MODE 4 without reliance upon steam generator for heat removal" is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The current CT for TS LCO 3.7.6 Required Action B.2, "Be in MODE 4, without reliance upon steam generator for heat removal" is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The proposed change would extend the CT for the Required Actions listed above from 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.0 TECHNICAL EVALUATION
3.1 NRC Staff's Technical Evaluation of Licensee's Proposed Changes TSTF-352-A, Revision 1, revised WOG STS 3.4.10, "Pressurizer Safety Valves," STS 3.4.12, "Low Temperature Overpressure Protection (LTOP) System," STS 3.7.4, "Atmospheric Dump Valves" and STS 3.7.6, "Condensate Storage Tank (CST)." The revisions increased the CTs for Required Actions which direct entry into conditions below MODE 4 to allow sufficient time to safely perform the actions and changed the time to go from LTOP conditions to having the RCS vented to allow sufficient time to complete the activity. The NRC published STS NUREG-1431, Revision 2, in June 16, 2001. No formal communication was issued to approve this TSTF Traveler in particular, rather, the NRC incorporated TSTF-352-A, Revision 1, along with other approved TSTF Travelers into Revision 2 of NUREG-1431.
3.1.1 Extension of CT for TS LCO 3.4.10, Required Action B.2 The current CT of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for TS LCO 3.4.10, Required Action B.2 is for a normal shutdown from MODE 1 to MODE 4 (average RCS temperature between 350 °F and 200 °F, according to TS 1.1, "Definitions," Table 1.1-1 ); however, TS LCO 3.4.10, Required Action 8.2 requires that the plant is required to be in MODE 4 at or below RCS cold-leg temperatures of 210 °f).
The 210 °F is 140 °F below the highest average RCS temperature for entry to MODE 4 (average RCS temperature between 350 °F and 200 °F). The additional time is needed to reduce the RCS cold-leg temperature to no more than 210 °f in a safe and controlled manner. The NRC staff finds that it is reasonable to provide the additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to allow for the fact that the condition to be reached in TS LCO 3.4.10, Required Action B.2 is a significant lower RCS temperature (21 O°F) than the RCS temperature (350 °F to 200 °F) for entry into MODE 4.
3.1.2 Extension of CTs for TS LCO 3.7.4, Required Action C.2 and TS LCO 3.7.6, Required Action B.2 Current TS LCOs 3. 7.4, Required Action C.2 and 3. 7.6, Required Action B.2, requires the plant to be in MODE 4 without reliance of the steam generator (SG) for heat removal within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The licensee stated that this would require cooling to shutdown cooling entry conditions (less than or equal to 200 °F), which would be below the MODE 4 entry temperature (between 350 °F and 200 °F). The licensee stated that the additional time is needed for further cooldown and depressurization of the RCS to shutdown cooling entry conditions. The NRC staff finds that it is reasonable to provide the additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to allow a controlled further cooldown and depressurization of the RCS.
3.2 NRC Staff's Conclusion The NRC staff reviewed the proposed changes and determined that the extended CT will allow additional time to establish the required plant conditions. The proposed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is reasonable for these type of Required Actions (getting RCS average temperature below the MODE 4 entry temperature) because it is a balance between two competing goals. The first goal is to get the plant to the specified state as quickly and safely as possible. For Required Actions which specify achieving temperatures below MODE 4 entry conditions, the licensee has provided sufficient information to conclude 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is insufficient. The second goal is to limit the time the plant is in the mode of applicability. The NRC staff concludes that 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> proposed by the licensee would provide reasonable assurance that these two goals can be accomplished. The NRC staff determined that the extended CT is necessary and appropriate to allow a controlled entry into the required plant conditions as specified by TS LCO 3.4.10, Required Action B.2, TS LCO 3.7.4, Required Action C.2, and TS LCO 3.7.6, Required Action B.2.
Based on the above, the NRC staff concludes that the proposed TS changes, consistent with TSTF 352-A, Revision 1, 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 19099: 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: M. Hamm NRR Date of issuance: oct ob er 2 3 , 2 O1 7
ML17254A144 *by memorandum OFFICE DORL/LPL2-1 /PM DORL/LPL2-1 /LA DSS/STSB/BC* DE/EPNB/BC NAME MMahoney KGoldstein/Rohrer If/ JWhitman DAiiey DATE 9/22/17 9/21/17 7/12/17 9/27/17 OFFICE OGC- NLO DORL/LPL2-1 /BC DORL/LPL2-1 /PM NAME JGillespie MMarkley MMahoney DATE 10/17/17 10/23/17 10/23/17