ML17249A135
| ML17249A135 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/29/2017 |
| From: | Michael Mahoney Plant Licensing Branch II |
| To: | Waldrep B Duke Energy Carolinas |
| Mahoney M | |
| References | |
| CAC MF8964, CAC MF8965, CAC MF8973, CAC MF8974, CAC MF8985, CAC MF8986 | |
| Download: ML17249A135 (16) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 29, 2017 Mr. Tom Simril Site Vice President Catawba Nuclear Station, Units 1 and 2 Duke Energy Carolinas, LLC 4800 Concord Road York, SC 29745
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1AND2- ISSUANCE OF AMENDMENTS ADOPTING TECHNICAL SPECIFICATIONS TASK FORCE TRAVELERS TSTF-349-A, REVISION 1, TSTF-361-A, REVISION 2, AND TSTF-438-A, REVISION 0 (CAC NOS. MF8964, MF8965, MF8973, MF8974, MF8985, AND MF8986)
Dear Mr. Simril:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 293 to Renewed Facility Operating License No. NPF-35 and Amendment No. 289 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) 3.9.5, "Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level," to add a note which allows all RHR pumps to be secured for less than or equal to 15 minutes to support the switching of the shutdown cooling loops from one train to another. Three conditions must also exist in order to secure the pumps: the core outlet temperature is maintained greater than 10 degrees Fahrenheit below saturation temperature; no operations are permitted that would cause introduction of coolant into the Reactor Coolant System (RCS) with boron concentration less than that required to meet the minimum boron concentration of TS LCO 3.9.1, "Boron Concentration"; and no draining operations to further reduce RCS water volume are permitted.
A second note is added to allow one required RHR loop to be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing, provided the other RHR loop is operable and in operation.
The changes are consistent with Technical Specifications Task Force (TSTF) Travelers TSTF-349-A, Revision 1, "Add Note to LCO 3.9.5 Allowing Shutdown Cooling Loops Removal from Operation," TSTF-361-A, Revision 2, "Allow standby [Shutdown Cooling] SDC/RHR/[Decay Heat Removal] OHR loop to be inoperable to support testing," and TSTF-438, Revision 0, "Clarify Exception Notes to be Consistent with the Requirement Being Excepted."
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.
Sincerely,
- ~/.1JJJ f 1chael Mahoney, Project Manager t 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. 293 to NPF-35
- 2. Amendment No. 289 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. 293 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. 293, 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.
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: September 29, 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. 289 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. 289, 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: September 29, 2017
ATTACHMENT CATAWBA NUCLEAR STATION, UNITS 1 AND 2 LICENSE AMENDMENT NO. 293 RENEWED FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND LICENSE AMENDMENT NO. 289 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 TS 3.9.5-1 TS 3.9.5-1
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 293, 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 293
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 289, 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 289
RHR and Coolant Circulation - Low Water Level 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level LCO 3.9.5 Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.
N 0 TES-----------------------------------------------------------
- 1. All RHR pumps may be removed from operation for~ 15 minutes when switching from one train to another provided:
- a. The core outlet temperature is maintained > 10 degrees F below saturation temperature,
- b. No operations are permitted that would cause introduction of coolant into the Reactor Coolant System (RCS) with boron concentration less than that required to meet the minimum required boron concentration of LCO 3.9.1, and
- c. No draining operations to further reduce RCS water volume are permitted.
- 2. One required RHR loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing, provided that the other RHR loop is OPERABLE and in operation.
APPLICABILITY: MODE 6 with the water level < 23 ft above the top of reactor vessel flange.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than the required A.1 Initiate action to restore Immediately number of RHR loops required RHR loops to OPERABLE. OPERABLE status.
OR A.2 Initiate action to establish Immediately
.:::. 23 ft of water above the top of reactor vessel flanoe.
B. No RHR loop in B.1 Suspend operations that Immediately operation. would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.
AND (continued)
Catawba Units 1 and 2 3.9.5-1 Amendment Nos 293/289
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 293 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-35 AMENDMENT NO. 289 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) 3.9.5, "Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level," to add a note which allows all RHR pumps to be secured for less than or equal to 15 minutes to support the switching of the shutdown cooling loops from one train to another. Three conditions must also exist in order to secure the pumps: the core outlet temperature is maintained greater than 10 degrees Fahrenheit below saturation temperature; no operations are permitted that would cause introduction of coolant into the Reactor Coolant System (RCS) with boron concentration less than that required to meet the minimum boron concentration of TS LCO 3.9.1, "Boron Concentration"; and no draining operations to further reduce RCS water volume are permitted.
A second note is added to allow one required RHR loop to be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing, provided the other RHR loop is operable and in operation.
The changes are consistent with Technical Specifications Task Force (TSTF) Travelers TSTF-349-A, Revision 1, "Add Note to LCO 3.9.5 Allowing Shutdown Cooling Loops Removal from Operation" (ADAMS Accession No. ML003723263), TSTF-361-A, Revision 2, "Allow standby [Shutdown Cooling] SDC/RHR/[Decay Heat Removal] OHR loop to be inoperable to support testing" (ADAMS Accession No. ML003735328), and TSTF-438, Revision 0, "Clarify Exception Notes to be Consistent with the Requirement Being Excepted" (ADAMS Accession No. ML021580334).
The amendments adopt previously NRG-approved TSTF-349-A, Revision 1, TSTF-361-A, Revision 2, and TSTF-438-A, Revision 0, in order to bring the Catawba TSs into closer alignment with NUREG-1431, 'Standard Technical Specifications - Westinghouse Plants' Enclosure 3
(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-349-A, Revision 1, change to STS Revision 1; however, this change was incorporated by the NRC into Revision 2 of the STS (ADAMS Accession No. ML011840211). The NRC approved TSTF-361, Revision 2, by letter dated October 31, 2000 (ADAMS Accession No. ML003765449). The NRC approved TSTF-438, Revision 0, by letter dated October 21, 2002 (ADAMS Accession No. ML022940574).
2.0 REGULATORY EVALUATION
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) 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 Current TS LCO 3.9.5 states:
Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.
Revised TS LCO 3.9.5 would state:
Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.
NOTES-------------------------------------------------
- 1. All RHR pumps may be removed from operation for s 15 minutes when switching from one train to another provided:
- a. The core outlet temperature if maintained > 10 degrees F [Fahrenheit] below saturation temperature,
- b. No operations are permitted that would cause introduction of coolant into the Reactor Coolant System (RCS) with boron concentration less than that required to meet the minimum boron concentration of LCO 3.9.1, and
- c. No draining operations to further reduce RCS water volume are permitted.
- 2. One required RHR loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing, provided that the other RHR loop is OPERABLE and in operation.
3.0 TECHNICAL EVALUATION
3.1 NRC Staff's Technical Evaluation of Licensee's Proposed Changes 3.1.1 TSTF-349-A, Revision 1 TSTF-349-A, Revision 1, revised WOG STS 3.9.6, "RHR and Coolant Circulation - Low Water Level," to add a Note to the LCO statement allowing securing the operating train of RHR for up to 15 minutes to support the switching of operating trains. STS 3.9.6 is equivalent to Catawba TS 3.9.5.
The RHR system is used to remove core decay heat and reactor coolant sensible heat during unit cooldown and cold shutdown and to provide adequate mixing of borated coolant. Currently, Catawba's TS LCO 3.9.5 requires two RHR loops to be operable and one in operation when a unit is in Mode 6 with less than 23 feet of water above the top of the reactor vessel flange.
With the adoption of TSTF-349-A, Revision 1, the licensee proposed to add a Note to allow all RHR pumps to be removed from operation for up to 15 minutes when switching from one train to another. This is a short period of time without coolant flow through the reactor core. The new Note 1 includes three restrictions, when entering this condition. The three restrictions are: the core outlet temperature is maintained greater than 10 degrees Fahrenheit below saturation temperature; no operations are permitted that would cause introduction of coolant into the Reactor Coolant System (RCS) with boron concentration less than that required to meet the minimum boron concentration of TS LCO 3.9.1, "Boron Concentration"; and no draining operations to further reduce RCS water volume are permitted. These restrictions will minimize the risk while switching trains and will improve the likelihood that RHR will be safely restored.
The proposed change is consistent with the allowances that are currently in TS 3.4.8, "RCS Loops - Mode 5, Loops Not Filled," which is consistent with the plant condition allowed by TS 3.9.5. Additionally, the proposed changes are consistent with NRG-approved TSTF-349, Revision 2. Based on the above, the NRC staff finds that safe operation of the facility is maintained if both RHR loops are removed from service for less than or equal to 15 minutes, with the operational restrictions described above.
Based on that the safe operation of the facility is maintained with the proposed changes, the NRC staff concludes that the proposed changes to TS LCO 3.9.5 meet the requirements of 10 CFR 50.36, and, therefore, are acceptable.
3.1.2 TSTF-361-A, Revision 2 The purpose of the RHR system in MODE 6 is to remove decay heat and sensible heat from the RCS, to provide mixing of borated coolant, and to prevent boron stratification. Heat is removed from the RCS by circulating reactor coolant through the RHR heat exchangers where the heat is transferred to the component cooling water system. The coolant is then returned to the RCS via the RCS cold leg(s). Operation of the RHR system for normal cool-down decay heat removal is manually accomplished from the control room. The heat removal rate is adjusted by controlling the flow of reactor coolant through the RHR heat exchanger(s) and the bypass lines. Mixing of the reactor coolant is maintained by this continuous circulation of reactor coolant through the RHR system.
The proposed change adds a note to allow one of the RHR loops to be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance testing, provided the other RHR loop is operable and operating. The allowance is needed to provide the operational flexibility to perform surveillance testing. Since the reactor decay heat generation during Mode 6 is sufficiently low, a potential 2-hour interruption of decay heat removal, assuming a failure of the operating SOC loop during this time interval, would not result in a reactor safety concern. The 2-hour testing duration ensures that there is reasonable time for operators to respond to and mitigate any expected failures.
Additionally, the proposed change is consistent with the allowances that are currently in TS 3.4.8, "RCS Loops - Mode 5, Loops Not Filled," which is consistent with the plant condition allowed by TS 3.9.5. The proposed changes are consistent with NRG-approved TSTF-361, Revision 2. Based on the above, the NRC staff finds that the safe operation of the facility is maintained if one RHR loop is removed from service, as proposed by the licensee, for up to two hours with the other RHR loop in operation.
Based on that the safe operation of the facility is maintained with the proposed changes, the NRC staff concludes that the proposed changes to TS LCO 3.9.5 meet the requirements of 10 CFR 50.36, and, therefore, are acceptable.
3.1.3 TSTF-438-A, Revision 0 The NRC staff's assessment for TSTF-438-A, Revision 0, is documented in a letter to the Nuclear Energy Institute, dated October 21, 2002 (ADAMS Accession No. ML022940574).
TSTF-438-A, Revision 0, revises the note which was added by adopting TSTF-349-A, Revision 1. TSTF-438, Revision 0, revises the wording of the note from "may be de-energized",
to "may be removed from operation." The proposed change to TS 3.9.5 is consistent with NRG-approved TSTF-438, Revision 0. This proposed change does not alter the intent of the note, does not affect any safety analysis assumptions, and does not alter any methods of plant operation. The proposed revisions are editorial and do not change the intent of TS LCO 3.9.5.
The proposed change is editorial in nature and does not change the intent of TS 3.9.5, therefore, the safe operation of the facility is maintained. Based on that the safe operation of the facility is maintained with the proposed change, the NRC staff concludes that the proposed change to TS LCO 3.9.5 meets the requirements of 10 CFR 50.36, and, therefore, is acceptable.
3.2 NRC Staff Conclusion
The NRC staff evaluated the proposed changes to TS LCO 3.9.5 against the applicable regulations and guidance and found that the TS changes are consistent with those in the previously approved TSTF-349-A, Revision 1, TSTF-361-A, Revision 2, and TSTF-438-A, Revision 0, and continue to ensure safe operation of the facility. The NRC staff concludes the proposed changes meet the requirements of 10 CFR 50.36 and, therefore, are acceptable.
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 1, 2017. The State official confirmed on September 1, 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 19101: 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: D. Woodyatt, NRR R. Grover, NRR Date of issuance: September 29, 2017
ML17249A135 *b memorandum OFFICE DORL/LPL2-1 /PM DORL/LPL2-1 /LA DSS/STSB/BC* DSS/SRXB/BC*
KGoldstein NAME MMahoney (SRohrer for) JWhitman EOesterle DATE 09/08/17 09/06/17 07/12/17 07/19/17 OFFICE OGC-NLO DORL/LPL2-1/BC DORL/LPL2-1 /PM JWachutka MMarkley MMahoney NAME (MOrenak for) (RHall for)
DATE 09/19/17 09/29/17 09/29/17