ML18277A322
| ML18277A322 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 11/19/2018 |
| From: | Michael Mahoney Plant Licensing Branch II |
| To: | Teresa Ray Duke Energy Carolinas |
| Mahoney M, NRR/DORL/LPL2-1, 415-3867 | |
| References | |
| EPID L-2018-LLA-0165 | |
| Download: ML18277A322 (19) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 19, 2018 Mr. Thomas D. Ray Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078-8985
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS TO REVISE TECHNICAL SPECIFICATIONS 3.1.7, "ROD POSITION INDICATION," TO ADOPT TSTF-234-A, REVISION 1, "ADD ACTION FOR MORE THAN ONE [D]RPI INOPERABLE" (EPID L-2018-LLA-0165)
Dear Mr. Ray:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 310 to Renewed Facility Operating License No. NPF-9 and Amendment No. 289 to Renewed Facility Operating License No. NPF-17 for the McGuire Nuclear Station, Units 1 and 2 (McGuire),
respectively. The amendments are in response to your application dated May 31, 2018.
The amendments modified Technical Specification 3.1.7, "Rod Position Indication," to add a new Condition for more than one inoperable digital rod position indication (DRPI) per rod group, and revise the Actions Note and to clarify the wording of current Required Actions A.1 and B.1.
This change is consistent with NRG-approved Technical Specification Task Force (TSTF)
Traveler TSTF-234-A, "Add Action for More Than One [D]RPI Inoperable," Revision 1.
T. Ray A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Michael Mahoney, Projec Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosures:
- 1. Amendment No. 31 Oto NPF-9
- 2. Amendment No. 289 to NPF-17
- 3. Safety Evaluation cc: Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-369 MCGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 310 Renewed License No. NPF-9
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility), Renewed Facility Operating License No. NPF-9, filed by Duke Energy Carolinas, LLC (the licensee), dated May 31, 2018, 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-9 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 310, are hereby incorporated into this renewed operating license. The licensee 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 30 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-9 and Technical Specifications Date of Issuance: November 1 9 , 2 O1 8
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-370 MCGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 289 Renewed License No. NPF-17
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility), Renewed Facility Operating License No. NPF-17, filed by the Duke Energy Carolinas, LLC (the licensee), dated May 31, 2018, 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-17 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 289, are hereby incorporated into this renewed operating license. The licensee 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 30 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-17 and Technical Specifications Date of Issuance: November 1 9, 2 O1 8
ATTACHMENT MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 LICENSE AMENDMENT NO. 310 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND LICENSE AMENDMENT NO. 289 RENEWED FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 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-9, page 3 NPF-9, page 3 NPF-17, page 3 NPF-17, page 3 Replace the following pages of the Appendix A Technical Specifications (TSs) 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 3.1.7-1 TS 3.1.7-1 TS 3.1.7-2 TS 3.1.7-2 TS 3.1.7-3
(4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of McGuire Nuclear Station, Units 1 and 2, and; (6) Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at a reactor core full steady state power level of 3469 megawatts thermal (100%).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 310, are hereby incorporated into this renewed operating license. The licensee 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 June 12, 2021, 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.
Renewed License No. NPF-9 Amendment No. 310
(4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts, 30, 40 and 70, to possess, but not separate, such byproducts and special nuclear materials as my be produced by the operation of McGuire Nuclear Station, Units 1 and 2; and, (6) Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such by product material as may be produced by the Duke Training and Technology Center.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or thereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at a reactor core full steady state power level of 3469 megawatts thermal (100%).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 289, are hereby incorporated into this renewed operating license. The licensee 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 March 3, 2023, 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.
Renewed License No. NPF-17 Amendment No. 289
Rod Position Indication 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication LCO 3.1.7 The Digital Rod Position Indication (DRPI) System and the Demand Position Indication System shall be OPERABLE.
APPLICABILITY: MODES 1 and 2.
ACTIONS
NOTE----------------------------------------------------------
Separate Condition entry is allowed for each inoperable rod position indicator and each demand position indicator.
CONDITION REQUIRED ACTION COMPLETION TIME A. One DRPI per group A.1 Verify the position of the Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable for one or rods with inoperable more groups. position indicators indirectly by using movable incore detectors.
OR A.2 Reduce THERMAL 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> POWER to~ 50% RTP.
B. More than one DRPI per 8.1 Place the control rods Immediately group inoperable. under manual control.
AND 8.2 Monitor and Record RCS Once per 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Tavg-AND (continued)
McGuire Units 1 and 2 3.1.7-1 Amendment Nos. 310/289
Rod Position Indication 3.1.7 CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Verify the position of the Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> rods with inoperable position indicators indirectly by using the moveable incore detectors.
AND 8.4 Restore inoperable 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> position indicators to OPERABLE status such that a maximum of one DRPI per group is inoperable.
C. One or more rods with C. 1 Verify the position of the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> inoperable position rods with inoperable indicators have been position indicators indirectly moved in excess of by using movable incore 24 steps in one direction detectors.
since the last determination of the OR rod's position.
C.2 Reduce THERMAL 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> POWER to~ 50% RTP.
D. One demand position D.1.1 Verify by administrative Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> indicator per bank means all DRPls for the inoperable for one or affected banks are more banks. OPERABLE.
AND D.1.2 Verify the most withdrawn Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> rod and the least withdrawn rod of the affected banks are
~ 12 steps apart.
OR D.2 Reduce THERMAL 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> POWER to~ 50% RTP.
(continued)
McGuire Units 1 and 2 3.1.7-2 Amendment Nos. 310/289
Rod Position Indication 3.1.7 CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and 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 /> associated Completion Time not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1. 7.1 Verify each DRPI agrees within 12 steps of the group Once prior to demand position for the full indicated range of rod travel. criticality after each removal of the reactor head McGuire Units 1 and 2 3.1.7-3 Amendment Nos. 310/289
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 310 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-9 AND AMENDMENT NO. 289 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-17 DUKE ENERGY CAROLINAS, LLC DOCKET NOS. 50-369 AND 50-370
1.0 INTRODUCTION
By letter to the U.S. Nuclear Regulatory Commission (NRC, Commission) dated May 31, 2018, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18159A035), Duke Energy Carolinas, LLC (Duke Energy, the licensee) submitted an application to seek approval to change the Technical Specifications (TSs) for the McGuire Nuclear Station (McGuire), Units 1 and 2.
The amendments revise TS 3.1.7, "Rod Position Indication", to add a new Condition for more than one inoperable digital rod position indication (DRPI) per rod group, and revise the Actions Note and to clarify the wording of current Required Actions A.1 and B.1. This change is consistent with NRG-approved Technical Specification Task Force (TSTF) Traveler TSTF-234-A, "Add Action for More Than One [D]RPI Inoperable," Revision 1 (ADAMS Accession No. ML040580468).
Additionally, current TS 3.1 :7, Conditions B, C and Dare renamed as Conditions C, D, and E (respectively) and Required Actions A.1 and B.1 (renamed as C.1) have been modified to reflect that the verification of the position of the rods with inoperable position indicators can be done indirectly by using movable incore detectors.
The licensee also included, in the license amendment request, its TS Bases changes for the proposed changes to the TSs. These changes were presented for information only because these changes are controlled through TS 5.5.14, "Technical Specification (TS) Bases Change Program." The NRC staff reviewed the changes and confirmed they were consistent with the changes in TSTF-234-A, Revision 1.
Enclosure 3
2.0 REGULATORY EVALUATION
2.1 System Descriptions and Requirements Updated Final Safety Analysis Report (UFSAR), Section 7.7.1.3.2 (ADAMS Accession No. ML041190222), provides a description of the Digital Rod Position Indication System, and it states, in part, that:
It [Digital Rod Position Indication System] measures the actual position of each full length rod using a detector which consists of 42 discrete coils mounted concentric with the rod drive pressure housing. The coils are located axially along the pressure housing on 3.75 inch spacing. They magnetically sense the entry and presence of the rod drive shaft through its center line. The coils are interlaced into two data channels, and are connected to the Containment electronics (Data A and B) by separate multiconductor cables. Multiplexing is used to transmit the digital position signals from the Containment electronics to the digital rod position indication cabinet. The digital position signal is displayed on the main control board by light-emitting-diodes (LED) for each full length control rod. By employing two separate channels of information, the digital rod position indication system can continue to function (at reduced accuracy) when one channel fails.
Included in the system is a rod at bottom signal that operates a local alarm and a Control Room annunciator.
Section 7.7.1.3.2, of the UFSAR, also provides a description of the Demand Position Indication System, and states, in part, that:
The demand position indication system counts pulses generated in the Rod Control System to provide a digital readout of the demanded bank position.
The demand position and digital rod position indication systems are separate systems; each serves as backup for the other. Operating procedures require the reactor operator to compare the demand and actual reading from the rod position indicating system so as to verify proper operation of the rod control system.
2.2 Licensee's Proposed Changes Current TS 3.1. 7, Actions Note, states:
Separate Condition entry is allowed for each inoperable rod position indicator per group and each demand position indicator per bank.
Revised TS 3.1. 7, Actions Note, would state:
Separate Condition entry is allowed for each inoperable rod position indicator and each demand position indicator.
Current TS 3.1.7, Condition A, Required Action A.1, states:
Verify the position of the rods with inoperable position indicators by using movable incore detectors.
Revised TS 3.1. 7, Condition A, Required Action A.1, would state:
Verify the position of the rods with inoperable position indicators indirectly by using movable incore detectors.
Current TS 3.1. 7, Condition B, Required Action B.1, states:
Verify the position of the rods with inoperable position indicators by using movable incore detectors.
New Condition B, "More than one DRPI per group inoperable" with its associated Required Actions B.1, B.2, B.3, B.4 and associated Completion Times is added, as shown below.
CONDITION REQUIRED ACTION COMPLETION TIME B. More than one DRPI B.1 Place the control rods Immediately per Group inoperable. under manual control.
AND B.2 Monitor and Record RCS Once per 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Tavg [Reactor Coolant System average tempature].
AND B.3 Verify the position of the Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> rods with inoperable position indicators indirectly by using the movable incore detectors.
AND B.4 Restore inoperable position 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> indicators to OPERABLE status such that a maximum of one DRPI per i:iroup is inoperable.
Current Condition Bis renamed Condition C and revised TS 3.1.7, Condition C, Required Action C.1, would state:
Verify the position of the rods with inoperable position indicators indirectly by using movable incore detectors.
Current Conditions C and Dare renamend as D and E, respectively, with no changes.
2.3 Applicable Regulations and Guidance Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36 requires TSs for nuclear reactors to include items in the following categories: (1) Safety limits [SLs], 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.
Paragraph 10 CFR 50.36(c)(2), "Limiting conditions for operation [LCO]," states, in part, (i)
Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met.
NUREG-1431, Revision 4, "Standard Technical Specifications [STS] - Westinghouse Plants,"
issued in April 2012 (ADAMS Accession No. ML12100A222), contains the staff's guidance for format and content of TSs for plants with Nuclear Steam Supply Systems (NSSS) similar to those of McGuire.
3.0 TECHNICAL EVALUATION
In adopting the Standard Technical Specifications (STS) or a TSTF traveler, licensees propose revisions to their licensed nuclear reactor facility TSs to: (1) incorporate revised NRC policy and guidance regarding the content and format of TSs, (2) clarify a specification's intent by revising ambiguous language and correcting editorial errors, and (3) enhance specifications to correct inadequacies.
Revision 1 of TSTF-234-A, allows for more than one DRPI to be inoperable for a maximum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, given that other indirect means of monitoring changes in rod position are available.
This provides sufficient time to restore operability while minimizing shutdown transients during the time that the position indication is degraded.
The proposed change is consistent with TSTF-234-A, Revision 1, which allows verification of core peaking factors and shutdown margin to satisfy the action requirements, providing the non-indicating rods have not been moved. The additional time to restore an inoperable DRPI is appropriate because the proposed action would require that the control rods be under manual control, that RCS Tavg be monitored and recorded hourly, and that rod position be verified indirectly every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, thereby assuring that the rod alignment and rod insertion LCOs are met. Therefore, the required shutdown margin will be maintained. Given the alternate position monitoring requirement, and other indirect means of monitoring changes in rod position (e.g.,
alarms on average versus reference temperature deviation), a 24-hour CT to restore all but one DRPI per group provides sufficient time to restore operability while minimizing shutdown transients during the time that the position indication system is degraded.
In letter dated May 31, 2018, letter, the licensee stated, consistent with TSTF-234-A, Revision 1, when more than one DRPI per group is inoperable, the TSs will require that the control rods be placed under manual control, the RCS Tavg be monitored and recorded hourly, and the rod position to be verified indirectly every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The proposed change requires the use of the movable incore detectors as an indirect means of monitoring changes in rod position in order to
assure that the rod alignment and rod insertion LCOs are met, consistent with TSTF-234-A, Revision 1.
- Changing current Conditions B, C, and D, with associated Required Actions and CTs is an administrative change and is, therefore, acceptable.
The licensee cited two differences between the proposed changes and the approved traveler in Section 2.2 of its May 31, 2018, letter. The two differences are: (1) The McGuire, Units 1 and 2, Section 3.1 TS numbers are different from the Improved Standard Technical Specifications (ISTS); and (2) TSTF-234-A, Revision 1, contains the bracketed text"[, or 8.1, as applicable]" in the TS Bases discussion for Condition C. The first difference is acceptable since McGuire, Units 1 and 2, TS 3.1. 7, "Rod Position Indication," is analogous to Specification 3.1.8 in the ISTS. The second difference is acceptable because it is not necessary to provide direction in the TS Bases that all applicable Conditions must be entered. The NRC staff evaluated these differences and determined they are acceptable because they are either administrative in nature or unnecessary.
Based on the above evaluation, the NRC staff concludes that the requirements of 10 CFR 50.36(c)(2) continue to be met because 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. Therefore, the staff finds that the proposed changes to TS 3.1. 7, are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, NRC staff notified the North Carolina State official of the proposed issuance of the amendments on October 4, 2018. The State official confimed on October 4, 2018, that the State of North 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 (83 FR 43904: August 28, 2018). 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 M. Mahoney, NRR Date of issuance: November 19, 2018
ML18277A322 OFFICE DORL/LPL2-1/PM DORL/LPL2-1 /LA DSS/STSB/BC DSS/SRXB/BC NAME MMahoney KGoldstein VCusamano JWhitman DATE 10/15/18 10/15/18 10/16/18 10/22/18 OFFICE OGC- NLO DORL/LPL2-1/BC DORL/LPL2-1 /PM AGhosh (subject to NAME comments) MMarkley MMahoney DATE 11/08/18 11/19/18 11/19/18