ML17269A055
| ML17269A055 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 10/25/2017 |
| From: | Michael Mahoney Plant Licensing Branch II |
| To: | Capps S Duke Energy Carolinas |
| Mahoney Michael (301) 415-3867 | |
| References | |
| CAC MF9098, CAC MF9099 | |
| Download: ML17269A055 (19) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 25, 2017 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078-8985
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1AND2 - ISSUANCE OF AMENDMENTS ADOPTING TECHNICAL SPECIFICATION TASK FORCE TRAVELER TSTF 283-A, REVISION 3 (CAC NOS. MF9098 and MF9099)
Dear Mr. Capps:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 300 to Renewed Facility Operating License No. NPF-9 and Amendment No. 279 to Renewed Facility Operating License No. NPF-17 for the McGuire Nuclear Station, Units 1 and 2, respectively.
The amendments are in response to your application dated January 11, 2017.
The amendments modify Technical Specification (TS) 3.8.1, "AC Sources - Operating,n to allow greater flexibility in performing Suiveillance Requirements (SRs) by modifying Mode restriction notes in TS SRs 3.8.1.11, 3.8.1.16, 3.8.1.17, 3.8.1.19, 3.8.4.8, and 3.8.4.9. This proposed change is consistent with Technical Specification Task Force (TSTF) Traveler TSTF-283-A, Revision 3, "Modify Section 3.8 Mode Restriction Notes."
A copy of the related Safety Evaluation is also enclosed.
the Commission's biweekly Federal Register notice.
Notice of Issuance will be included in Docket Nos. 50-369 and 50-370
Enclosures:
- 1. Amendment No. 300 to NPF-9
- 2. Amendment No. 279 to NPF-17
- 3. Safety Evaluation cc w/enclosures: Distribution via Listserv Sincerely,
.***.?"* /
' Ii v
Michael Mahoney, Project 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 DOCKET NO. 50-369 MCGUIRE NUCLEAR STATION UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 300 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 (licensee), dated January 11, 2017, 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-9 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 300, 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 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-9 and Technical Specifications Date of Issuance:
October 25, 2017
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. 279 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 January 11, 2017, 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 1 O CFR Chapter I;
- 8.
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-17 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 279, 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 120 days of issuance.
Attachment:
FOR THE NUCLEAR REGULATORY COMMISSION r-:.e-~....f -;: fa~.U(J 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-17 and Technical Specifications Date of Issuance:
October 25, 2017
ATIACHMENT MCGUIRE NUCLEAR STATION, UNITS 1AND2 LICENSE AMENDMENT NO. 300 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 LICENSE AMENDMENT NO. 279 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 NPF-9, page 3 NPF-17, page 3 Insert NPF-9, page 3 NPF-17, page 3 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 3.8.1-7 TS 3.8.1-9 TS 3.8.1-12 TS 3.8.1-13 TS 3.8.1-14 Insert TS 3.8.1-7 TS 3.8.1-9 TS 3.8.1-12 TS 3.8.1-13 TS 3.8.1-14 (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 1 O 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°/o).
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 300, 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 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 June 12, 2021, and shall notify the NRG in writing when implementation of these activities is complete and can be verified by NRG 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.
Renewed License No. NPF-9 Amendment No. 300 (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. 279, 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 NRG in writing when implementation of these activities is complete and can be verified by NRG 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. 279
AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE SR 3. 8.1. 7
NOTES-------------------------------
SR 3.8.1.8 All DG starts may be preceded by an engine prelube period.
Verify each DG starts from standby condition and achieves in::;; 11 seconds voltage of;:::.: 3740 V and frequency of::::-: '{>7 Hz and maintains steady state voltage
- -: 3740 V and::;; 4580 V, and frequency::::-: 58.8 Hz and
~ 61.2 Hz.
N 0 TES--------------------------------
This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.
Verify automatic and manual transfer of AC power sources from the normal offsite circuit to each alternate offsite circuit.
FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Proo ram (continued)
McGuire Units 1 and 2 3.8.1-7 Amendment Nos. 300/279
AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE SR 3.8.1.11
NOTES--------------------------------
- 1.
All DG starts may be preceded by an engine prelube period.
- 2.
This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.
Verify on an actual or simulated loss of offsite power signal:
- a.
De-energization of emergency buses;
- b.
Load shedding from emergency buses;
- c.
DG auto-starts from standby condition and:
- 1.
energizes the emergency bus in s 11 seconds,
- 2.
energizes auto-connected blackout loads through automatic load sequencer,
- 3.
maintains steady state voltage
~ 3740 V and~ 4580 V,
- 4.
maintains steady state frequency
- 58.8 Hz ands 61.2 Hz, and
- 5.
supplies auto-connected blackout loads for
- 5 minutes.
FREQUENCY In accordance with the Surveillance Frequency Control Program (continued)
McGuire Units 1 and 2 3.8.1-9 Amendment Nos. 300/279
AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS !continued!
SURVEILLANCE SR 3.8.1.15 --------------------------------NOTES------------------------------
- 1.
This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated ~ 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> loaded 2 3600 kW and
<4000 kW.
Momentary transients outside of load range do not invalidate this test.
- 2.
All DG starts may be preceded by an engine prelube period.
Verify each DG starts and achieves, in :-:;; 11 seconds, voltage 2 3740 V, and frequency~ 57 Hz and maintains steady state voltage~ 3740 V and< 4580 V and frequency::::: 58.8 Hz and:-:;; 61.2 Hz.
SR 3. 8.1.16 -------------------------------NOTES---------------------------------
This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.
Verify each DG:
- a.
Synchronizes with offsite power source while loaded with emergency loads upon a simulated restoration of offsite power;
- b.
Transfers loads to offsite power source; and
- c.
Returns to standby operation.
FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
McGuire Units 1 and 2 3.8.1-12 Amendment Nos. 300/279
AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE SR 3.8.1.17
NOTES-------------------------------
This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.
Verify, with a OG operating in test mode and connected to its bus, an actual or simulated ESF actuation signal overrides the test mode by:
- a.
Returning DG to standby operation; and
- b.
Automatically energizing the emergency load from offsite power.
SR 3.8.1.18 Verify interval between each sequenced load block is within design interval for each automatic load sequencer.
FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control ProQram (continued)
McGuire Units 1 and 2 3.8.1-13 Amendment Nos. 300/279
AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE SR 3. 8.1.19 -------------------------------NOTES--------------------------------
- 1.
All DG starts may be preceded by an engine prelube period.
- 2.
This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.
Verify on an actual or simulated loss of offsite power signal in conjunction with an actual or simulated ESF actuation signal:
- a.
De-energization of emergency buses;
- b.
Load shedding from emergency buses; and
- c.
DG auto-starts from standby condition and:
- 1.
energizes the emergency bus in :::;; 11
- seconds,
- 2.
energizes auto-connected emergency loads through load sequencer,
- 3.
achieves steady state voltage::::>: 3740 V and:-:;; 4580 V,
- 4.
achieves steady state frequency;::,.: 58.8 Hz and ~ 61.2 Hz, and
- 5.
supplies auto-connected emergency loads for;::,.: 5 minutes.
FREQUENCY In aacordance with the Surveillance Frequency Control Program (continued)
McGuire Units 1 and 2 3.8.1-14 Amendment Nos. 3001279
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 300 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-9 AND AMENDMENT NO. 279 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-17 DUKE ENERGY CAROLINAS, LLC MCGUIRE NUCLEAR STATION UNITS 1AND2 DOCKET NOS. 50-369 AND 50-370
1.0 INTRODUCTION
By letter dated January 11, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17025A069), Duke Energy Carolinas, LLC (the licensee), submitted a license amendment request (LAR) for the McGuire Nuclear Station, Units 1 and 2 (McGuire),
to adopt multiple Technical Specification Task Force (TSTF) Travelers. This safety evaluation specifically evaluates the adoption of TSTF-283-A, Revision 3, "Modify Section 3.8 Mode Restriction Notes," for McGuire.
TSTF Traveler 283-A, Revision 3, "Modify Section 3.8 Mode Restriction Notes," introduced a modification of the mode restriction note at the top of 14 different surveillance requirements (SRs) in the NUREG-1431, "Standard Technical Specifications: Westinghouse Plants." The licensee has chosen to adopt five of the modifications.
Specifically, McGuire Technical Specification (TS) 3.8.1, "AC Sources Operating" SRs are modified by changing the mode restriction note to allow portions of the SRs to be performed to reestablish operability provided an assessment determines the safety of the plant is maintained or enhanced. Additionally, each SR is modified by adding a sentence that allows credit to be taken for unplanned events that satisfy the SR.
2.0 REGULATORY EVALUATION
2.1 Applicable Regulations and Guidance In Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, the U.S. Nuclear Regulatory Commission (NRC or Commission) 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 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 TS.
As discussed in 10 CFR 50.36(c)(3), SRs are requirements relating to testing, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met.
NUREG-1431 contains the standardized technical specifications for the Westinghouse fleet.
NUREG-1431, September 1992 (ADAMS Accession No. ML13196A330), was developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, published July 22, 1993 (58 FR 39132), and these criteria were subsequently codified by changes to 10 CFR 50.36 (60 FR 36953).
2.2 Proposed Changes McGuire SR 3.8.1.8 currently limits performance of the SR to plant operating modes other than Modes 1 or2, by an existing note, SRs 3.8.1.11, 3.8.1.16, 3.8.1.17, and 3.8.1.19 currently limit performance of the SR to plant operating modes other than Modes 1, 2, 3, or 4 by an existing note. The adoption of TSTF-283-A, Revision 3, will revise the SR notes to state that while the SRs are normally prohibited "in Modes 1 and 2" (for SR 3.8.1.8) or "in Modes 1, 2, 3, or 4," (for SRs 3.8.1.11, 3.8.1.16, 3.8.1.17, and 3.8.1.19) they may be performed to reestablish operability provided an assessment determines the safety of the plant is maintained or enhanced. The NRC staff approved the changes in TSTF-283-A, Revision 3, by incorporating them into Revision 2 of NUREG-1431, '"Standard Technical Specifications: Westinghouse Plants," April 2001 (ADAMS Accession No. ML011090393).
In addition to the above changes in TSTF-283-A, Revision 3, the licensee proposed to modify each SR by adding a sentence to clarify that credit may be taken for unplanned events that satisfy the SR. These changes were also included in all versions of NUREG-1431, uStandard Technical Specifications: Westinghouse Plants," including the current revision, Revision 4, April 2012 (ADAMS Accession No. ML 121 OOA222).
Current SR 3.8.1.8 Note states:
This Surveillance shall not be performed in MODE 1 or 2.
Revised SR 3.8.1.8 Note 2 would state:
This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.
Current SR 3.8.1.11 Note 2 states:
This Surveillance shall not be performed in MODE 1, 2, 3 or 4.
Revised SR 3.8.1.11 Note 2 would state:
This Surveillance shall not normally be performed in MODE 1, 2, 3 or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.
Current SR 3.8.1.16 Note states:
This Surveillance shall not be performed in MODE 1, 2, 3 or 4.
Revised SR 3.8.1.16 Note would state:
This Surveillance shall not normally be performed in MODE 1, 2, 3 or 4. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.
Current CNS SR 3.8.1.17 Note states:
This Surveillance shall not be performed in MODE 1, 2, 3 or 4.
Revised SR 3.8.1.17 Note would state:
This Surveillance shall not normally be performed in MODE 1, 2, 3 or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.
Current SR 3.8.1.19 Note 2 states:
This Surveillance shall not be performed in MODE 1, 2, 3 or 4.
Revised SR 3.8.1.19 Note 2 would state:
This Surveillance shall not normally be performed in MODE 1, 2, 3 or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.
The licensee did not propose changes to McGuire SRs 3.8.1-9, 3.8.1-10, 3.8.1-12, 3.8.1-13, 3.8.1-14, 3.8.1-18, 3.8.4.6, 3.8.4.7, and 3.8.4-8 even though they were included as changes in TSTF-283-A, Revision 3. The licensee stated that these SRs do not include Notes restricting the MODES in which the SR may be performed, therefore, the changes that provide exceptions to the Mode restrictions are not necessary and are not proposed to be adopted.
3.0 TECHNICAL EVALUATION
Duke Energy proposed a revision to the McGuire SRs 3.8.1.8, 3.8.1.11, 3.8.1.16, 3.8.1.17, and 3.8.1.19. McGuire SR 3.8.1.8 currently limits performance of the SR to plant operating modes other than Modes 1 or2, by an existing note. SRs 3.8.1.11, 3.8.1.16, 3.8.1.17, and 3.8.1.19 currently limit performance of the SR to plant operating modes other than Modes 1, 2, 3, or 4 by an existing note. The notes are modified to state that while normally prohibited "in Modes 1 and 2" (for SR 3.8. 1.8) or "in Modes 1, 2, 3, or 4" (for SRs 3.8. 1. 11, 3.8. 1. 16, 3.8. 1. 17, and 3.8.1.19), the surveillances (or portions of) may be performed to reestablish operability provided an assessment determines the safety of the plant is maintained or enhanced.
The NRC staff approved the changes in TSTF-283-A, Revislon 3, by incorporating them into NUREG-1431, Revision 2, issued in April 2001. The intent of TSTF-283-A is to allow some testing of the emergency diesel generators (EDGs) and Class 1 E batteries in modes not currently allowed for the purpose of maintaining or reestablishing system or component operability (e.g., post corrective maintenance testing). Testing is allowed with the provision that the licensee performs a safety assessment that determines the safety of the plant would be maintained or enhanced by conducting the operability testing before the testing begins.
The NRC staff reviewed the proposed changes to the McGuire SRs 3.8. 1.8, 3.8. 1. 11, 3.8. 1. 16, 3.8. 1.17, and 3.8.1.19. The NRC staff finds that the changes are identical to those contained in TSTF-283-A, Revision 3, for SRs 3.8. 1.8, 3.8. 1. 11, 3.8. 1. 16, 3.8. 1. 17, and 3.8. 1. 19. The NRC staff finds that the changes would provide flexibility in outage scheduling and reduce outage critical path time since these EOG and Class 1 E battery surveillance tests would no longer have to be performed during an outage. The changes would not result in any changes to the performance of the SR or the determination of component operability.
In addition, the proposed changes could potentially avoid a plant shutdown and the associated risk if corrective maintenance (planned or unplanned) were performed during power operation. The change will also improve the licensee's flexibility in responding to an event during shutdown when other engineered safety feature equipment may be out of service.
Finally, the deviation to allow credit to be taken for unplanned events that satisfy the SR has been included in all final versions of NUREG-1431. If any unplanned event effectively demonstrates meeting the SR requirement, the licensee may use it to determine the operability of the associated component.
The NRC staff concludes that the requirements of 10 CFR 50.36(c)(3) will continue to be met because the revised SRs provide the appropriate surveillances to ensure the necessary quality of components is maintained and the associated LCOs will be met, ensuring the safe operation of McGuire. Therefore, the NRC staff concludes that the proposed TS changes are acceptable
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the NRC staff notified North Carolina State official of the proposed issuance of the amendments on September 11, 2017. On September 11, 2017, the NRG staff confirmed that the North Carolina State official had no comments.
5.0 PUBLIC COMMENTS On May 23, 2017, the NRG staff published a "Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing," in the Federal Register associated with the proposed amendment request (82 FR 23619). In accordance with the requirements in 10 CFR 50.91, the notice provided a 30~day period for public comment on the proposed no significant hazards consideration determination. One comment from a member of the public was received, however it was not related to the no significant hazards consideration determination nor the LAR. The comment can be found at www.regulations.gov, reference NRC-2017-0120-0002.
6.0 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 23630; June 23, 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.
7.0 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: P. Snyder, NRR Date of issuance: October 25, 2017
ML17269A055 OFFICE DORULPL2-1/PM DORULPL2-1/LA NAME MMahoney KGoldstein/Rohrer /f/
DATE 9/20/17 9/20/17 OFFICE OGC-NLO DORL/LPL2-1/BC NAME DRoth MMarkley DATE 10/16/17 10/25/2017 DSS/STSB/BC AKlein 4/15/17*
DORULPL2-1/PM MMahoney 10/25/2017