ML20239A791
| ML20239A791 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 10/28/2020 |
| From: | Kimberly Green Plant Licensing Branch II |
| To: | Jim Barstow Tennessee Valley Authority |
| Green K | |
| References | |
| EPID L-2020-LLA-0068 | |
| Download: ML20239A791 (22) | |
Text
October 28, 2020 Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 137 AND 43 REGARDING REVISION TO TECHNICAL SPECIFICATIONS TO ADOPT TECHNICAL SPECIFICATION TASK FORCE TRAVELER 541, REVISION 2, ADD EXCEPTIONS TO SURVEILLANCE REQUIREMENTS FOR VALVES AND DAMPERS LOCKED IN THE ACTUATED POSITION (EPID L-2020-LLA-0068)
Dear Mr. Barstow:
The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 137 to Facility Operating License No. NPF-90 and Amendment No. 43 to Facility Operating License No. NPF-96 for the Watts Bar Nuclear Plant, Units 1 and 2, respectively. These amendments are in response to your application dated April 3, 2020.
The amendments revise certain Technical Specification Surveillance Requirements (SRs) to add exceptions that consider the SR to be met when automatic valves or dampers are locked, sealed, or otherwise secured in the actuated position. The revisions are consistent with Technical Specification Task Force Traveler 541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position.
A copy of our related safety evaluation is also enclosed. Notice of issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Kimberly J. Green, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-390 and 50-391
Enclosures:
- 1. Amendment No. 137 to NPF-90
- 2. Amendment No. 43 to NPF-96
- 3. Safety Evaluation cc: Listserv
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 137 License No. NPF-90
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (TVA, the licensee) dated April 3, 2020, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations 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 Commissions regulations; 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 Commissions regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-90 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 137 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of the date of its issuance, and shall be implemented with 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Undine Shoop, Chief Plant Licensing Branch II-2 Division of operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License and Technical Specifications Date of Issuance: October 28, 2020 Undine S.
Shoop Digitally signed by Undine S. Shoop Date: 2020.10.28 10:41:16 -04'00'
ATTACHMENT TO AMENDMENT NO. 137 WATTS BAR NUCLEAR PLANT, UNIT 1 FACILITY OPERATING LICENSE NO. NPF-90 DOCKET NO. 50-390 Replace page 3 of Facility Operating License No. NPF-90 with the attached revised page 3.
Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 3.6-25 3.6-25 3.7-24 3.7-24 3.7-28 3.7-28
Amendment No. 137 Facility License No. NPF-90 (4)
TVA, 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, instrument calibration, or other activity associated with radioactive apparatus or components; and (5)
TVA, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commissions 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 TVA is authorized to operate the facility at reactor core power levels not in excess of 3459 megawatts thermal.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 137 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Safety Parameter Display System (SPDS) (Section 18.2 of SER Supplements 5 and 15)
Prior to startup following the first refueling outage, TVA shall accomplish the necessary activities, provide acceptable responses, and implement all proposed corrective actions related to having the Watts Bar Unit 1 SPDS operational.
(4)
Vehicle Bomb Control Program (Section 13.6.9 of SSER 20)
During the period of the exemption granted in paragraph 2.D.(3) of this license, in implementing the power ascension phase of the approved initial test program, TVA shall not exceed 50% power until the requirements of 10 CFR 73.55(c)(7) and (8) are fully implemented. TVA shall submit a letter under oath or affirmation when the requirements of 73.55(c)(7) and (8) have been fully implemented.
Watts Bar-Unit 1 3.6-25 Amendment 132, 137 EGTS 3.6.9 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.9.3 Verify each EGTS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.
In accordance with the Surveillance Frequency Control Program SR 3.6.9.4 Verify each EGTS train produces a flow rate 3600 and 4400 cfm within 20 seconds from the initiation of a Containment Isolation Phase A signal.
In accordance with the Surveillance Frequency Control Program
Watts Bar-Unit 1 3.7-24 Amendment 70, 94, 132, 137 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME H.
Two CREVS trains inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B or E.
H.1 Enter LCO 3.0.3 Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CREVS train for 15 minutes.
In accordance with the Surveillance Frequency Control Program SR 3.7.10.2 Perform required CREVS filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
In accordance with the VFTP SR 3.7.10.3 Verify each CREVS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.
In accordance with the Surveillance Frequency Control Program SR 3.7.10.4 Perform required CRE unfiltered air inleakage testing in accordance with the Control Room Habitability Program.
In accordance with the Control Room Envelope Habitability Program
ABGTS 3.7.12 Watts Bar-Unit 1 3.7-28 Amendment 92, 115, 132, 137 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.1 Operate each ABGTS train for 15 continuous minutes with the heaters operating.
In accordance with the Surveillance Frequency Control Program SR 3.7.12.2 Perform required ABGTS filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
In accordance with the VFTP SR 3.7.12.3 Verify each ABGTS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position In accordance with the Surveillance Frequency Control Program SR 3.7.12.4 Verify one ABGTS train can maintain a pressure between -0.25 and -0.5 inches water gauge with respect to atmospheric pressure during the post accident mode of operation at a flow rate 9300 and 9900 cfm.
In accordance with the Surveillance Frequency Control Program
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-391 WATTS BAR NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. NPF-96
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (TVA, the licensee) dated April 3, 2020, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations 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 Commissions regulations; 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 Commissions regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-96 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 43 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of the date of its issuance, and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Undine Shoop, Chief Plant Licensing Branch II-2 Division of operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License and Technical Specifications Date of Issuance: October 28, 2020 Undine S.
Shoop Digitally signed by Undine S. Shoop Date: 2020.10.28 11:11:01 -04'00'
ATTACHMENT TO AMENDMENT NO. 43 WATTS BAR NUCLEAR PLANT, UNIT 2 FACILITY OPERATING LICENSE NO. NPF-96 DOCKET NO. 50-391 Replace page 3 of Facility Operating License No. NPF-96 with the attached revised page 3.
Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 3.6-23 3.6-23 3.7-23a 3.7-23a 3.7-27 3.7-27 Unit 2 Facility Operating License No. NPF-96 Amendment No. 43 C.
The license shall be deemed to contain and is subject to the conditions specified in the Commissions 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 TVA is authorized to operate the facility at reactor core power levels not in excess of 3549 megawatts thermal.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 43 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
TVA shall implement permanent modifications to prevent overtopping of the embankments of the Fort Loudon Dam due to the Probable Maximum Flood by June 30, 2018.
(4)
PAD4TCD may be used to establish core operating limits until the WBN Unit 2 steam generators are replaced with steam generators equivalent to the existing steam generators at WBN Unit 1.
(5)
By December 31, 2019, the licensee shall report to the NRC that the actions to resolve the issues identified in Bulletin 2012-01, Design Vulnerability in Electrical Power System, have been implemented.
(6)
The licensee shall maintain in effect the provisions of the physical security plan, security personnel training and qualification plan, and safeguards contingency plan, and all amendments made pursuant to the authority of 10 CFR 50.90 and 50.54(p).
(7)
TVA shall fully implement and maintain in effect all provisions of the Commission approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The TVA approved CSP was discussed in NUREG-0847, Supplement 28, as amended by changes approved in License Amendment No. 7.
(8)
TVA shall implement and maintain in effect all provisions of the approved fire protection program as described in the Fire Protection Report for the facility, as described in NUREG-0847, Supplement 29, subject to the following provision:
EGTS 3.6.9 Watts Bar - Unit 2 3.6-23 Amendment 36, 43 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.9.3 Verify each EGTS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.
In accordance with the Surveillance Frequency Control Program SR 3.6.9.4 Verify each EGTS train produces a flow rate 3600 cfm and 4400 cfm within 20 seconds from the initiation of a Containment Isolation Phase A signal.
In accordance with the Surveillance Frequency Control Program
CREVS 3.7.10 Watts Bar - Unit 2 3.7-23a Amendment 36, 43 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.7.10.3 Verify each CREVS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.
In accordance with the Surveillance Frequency Control Program SR 3.7.10.4 Perform required CRE unfiltered air inleakage testing in accordance with the Control Room Envelope Habitability Program.
In accordance with the Control Room Envelope Habitability Program
ABGTS 3.7.12 Watts Bar - Unit 2 3.7-27 Amendment 15, 36, 43 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.12.1 Operate each ABGTS train for 15 continuous minutes with the heaters operating.
In accordance with the Surveillance Frequency Control Program SR 3.7.12.2 Perform required ABGTS filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
In accordance with the VFTP SR 3.7.12.3 Verify each ABGTS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.
In accordance with the Surveillance Frequency Control Program SR 3.7.12.4 Verify one ABGTS train can maintain a pressure between -0.25 inches and -0.5 inches water gauge with respect to atmospheric pressure during the post accident mode of operation at a flow rate 9300 cfm and 9900 cfm.
In accordance with the Surveillance Frequency Control Program
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 137 AND 43 TO FACILITY OPERATING LICENSE NOS. NPF-90 AND NPF-96 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-390 AND 50-391
1.0 INTRODUCTION
By letter dated April 3, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20097D315), the Tennessee Valley Authority (TVA, licensee) submitted a license amendment request (LAR) for Watts Bar Nuclear Plant (WBN), Units 1 and 2.
Limiting Conditions for Operation (LCOs) in the Technical Specifications (TSs) identify the lowest functional capability or performance level of equipment required for safe operation of the facility. To ensure a plant meets the LCOs, several existing surveillance requirements (SRs) require the licensee to verify that each train of specified trains actuates on an actual or simulated actuation signal. The amendments would revise certain SRs by adding, except for automatic valves or dampers that are locked, sealed, or otherwise secured in the actuated position.
The proposed amendments are based on Technical Specifications Task Force (TSTF) Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position, dated August 28, 2019 (ADAMS Accession No. ML19240A315). The U.S. Nuclear Regulatory Commission (NRC or the Commission) approved TSTF-541, Revision 2, by letter dated December 10, 2019 (ADAMS Package Accession No. ML19323E957). The NRC staffs safety evaluation (SE) of the traveler is included with the NRC staffs approval letter.
The licensee has proposed variations from the TS changes described in Traveler TSTF-541, Revision 2. The variations are described in Section 2.2.1 of this SE and evaluated in Section 3.1.
2.0 REGULATORY EVALUATION
2.1 System Descriptions Consistent with Traveler TSTF-541, the licensee has proposed revising SR 3.6.9.3, SR 3.7.10.3, and SR 3.7.12.3, which concern the emergency gas treatment system (EGTS) trains, emergency ventilation system (CREVS) trains, and auxiliary building gas treatment system (ABGTS) trains, respectively.
LCO 3.6.9 requires two EGTS trains to be operable in MODES 1, 2, 3, and 4. Currently, SR 3.6.9.3 requires the licensee to [v]erify each EGTS train actuates on an actual or simulated actuation signal. The emergency gas treatment system (EGTS) air cleanup subsystem is required to ensure that radioactive materials that leak from the primary containment into the shield building (secondary containment) following a design-basis accident (DBA) are filtered and adsorbed prior to exhausting to the environment. The containment has a secondary containment called the shield building, which is a concrete structure that surrounds the steel primary containment vessel. Between the containment vessel and the shield building inner wall is an annular space that collects any containment leakage that may occur following a loss-of-coolant accident (LOCA). The EGTS establishes a negative pressure in the annulus between the shield building and the steel containment vessel. Filters in the system then control the release of radioactive contaminants to the environment. The EGTS consists of two separate and redundant trains. Each train includes a heater, cooling coils, a prefilter, moisture separators, a high-efficiency particulate air (HEPA) filter, an activated charcoal adsorber section for removal of radioiodines, and a fan. Ductwork, valves or dampers, and instrumentation also form part of the system. The system initiates and maintains a negative air pressure in the shield building by means of filtered exhaust ventilation of the shield building following receipt of a safety injection signal. The purpose of SR 3.6.9.3 is to verify proper actuation of all train components, including dampers, on an actual or simulated actuation signal.
LCO 3.7.10 requires two CREVS trains to be operable in MODES 1, 2, 3, 4, 5, and 6, and during movement of irradiated fuel assemblies. Currently, SR 3.7.10.3 requires the licensee to
[v]erify each CREVS train actuates on an actual or simulated actuation signal. The purpose of SR 3.7.10.3 is to verify that each train/subsystem starts and operates on an actual or simulated actuation signal. The CREVS provides a protected environment from which occupants can control the unit following an uncontrolled release of radioactivity, hazardous chemicals, or smoke.
LCO 3.7.12 requires two ABGTS trains to be operable in Modes 1, 2, 3, and 4. Currently, SR 3.7.12.3 requires the licensee to [v]erify each ABGTS train actuates on an actual or simulated actuation signal. The auxiliary building gas treatment system (ABGTS) filters air from the penetration area between containment and the auxiliary building. The ABGTS consists of two independent and redundant trains. Each train consists of a heater, a prefilter or demister, a HEPA filter, an activated charcoal adsorber section for removal of gaseous activity (principally iodines), and a fan. Ductwork, valves or dampers, and instrumentation, as well as demisters, functioning to reduce the relative humidity of the air stream, also form part of the system. The ABGTS is a standby system, parts of which may also operate during normal unit operations.
Upon receipt of the actuating signal(s), the ABGTS dampers are realigned and fans are started to initiate filtration. The purpose of SR 3.7.12.3 is to verify proper actuation of all train components, including dampers, on an actual or simulated actuation signal.
2.2 Description of Proposed Changes The licensee proposed to revise certain SRs by adding exceptions to the SR for automatic valves or dampers that are locked, sealed, or otherwise secured in the actuated position, consistent with the changes described in TSTF-541, Revision 2. The following list denotes the proposed changes to the SRs. The proposed new text containing the exception is shown in italics.
SR 3.6.9.3 Verify each EGTS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.
SR 3.7.10.3 Verify each CREVS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.
SR 3.7.12.3 Verify each ABGTS train actuates on an actual or simulated actuation signal, except for dampers and valves that are locked, sealed, or otherwise secured in the actuated position.
2.2.1 Variations from TSTF-541, Revision 2 The licensee proposed the following variations from the TS changes described in TSTF-541, Revision 2, or the applicable parts of the NRC staffs SE of TSTF-541, Revision 2. The licensee stated that these variations do not affect the applicability of TSTF-541, Revision 2, or the NRC staffs SE to the proposed LAR. These variations are detailed in Section 2.2 of the LAR and are summarized below.
The WBN TSs contain different numbering or titles for three SRs than identified in TSTF-541. For example, the TSTF-541 numbering and title is, SR 3.6.13.3, Shield Building Air Cleanup System (SBACS), and in the WBN TSs, the numbering and title is, SR 3.6.9.3, Emergency Gas Treatment System (EGTS) Air Cleanup Subsystem.
The WBN TSs do not contain several of the SRs equivalent to the SRs affected by TSTF-541.
The WBN TS contain a Surveillance Frequency Control Program. Therefore, the Frequency for the affected SRs is, In accordance with the Surveillance Frequency Control Program.
2.3 Applicable Regulatory Requirements and Guidance Title 10 of the Code of Federal Regulations (10 CFR), Section 50.90, Application for amendment of license, construction permit, or early site permit, requires that whenever a licensee desires to amend the license, application for an amendment must be filed with the Commission fully describing the changes desired, and following as far as applicable, the form prescribed for original applications.
Under 10 CFR 50.92(a), determinations on whether to grant an applied-for license amendment are guided by the considerations that govern the issuance of initial licenses or construction permits to the extent applicable and appropriate. Both the common standards for licenses and construction permits in 10 CFR 50.40(a), and those specifically for issuance of operating licenses in 10 CFR 50.57(a)(3), provide that there must be reasonable assurance that the activities at issue will not endanger the health and safety of the public.
The regulation under 10 CFR 50.36, Technical specifications, establishes the regulatory requirements related to the content of TSs. Section 50.36(a)(1) requires an application for an operating license to include proposed TSs. A summary statement of the bases or reasons for such specifications, other than those covering administrative controls, must also be included in the application, but shall not become part of the TSs.
In accordance with 10 CFR 50.36(c)(2)(i), LCOs are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When LCOs are not met, the licensee must shut down the reactor or follow any remedial action permitted by the TSs until the condition can be met.
SRs are defined in 10 CFR 50.36(c)(3) as requirements relating to test, 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 LCO will be met.
3.0 TECHNICAL EVALUATION
The proposed amendment is based on the NRC-approved TSTF-541, Revision 2. The NRC staffs evaluation of the proposed amendment relies upon the NRC staffs previous approval of TSTF-541, Revision 2. The regulatory framework the NRC staff used to determine the acceptability of the proposed changes consist of the requirements and guidance listed in Section 2.3 of this SE. The NRC staff reviewed the proposed TS changes to determine whether they meet the standards in 10 CFR 50.36(c)(3).
Consistent with TSTF-541, the licensee has proposed revising SR 3.6.9.3, SR 3.7.10.3, and SR 3.7.12.3, which concern the EGTS trains, CREVS trains, and ABGTS trains, respectively. LCO 3.6.9 requires two EGTS trains to be operable in MODES 1, 2, 3, and 4. LCO 3.7.10 requires two CREVS trains to be operable in MODES 1, 2, 3, 4, 5, and 6, and during movement of irradiated fuel assemblies. LCO 3.7.12 requires two ABGTS trains to be operable in Modes 1, 2, 3, and 4. As defined in TS 1.1, a train shall be operable when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
The proposed amended SRs would exclude the need to verify actuation of dampers and valves that do not, in fact, actuate (e.g., change position) in response to an actuation signal. The amended SRs will continue to require the licensee to verify that valves and dampers that must actuate perform their safety functions and support functions by being able to change position.
But the NRC staff finds that it is not necessary to verify actuation of valves and dampers that are already in their actuated positions, and are locked, sealed, or otherwise secured in those positions. Accordingly, the NRC staff determines that the amended WBN TS changes will continue to provide an acceptable way to meet 10 CFR 50.36(c)(3) because the revised SRs will continue to provide assurance that the necessary quality of systems and components is maintained and that the LCOs will be met.
3.1 Variations As discussed in Section 2.2.1 of this SE, the licensee proposed variations from TSTF-541, Revision 2, related to the use of different numbering, titles, and nomenclature. For example, the TSTF-541 numbering and title is, SR 3.6.13.3, Shield Building Air Cleanup System (SBACS),
and in the WBN TSs the numbering and title is, SR 3.6.9.3, Emergency Gas Treatment System (EGTS) Air Cleanup Subsystem. The NRC staff reviewed these variations and finds them acceptable as the differences do not affect the applicability of traveler TSTF-541 to the WBN TSs.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Tennessee State official was notified of the proposed issuance of the amendment on August 14, 2020. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes SRs.
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 previously issued a proposed finding that the amendment involves no significant hazards consideration, published in the Federal Register on May 5, 2020 (85 FR 26731), and there has been no public comment on such finding. 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 amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Josh Wilson, NRR Date: October 28, 2020
- via e-mail OFFICE NRR/DORL/LPL2-2/PM*
NRR/DORL/LPL2-2/LA*
NRR/DSS/STSB/BC*
NAME KGreen BAbeywickrama VCusumano DATE 09/11/2020 09/09/2020 08/21/2020 OFFICE OGC (NLO)*
NRR/DORL/LPL2-2/BC*
NRR/DORL/LPL2-2/PM*
NAME JScro (w/edits)
UShoop KGreen DATE 10/07/2020 10/28/2020 10/28/2020