ML21015A034

Issuance of Amendment No. 144 Regarding Post Accident Monitoring Instrumentation

ML21015A034
Person / Time
Site:	Watts Bar
Issue date:	03/09/2021
From:	Kimberly Green Plant Licensing Branch II
To:	Jim Barstow Tennessee Valley Authority
Green K
References
EPID L-2020-LLA-0136
Download: ML21015A034 (13)

Text

March 9, 2021 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, UNIT 1 - ISSUANCE OF AMENDMENT NO. 144 REGARDING POST ACCIDENT MONITORING INSTRUMENTATION (EPID L-2020-LLA-0136)

Dear Mr. Barstow:

The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 144 to Facility Operating License No. NPF-90 for the Watts Bar Nuclear Plant, Unit 1. This amendment is in response to your application dated June 22, 2020.

This amendment revises Technical Specification 3.3.3, Post Accident Monitoring (PAM)

Instrumentation, Table 3.3.3-1, to delete the term plasma from the footnotes in the PAM instrumentation table.

A copy of our related safety evaluation is also enclosed. Notice of issuance will be included in the Commissions monthly 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 No. 50-390

Enclosures:

1. Amendment No. 144 to NPF-90

2. Safety Evaluation cc: Listserv

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 144 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 June 22, 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.

Enclosure 1

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. 144 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 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by Undine S. Undine S. Shoop Date: 2021.03.09 Shoop 16:30:43 -05'00' Undine S. 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: March 9, 2021

ATTACHMENT TO AMENDMENT NO. 144 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 page 3.

Replace the following page of the Appendix A Technical Specifications with the attached page.

The revised page is identified by amendment number and contains vertical lines indicating the area of change.

Remove Pages Insert Pages 3.3-45 3.3-45

(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. 144 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.

Facility License No. NPF-90 Amendment No. 144

PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 2 of 2)

Post Accident Monitoring Instrumentation APPLICABLE MODES CONDITION OR OTHER REFERENCED FROM SPECIFIED REQUIRED REQUIRED FUNCTION CONDITIONS CHANNELS/TRAINS ACTION D.1

18. Core Exit Temperature- 1,2,3 2 (e) E Quadrant 2(f)

19. Core Exit Temperature- 1,2,3 2 (e) E (f)

Quadrant 3

20. Core Exit Temperature- 1,2,3 2 (e) E (f)

Quadrant 4

21. Auxiliary Feedwater Flow 1,2,3 2/SG E

22. Reactor Coolant System 1,2,3 2 E (h)

Subcooling Margin Monitor

23. Refueling Water Storage Tank 1,2,3 2 E Water Level

24. Steam Generator Pressure 1,2,3 2/SG E

25. Auxiliary Building Passive Sump 1,2,3 2 E (j)

Level (a) Below the P-10 (Power Range Neutron Flux) interlocks.

(b) Above the P-6 (Intermediate Range Neutron Flux) interlocks.

(c) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(d) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, pressure relief valve, or check valve with flow through the valve secured.

(e) A channel consists of two core exit thermocouples (CETs).

(f) The ICCM provides these functions on a display.

(g) Regulatory Guide 1.97, non-Type A, Category 1 Variables.

(h) This function is displayed on the ICCM display and digital panel meters.

(i) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(j) Watts Bar specific (not required by Regulatory Guide 1.97) non-Type A Category 1 variable.

Watts Bar-Unit 1 3.3-45 Amendment 72, 144

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 144 TO FACILITY OPERATING LICENSE NO. NPF-90 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-390

1.0 INTRODUCTION

By letter dated June 22, 2020, the Tennessee Valley Authority (TVA, the licensee) requested changes to the Watts Bar Nuclear Plant (Watts Bar), Unit 1, Technical Specifications (TSs)

(Agencywide Documents Access and Management System (ADAMS) Accession No. ML20174A546). The proposed changes revise TS 3.3.3, Post Accident Monitoring (PAM)

Instrumentation, Table 3.3.3-1, to delete the term plasma from the footnotes in the PAM instrumentation table. The proposed changes will allow future modifications to upgrade the Inadequate Core Cooling Monitor (ICCM) PAM display, while still meeting the requirements of the PAM instrumentation functions.

2.0 REGULATORY EVALUATION

2.1 System Description The PAM instrumentation for Watts Bar, Unit 1 is required to monitor plant and environs conditions during and following design basis Condition II, III and IV faults as described in the Watts Bar dual-unit Updated Final Safety Analysis Report (UFSAR) Chapter 15 (ADAMS Accession No. ML19176A135). PAM instrumentation enables the Main Control Room operating staff to: take preplanned manual actions; provide information on whether critical safety functions are being accomplished; provide information for potential or actual breach of the barriers to fission product release; provide information of individual safety systems; and provide information on the magnitude of the release of radioactive materials.

The PAM display panel in use at Watts Bar, Unit 1 from original licensing to the present time is a plasma display. The PAM display panel does not perform any calculations or any critical/essential function of the PAM System (PAMS) other than functioning as a visual display.

As described in Section 3.1 of the licensees June 22, 2020, license amendment request (LAR),

the PAMS is a computer-based system that displays the following three post-accident parameters: core exit temperature, reactor vessel level, and subcooled margin.

Enclosure 2

The three parameters displayed by PAMS are key variables as defined by Regulatory Guide (RG) 1.97, Revision 2, Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident (ADAMS Accession No. ML060750525).

2.2 Description of Proposed Changes The licensee proposed the following deletions from the Watts Bar, Unit 1, TS Table 3.3.3-1, Post Accident Monitoring Instrumentation, footnotes. The strikeout feature is used to show the proposed deletion.

(f) The ICCM provides these functions on a plasma display (h) This function is displayed on the ICCM plasma display and digital panel meters.

2.3 Regulatory Requirements and Guidance 2.3.1 Regulatory Requirements The U.S. Nuclear Regulatory Commissions (NRC or Commission) regulations are codified in Title 10 of the Code of Federal Regulations (10 CFR). Appendix A, General Design Criteria for Nuclear Power Plants, of 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, contains the following applicable General Design Criteria (GDC):

GDC 13, Instrumentation and control, states that instrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions as appropriate to assure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment and its associated systems. Appropriate controls shall be provided to maintain these variables and systems within prescribed operating ranges.

GDC 19, Control room, states that a control room shall be provided from which actions can be taken to operate the nuclear power unit safely under normal conditions and to maintain it in a safe condition under accident conditions, including loss-of-coolant accidents. Adequate radiation protection shall be provided to permit access and occupancy of the control room under accident conditions without personnel receiving radiation exposures in excess of 5 rem whole body, or its equivalent to any part of the body, for the duration of the accident. Equipment at appropriate locations outside the control room shall be provided (1) with a design capability for the prompt hot shutdown of the reactor, including necessary instrumentation and controls to maintain the unit in a safe condition during hot shutdown, and (2) with a potential capability for subsequent cold shutdown of the reactor through the use of suitable procedures.

The regulation at 10 CFR 50.34(f)(2)(iii) requires, in part, that control room designs reflect state-of-the-art human factor principles.

Section 50.34(f)(2)(xix) of 10 CFR, requires that control room designs include instrumentation adequate for monitoring plant conditions following an accident that includes core damage.

The regulation at 10 CFR 50.36(b) requires that each license authorizing operation of a production or utilization facility include TSs. More specifically, 10 CFR 50.36(c)(2) requires that the TSs include, among other categories, limiting conditions for operation (LCOs), which are the lowest functional capability or performance levels of equipment required for safe operation of the facility.

2.3.2 Regulatory Guidance Regulatory Guide (RG) 1.97, Revision 2, describes a method that is acceptable to the staff for use in complying with the Commissions regulations to provide instrumentation to monitor plan variables and systems during and following an accident in a light-water-cooled nuclear power plant.

NUREG-0737, Supplement 1, Clarification of [Three Mile Island] TMI Action Plan Requirements, (ADAMS Accession No. ML102560009), provides guidance regarding control room instrument display design, including reference to the design criteria outlined in Regulatory Guide 1.97.

NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: [Light-Water Reactor] LWR Edition, Chapter 18, Human Factors Engineering, Revision 3 (ADAMS Accession No. ML16125A114), provides the regulatory guidance regarding human factors engineering (HFE) considerations for applicants.

NUREG-0711, Human Factors Engineering Program Review Model, Revision 3 (ADAMS Accession No. ML12324A013), provides acceptance criteria for a human factors engineering design process that the NRC staff have found acceptable.

NUREG-0700, Human-System Interface Design Review Guidelines, Revision 2 (ADAMS Accession Nos. ML021700337, ML021700342, and ML021700371), provides guidelines addressing the physical and functional characteristics of human-system interfaces (HSIs).

NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Revision 4, Volume 1 (ADAMS Accession No. ML12100A222), provides an NRC-developed standard set of improved Standard Technical Specifications for Westinghouse plants.

3.0 TECHNICAL EVALUATION

3.1 Staff Evaluation The NRC staff reviewed the licensees LAR and focused on determining whether the TSs, as amended, would continue to meet the regulatory requirements of GDC 13 and GDC 19, using the guidance in RG 1.97, Revision 2, as committed to by TVA. The proposed changes delete the term plasma from footnotes (f) and (h) to TS Table 3.3.3-1 (page 2 of 2), Post Accident Monitoring Instrumentation. The term plasma describes the type of display technology currently used for the ICCM PAM display for Watts Bar, Unit 1.

The NRC staff reviewed the Watts Bar, Unit 1 UFSAR and determined the proposed changes are consistent with the current design basis, and the ICCM PAM display will continue to perform its intended function. The staff confirmed that the PAM display panel does not perform any calculations or any critical/essential function of the PAMS other than visual display.

The NRC staff reviewed the changes to ensure the requirements of GDC 13 are met. Based on its review of the changes, the staff determined that compliance with GDC 13 is not impacted, and the instrumentation will continue to monitor variables and systems over their anticipated ranges with appropriate controls to maintain these variables and systems within prescribed operating ranges. In addition, the staff reviewed the changes to ensure the requirements of GDC 19 are met. Based on its review of the changes, the staff determined that compliance with GDC 19 is not impacted, and the control room will continue to allow actions to be taken to operate the nuclear power unit safely under normal conditions and to maintain it in a safe condition under accident conditions. Therefore, the NRC staff concludes the proposed changes to TS Table 3.3.3-1 Footnotes are acceptable.

3.2 Human Factors Considerations 3.2.1 Licensee Discussion In Section 3.2.1 of the submittal, the licensee discusses the fact that the prescription in the unit TS that the PAMS displays be plasma displays appears to have been originally included to highlight that the latest in display technology was being used at the time the TS was developed.

The licensee communicates, however, that due to technology developments since original design of the PAM display system, plasma displays have become an outmoded technology.

The license also states, in Section 3.2.1 of the submittal, that the plasma display currently prescribed by the TS does not perform any calculations or any critical/essential function of the PAMS other than as a visual display.

In Section 3.2 of the submittal, the licensee states that the requirements for instrumentation used to assess plant and environs conditions during and following an accident at [Watts Bar] are based on satisfying the intent of RG 1.97, as mandated by TVA commitments to comply with NUREG-0737 Supplement 1. The licensee discusses the requirement in RG 1.97 that key variables must be displayed in a manner that allows the control room operators to take the appropriate manual actions. The licensee goes on to state, however, that its review of applicable human factor standards for visual display units indicates no regulatory requirements calling for a specific display technology.

3.2.2 Staff Evaluation NUREG-0711 provides criteria for considering information provided in an application regarding post-accident monitoring, stating that applicants should describe how the HSI assures monitoring of plant and environmental conditions following an accident including core damage.

The licensee has communicated in its submittal that the PAMS display serves the sole function of providing a visual display of the necessary parameters.

NUREG-0700, Revision 2, provides guidance regarding the design of human-system interfaces, including a detailed discussion of the specifications that visual display systems should meet for optimized human performance (such as glare, reflectance, resolution, brightness, and color).

NUREG-0700, Revision 2, Section 1, Information display, mentions possible technologies that can be used for video display units - including plasma panels, light-emitting diode panels, electroluminescent panels, and several others; however, it does not call for anyone particular technology type to be used or preferred.

RG 1.97, Revision 2, provides additional guidance on visual information displays. It states, in Section C, The method of display may be by dial, digital, [cathode ray tube], or stripchart recorder indication. Again however, this guidance does not go so far as to prescribe that any one particular display technology (e.g., a plasma display) be used. The NRC staff notes that RG 1.97 and NUREG-0700, as discussed in the licensees submittal, have since been revised.

The staff also considered the up-to-date guidance contained in these revisions and determined that they do not provide any prescriptions regarding the type of technology used for displays that would prohibit the use of a design that implements a non-plasma display. Based on the non-prescriptive nature of the applicable regulations and associated guidance, the NRC staff determines that there are no regulatory requirements or guidance that call for a specific display technology.

The NRC staff noted that the licensees submittal does not include a proposal for any actual, specific physical changes to any displays, controls, or alarms in the main control room. The proposed change only affects the plant TS limiting the technology that can be used for the PAMS display. As such, any impact on operator actions from the requested change is expected to be minimal, and the NRC staff, therefore, determines that the requested change is unlikely to negatively impact the safe operation of the plant. Any actual physical changes to displays, controls, or alarms implemented by the licensee in the future would be considered separately by NRC staff, in the event that the licensee submits an associated LAR.

3.2.3 Conclusion The NRC staff have reviewed the human factors considerations associated with TVAs request to modify the Watts Bar, Unit 1, TSs for post-accident monitoring instrumentation. The staff determined that that the applicable regulations and associated guidance do not prescribe the use of any specific type of technology for the display systems discussed. In accordance with NRC guidance addressing human factors and human-system interaction design considerations, the staff determined that the changes proposed by the licensee do not relieve any prescriptions associated with a regulatory requirement and will not have any impact on the licensees compliance with the requirements listed in 10 CFR 50.34(f)(2)(iii) and 10 CFR Part 50, Appendix A, GDC 13 and GDC 19. Additionally, the changes described in the licensees submittal do not include any actual changes to the alarms, displays, and controls in the main control room that would be expected to negatively impact operator performance. The staff also determined that the regulatory requirements of 10 CFR 50.36(c)(2) will continue to be met because the LCO will continue to describe the lowest functional capability or performance level of equipment required for safe operation of the facility. Based on these determinations, the NRC staff concludes the proposed changes to TS Table 3.3.3-1 Footnotes are acceptable.

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 26, 2020. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves 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 in the Federal Register on August 25, 2020 (85 FR 52374), and there have been no public comments received. Accordingly, the amendment meets 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 amendment.

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 Contributors: C. Cheung, NRR J. Vazquez, NRR Date: March 9, 2021

ML21015A034 *by e-mail OFFICE NRR/DORL/LPL2-2/PM* NRR/DORL/LPL2-2/LA* NRR/DEX/EICB/BC* NRR/DRO/IOLB/BC*

NAME KGreen BAbeywickrama MWaters (RStattel for) CCowdrey DATE 01/28/2021 01/22/2021 08/25/2020 11/19/2020 OFFICE NRR/DSS/STSB/BC* OGC (NLO)* NRR/DORL/LPL2-2/BC* NRR/DORL/LPL2-2/PM*

NAME VCusumano TJones w/edits UShoop w/edits KGreen DATE 01/14/2021 02/16/2021 03/09/2021 03/09/2021