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Category:Letter
MONTHYEARML23180A1512023-06-29029 June 2023 LLC, Request for Exemption to the Reporting Requirements of 10 CFR 50.46(a)(3) ML21102A3072021-04-15015 April 2021 OEDO-21-00155 - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC, Small Modular Reactor ML21050A4312021-02-19019 February 2021 LLC - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC Small Modular Reactor ML20247J5642020-09-11011 September 2020 Standard Design Approval for the NuScale Power Plant Based on the NuScale 600 Standard Plant Design Certification Application ML20231A8042020-08-28028 August 2020 Final Safety Evaluation Report for the NuScale Standard Plant Design ML20224A4602020-08-25025 August 2020 OEDO-20-00292-Response to the Advisory Committee on Reactor Safeguards Letter on NuScale Power, LLC, Report on the Safety Aspects of the NuScale Small Modular Reactor ML20231A5982020-08-25025 August 2020 OEDO-20-00285_NuScale Area of Focus - Boron Redistribution ML20210M8902020-07-29029 July 2020 Area of Focus - Boron Redistribution ML20195A5872020-07-13013 July 2020 LLC - Submittal of Draft Operator Licensing and Examination Standard for NuScale Small Modular Reactors ML20195C7662020-07-13013 July 2020 LLC Request for Standard Design Approval Based on the NuScale Standard Plant Design Certification Application ML20192A3262020-07-10010 July 2020 LLC, Submittal of Environmental Report: Revision Status ML20198M3932020-07-0202 July 2020 LLC Submittal of Revised Packing Slip for Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1, Dated June 19, 2020 ML20174A3472020-07-0101 July 2020 OEDO-20-00220 - Area of Focus - Probabilistic Risk Assessment and Emergency Core Cooling System Valve Performance ML20184A2872020-07-0101 July 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and General Design Criterion 33, PM-0720-70785, Revision 0 ML20181A4322020-06-22022 June 2020 Final SER for NuScale TR-0516-49416 NON-Loss-of-Coolant Analysis Model, Rev 3 (Letter) ML20181A2702020-06-22022 June 2020 Final SER for NuScale TR-0516-49422 Loss-of-Coolant Analysis Model, Rev 2 (Letter) ML20198M3922020-06-19019 June 2020 LLC - 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Response to the ACRS Letter on Combustible Gas Monitoring ML20133K0882020-05-12012 May 2020 LLC, Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution (Closed Session), PM-0420-69512, Revision 0 ML20133J9142020-05-11011 May 2020 LLC Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0420-69511, Revision 0 ML20112F4552020-05-0101 May 2020 LLC, Design Certification Application Phases 5 and 6 Review Status ML20107F8492020-05-0101 May 2020 OEDO-2000140 - NuScale Area of Focus - Helical Tube Steam Generator Design ML20104A0792020-04-27027 April 2020 OEDO-20-00115 - Safety Evaluation Report for Topical Report TR-0516-49416, Revision 2, Non-Loss-of-Coolant Accident Analysis Methodology ML20099H0802020-04-0808 April 2020 LLC - Submittal of Presentation Materials Entitled NRC Public Meeting: Revisions to Nuscale'S EPZ Sizing Methodology Topical Report, PM-0420-69598, Revision 0 ML20098G2372020-04-0707 April 2020 Nuscale Power, LLC Submittal of Remaining Closure Items for the Emergency Core Cooling System Valve Failure Mode Effects Analysis Audit Items ML20097F1922020-04-0606 April 2020 Nuscale Power, LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: Nuscale Topic - Hydrogen/Oxygen Monitoring, PM-0420-69518, Revision 0 ML20094H6742020-04-0303 April 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation NuScale Topic-Probabilistic Risk Assessment with a Focus on Emergency Core Cooling System Analysis PM-0420-69559, Revision 0 ML20092L8992020-04-0101 April 2020 LLC - Submittal of Updates to Standard Plant Design Certification Application, Revision 4 ML20072M6682020-03-30030 March 2020 Response to NuScale Letter Dated February 24, 2020, on Planned SDA Application Content ML20072H3332020-03-0909 March 2020 LLC - Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0320-69218, Revision 0 ML20057D9002020-03-0606 March 2020 Submittal of Errata to Final SE for NuScale Power, LLC TR-1010-859-NP-A, Quality Assurance Program Description for the NuScale Power Plant ML20062F7262020-03-0505 March 2020 Request for Withholding Information from Public Disclosure for Nuscale Power, LLC Letter Public ML20069A1572020-03-0404 March 2020 LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Rod Ejection Accident Methodology, PM-0320-69146, Revision 0 ML20069A1772020-03-0404 March 2020 LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Non-Loss-of-Coolant Accident, PM-0320-69141, Revision 0 ML20069A9632020-03-0404 March 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report, Loss-of-Coolant Accident Evaluation Model, PM-0320-69138, Revision 0 ML20066G2802020-03-0303 March 2020 LLC, Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Topic - Hydrogen Monitoring, PM-0220-69071, Revision 0 ML20066G2882020-02-28028 February 2020 LLC Submittal of Presentation Materials Titled ACRS Full Committee Presentation: NuScale - Steam Generator Design (Closed Session), PM-0220-69053, Revision 0 2023-06-29
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRAIO-0420-69855, LLC, Submittal of Corrected Response to NRC Request for Additional Information No. 284 (Erai No. 9225) on the NuScale Design Certification2020-04-30030 April 2020 LLC, Submittal of Corrected Response to NRC Request for Additional Information No. 284 (Erai No. 9225) on the NuScale Design Certification ML19332A1202019-11-27027 November 2019 LLC Supplemental Response to NRC Request for Additional Information No. 484 (Erai No. 8930) on the NuScale Design Certification Application ML19304B4712019-10-31031 October 2019 LLC Supplemental Response to NRC Request for Additional Information No. 466 (Erai No. 9482) on the NuScale Design Certification Application ML19296D8052019-10-23023 October 2019 LLC Response to NRC Request for Additional Information No. 526 (Erai No. 9719) on the NuScale Design Certification Application ML19283E5302019-10-10010 October 2019 LLC Supplemental Response to NRC Request for Additional Information No. 522 (Erai No. 9681) on the NuScale Design Certification Application ML19260G7352019-10-0707 October 2019 Summary of Public Meeting with NuScale to Discuss Response to RAI 9681 ML19266A5872019-09-23023 September 2019 LLC Supplemental Response to NRC Request for Additional Information No. 518 (Erai No. 9659) on the NuScale Design Certification Application ML19262G9742019-09-19019 September 2019 LLC - Submittal of Changes to Final Safety Analysis Report, Tier 1, Section 3.11, Reactor Building and Section 3.13, Control Building, and Tier 2, Section 3.8.4, Design of Category I Structure and Section 14.3, Certified ... ML19262G5762019-09-19019 September 2019 LLC - Submittal of Changes to Final Safety Analysis Report, Section 14.2, Initial Plant Test Program, Table 14.2-2, Pool Cleanup Systems Test #2, and Table 14.2-50, Module Assembly Equipment Test #50 ML19259B8102019-09-16016 September 2019 LLC Supplemental Response to NRC Request for Additional Information No. 205 (Erai No. 9044) on the NuScale Design Certification Application ML19259A0922019-09-16016 September 2019 LLC Response to NRC Request for Additional Information No. 525 (Erai No. 9705) on the NuScale Design Certification Application ML19238A3722019-08-26026 August 2019 LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application ML19238A3662019-08-23023 August 2019 LLC - Response to NRC Request for Additional Information No. 523 (Erai No. 9682) on the NuScale Design Certification Application ML19215A0032019-08-0202 August 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on the NuScale Design Certification Application ML19215A0062019-08-0202 August 2019 LLC - 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Response to NRC Request for Additional Information No. 524 (Erai No. 9691) on the NuScale Design Certification Application ML19199A1172019-07-18018 July 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 484 (Erai No. 8930) on the NuScale Design Certification Application ML19198A3252019-07-17017 July 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 249 (Erai No. 9135) on the NuScale Design Certification Application ML19196A3682019-07-15015 July 2019 LLC Response to NRC Request for Additional Information No. 516 (Erai No. 9647) on the NuScale Design Certification Application ML19191A2202019-07-10010 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application ML19184A6152019-07-0303 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 386 (Erai No. 9316) on the NuScale Design Certification Application ML19176A5802019-06-25025 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19170A3702019-06-19019 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19168A2442019-06-17017 June 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 325 (Erai No. 9268) on the NuScale Design Certification Application ML19164A1452019-06-13013 June 2019 LLC - Submittal of Containment Response Analysis Methodology Technical Report, TR-0516 -49 08 4, Revision 1 ML19157A3262019-06-0606 June 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19154A6222019-06-0303 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on the NuScale Design Certification Application ML19154A6052019-06-0303 June 2019 LLC Response to NRC Request for Additional Information No. 514 (Erai No. 9645) on the NuScale Design Certification Application ML19151A8372019-05-31031 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 377 (Erai No. 9380) on the NuScale Design Certification Application ML19140A4592019-05-20020 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 401 (Erai No. 9447) on the NuScale Design Certification Application ML19137A2902019-05-17017 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application ML19137A2872019-05-15015 May 2019 LLC Response to NRC Request for Additional Information No. 519 (Erai No. 9656) on the NuScale Design Certification Application ML19126A2942019-05-0606 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 26 (Erai No. 8840) on the NuScale Design Certification Application ML19122A5092019-05-0202 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 494 (Erai No. 9548)on the Design Certification Application ML19121A6002019-05-0101 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on Design Certification Application 2020-04-30
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Text
RAIO-0917-56106 September 20, 2017 Docket No.52-048 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738
SUBJECT:
NuScale Power, LLC Response to NRC Request for Additional Information No.
108 (eRAI No. 8825) on the NuScale Design Certification Application
REFERENCE:
U.S. Nuclear Regulatory Commission, "Request for Additional Information No.
108 (eRAI No. 8825)," dated July 27, 2017 The purpose of this letter is to provide the NuScale Power, LLC (NuScale) response to the referenced NRC Request for Additional Information (RAI).
The Enclosure to this letter contains NuScale's response to the following RAI Question from NRC eRAI No. 8825:
09.05.03-1 This letter and the enclosed response make no new regulatory commitments and no revisions to any existing regulatory commitments.
If you have any questions on this response, please contact Carrie Fosaaen at 541-452-7126 or at cfosaaen@nuscalepower.com.
Sincerely, Zackary W. Rad
- Director, Di t Regulatory R l t Affairs Aff i NuScale Power, LLC Distribution: Gregory Cranston, NRC, OWFN-8G9A Samuel Lee, NRC, OWFN-8G9A Anthony Markley, NRC, OWFN-8G9A : NuScale Response to NRC Request for Additional Information eRAI No. 8825 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com
RAIO-0917-56106 :
NuScale Response to NRC Request for Additional Information eRAI No. 8825 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com
Response to Request for Additional Information Docket No.52-048 eRAI No.: 8825 Date of RAI Issue: 07/27/2017 NRC Question No.: 09.05.03-1 NUREG-0800, Standard Review Plan (SRP), Section 9.5.3 states that the plant lighting system (PLS) must provide adequate lighting during all plant operating conditions, including fire, transient, and accident conditions. The staff reviewed the information in the design certification application, FSAR Tier 2, Section 9.5.3, using the methods described in Section 9.5.3 of NUREG-0800, and is requesting the following additional information:
A. FSAR Tier 2, Section 9.5.3.1 states that the plant illumination levels provided by the PLS are in accordance with the applicable lighting levels recommended in NUREG-0700, Human-System Interface Design Review Guidelines, and the Illuminating Engineering Society of North America (IESNA) lighting handbook (Reference 9.5.3-2 in FSAR Tier 2).
FSAR Tier 2, Section 9.5.3.2 also states that the plant lighting system is capable of delivering at least 100 foot-candles of illumination to the main control room seated operator stations and 50 foot-candles of illumination to the main control room primary operating areas and remote and auxiliary operating panels.
QUESTION: Please provide the illumination levels for normal lighting for: (1) various tasks and work areas as specified in NUREG-0700, Table 12.1, Nominal illumination levels for various tasks and work areas, (2) in-plant areas as specified in NUREG-0700, Table 12.10, Range of recommended illuminances for inspection/assembly activities, and (3) all other areas/rooms of the plant that are required for control and maintenance of equipment and plant access routes during normal plant operations.
B. NUREG-0800, Section 9.5.3 states that the capability of the emergency lighting system to provide adequate lighting during all plant operating conditions, including fire, transient and accident conditions should be evaluated. FSAR Tier 2, Section 9.5.3.4 states that the emergency lighting is inspected and tested periodically.
QUESTION: Please identify the programs (i.e., maintenance rule program if applicable) that will address inspection and testing of the emergency lighting systems. In addition, discuss the COL applicant responsibility and revise the FSAR as necessary.
C. FSAR Tier 1, Section 3.8.1 and Tier 2, Section 9.5.3 state that the PLS provides artificial NuScale Nonproprietary
illumination for the entire plant, but FSAR Tier 1, Section 3.8.1 only provides a design commitment and ITAAC for the PLS in the Main Control Room and the Remote Shutdown Station.
QUESTION: Please explain why a design commitment and ITAAC are not included to confirm the capability of the PLS to provide adequate lighting in all areas of the plant during all plant conditions.
NuScale Response:
A. FSAR Section 9.5.3 has been revised to more clearly indicate that the illumination levels for normal operation in the main control room (MCR) and remote shutdown station (RSS) conform to the guidance of NUREG-0700 Table 12.1. Normal lighting in other areas of the plant is based on the IESNA Lighting Handbook, which may not in all cases conform to the guidance provided in Table 12.10 of NUREG-0700.
B. FSAR Section 9.5.3 states that illumination levels are a minimum of 10 foot-candles in emergency operation areas and a minimum of 2 foot-candles in other areas of the plant. The testing and inspection programs for emergency lighting will be determined and developed by the licensee.
C. Section 1.0 of Tier 1 of the NuScale application states that a graded approach is employed relative to the level of design information presented in Tier 1, i.e., the amount of design information presented is proportional to the safety significance of the structures, systems, and components being addressed. Tier 1 Table 3.8-1 provides ITAAC for those portions of the NuScale plant from which the nuclear power modules are operated.
D. The NuScale design does not have an ITAAC to confirm the capability of the PLS to provide adequate lighting in all areas of the plant during all plant conditions. The following is the basis for not including this ITAAC in Tier 1.
Tier 1 Section 3.8.1 Design Description contains two parts: System Description and Design Commitments. Tier 1 Section 3.8.1 System Description is designed to provide a general description of the PLS system. It is not designed to identify the top-level design features to be verified by ITAAC. Instead, the PLS top-level design features to be verified by ITAAC are the PLS design commitments identified in Tier 1 Section 3.8.1 Design Commitments. The design commitments were selected using the first principles described in Tier 2 Section 14.3.2.1, Tier 1 Design Description Scope First Principles.
The PLS system illumination ITAAC are included in Tier 1 Table 3.8-1 (No, 1, No2. and No.3).
In a multi-year collaboration between the industry and the NRC, the NRC held numerous public meeting with the industry to discuss the standardization of ITAAC with the objective of clarifying NuScale Nonproprietary
the scope of ITAAC required for design certification applications. In May 2015 NEI submitted draft A of Rev 0 of NEI 15-02 Industry Guideline for the Development of Tier 1 and ITAAC Under 10 CFR Part 52 to the NRC for review. Attachment A of NEI 15-02 contains proposed standardized ITAAC for plant illumination. The attachment contained Standardized ITAAC E15 for the MCR and RSS normal illumination; E16 for the MCR and RSS emergency illumination; and E24 for eight-hour battery pack emergency illumination.
In a letter dated April 8, 2016, Frank Akstulewicz, NRC Director, Division of New Reactor Licensing, Office of New Reactors to Thomas Bergman, Vice-President Regulatory Affairs, NuScale Power, LLC entitled TRANSMITTAL OF DRAFT STANDARD INSPECTIONS, TESTS, ANALYSIS AND ACCEPTANCE CRITERIA, ADAMS Accession No.:ML16096A121, the NRC issued a draft set of standardized ITAAC that could be used in your future design certification application using the Title 10 of the Code of Federal Regulations (10 CFR) Part 52. Included in the letter were the NRC-proposed ITAAC for plant illumination. In the letter, the NRC did not propose any additional plant illumination ITAAC to the NEI-proposed ITAAC E15, E16 and E24.
In a letter dated June 21, 2016, Frank Akstulewicz, NRC Director, Division of New Reactor Licensing, Office of New Reactors to Thomas Bergman, Vice-President Regulatory Affairs, NuScale Power, LLC entitled TRANSMITTAL OF ADDITIONAL ITEMS INCLUDED IN THE DRAFT STANDARD INSPECTIONS, TESTS, ANALYSIS, AND ACCEPTANCE CRITERIA, the NRC added two additional draft standard ITAAC. The additional ITAAC were not associated with plant illumination.
The PLS system illumination ITAAC included in Tier 1 Table 3.8-1 (No, 1, No2. And No.3) are based on standardized ITAAC E15, E16, and E24.
Therefore, NuScale design does not have an ITAAC to confirm the capability of the PLS to provide adequate lighting in all areas of the plant during all plant conditions.
Impact on DCA:
FSAR Section 9.5.3 has been revised as described in the response above and as shown in the markup provided in this response.
NuScale Nonproprietary
NuScale Final Safety Analysis Report Other Auxiliary Systems RAI 09.05.03-1 Adequate lighting in important areas is ensured by lighting calculations that consider tasks performed in the area and other lighting factors (e.g, reflectance, illumination levels) when calculating required illumination levels. Task area coatings and equipment are also taken into consideration in the lighting calculations. The plant lighting system is capable of delivering at least 100 foot-candles of illumination to the main control room and remote shutdown station seated operator stations and 50 foot-candles of illumination to the panels in the primary operating areas and to the auxiliary panels in the main control room primary operating areas and remote and auxiliary operating panelsand the remote shutdown station. Lower illumination levels may be used within these areas to ensure more favorable visual conditions, or for areas where critical tasks are not performed.
Emergency Plant Lighting Emergency lighting outside the control room provides illumination upon loss of normal lighting in plant areas where emergency operations are performed, including the:
- electrical distribution control panels
- backup diesel generators and their controls
Emergency lighting located outside of the MCR consists of self-contained, battery-powered fixtures. Lighting calculations confirm the illumination levels are in accordance with the National Electric Code and the Life Safety Code of the National Fire Protection Association. Three different types of emergency lighting are provided:
- fixtures that meet National Fire Protection Association Life Safety Code 101 requirements, which are equipped with 1.5-hour battery backup to support ingress/egress the area
- fixtures in areas where operators perform actions to support safe shutdown of the plant in the event of a station blackout, which are equipped with an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> battery backup
- fixtures in areas where operators perform actions required in a fire safe shutdown scenario satisfy guidance in RG 1.189, Section 4.1.6.2.a, which are equipped with an 8-hour battery backup RAI 09.05.03-1 Tier 2 9.5-123 Draft Revision 1
NuScale Final Safety Analysis Report Other Auxiliary Systems Emergency lighting provides a minimum illumination of 10 foot-candles at workstations in the plant where emergency operations are performed.
RAI 09.05.03-1 Emergency lighting provides the minimum illumination levels based on Reference 9.5.3-2 in the remote shutdown station for emergency operations consistent withIn accordance with Table 12.1 of NUREG-0700. Additionally, PLS calculations confirm that illumination levels are, the PLS provides a minimum of 10 foot-candles of illumination in emergency operation areas and. In addition, the PLS provides a minimum of 2 foot-candles of illumination in other areas for the required durations. Battery loading for emergency lighting fixtures is less than 80 percent of battery capacity, including allowances for temperature derating, where required.
Circuit breakers supplying power to the self-contained, battery-powered emergency lighting fixtures are locked in the "energized" position to reduce inadvertent operation.
Following restoration of AC power, self-contained, battery-powered light units turn off after a time delay to provide adequate time for normal lighting to restart.
Normal and Emergency Main Control Room Lighting RAI 09.05.03-1 Normal and emergency MCR lighting provides artificial illumination under all operating, maintenance, testing, and emergency conditions. Emergency lighting in the MCR provides the minimum illumination levels based on Reference 9.5.3-2 consistent with NUREG-0700. Plant illumination levels are summarized in Table 9.5.3-1.
The MCR lighting fixtures are designed to operate on either 120V AC power or 125V DC power, which allows MCR lighting to auto transfer from the normal AC power source to the emergency DC power source in the event of a failure of normal AC power. Normal and emergency lighting circuits are fed from their respective lighting panels, which are physically separated from each other. The MCR lighting circuits that auto transfer from normal to emergency power are transferred to the normal power supply after restoration of power.
The MCR lighting is supported by two divisions of nonsafety-related normal AC power and two divisions of nonsafety-related emergency DC power. Both normal and emergency power circuits to individual lighting fixtures are staggered, to the extent possible, to ensure both MCR normal and emergency lighting is maintained following loss of a circuit.
Normal (AC) MCR lighting power is supplied by the PLS which is powered by the ELVS described in Section 8.3.1. Two nonsafety-related divisions of ELVS (Division 1 and Division 2) supply 480V AC power to the PLS lighting transformers, which supply 120V single-phase power to the MCR lighting panelboards. The ELVS and PLS are nonsafety-related and not risk-significant.
Emergency (DC) MCR lighting power is supplied by the nonsafety-related highly reliable DC power system-common (EDSS-C) described in Section 8.3.2. Two divisions of EDSS-C (Division I and Division II) supply 125V DC power to MCR lighting. The EDSS-C Tier 2 9.5-124 Draft Revision 1
NuScale Final Safety Analysis Report Other Auxiliary Systems RAI 09.05.03-1 Table 9.5.3-1: Plant Illumination Levels Area Illumination (foot-candles)
Panels, primary operating area, MCR and RSS 50 Auxiliary panels, MCR and RSS 50 Seated Operator Workstations, MCR and RSS 100 Emergency operating lighting, MCR and RSS 10 Emergency operating lighting, other areas of plant 2 Tier 2 9.5-127 Draft Revision 1