ML19262G576

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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
ML19262G576
Person / Time
Site: NuScale
Issue date: 09/19/2019
From: Rad Z
NuScale
To:
Document Control Desk, Office of New Reactors
References
LO-0919-67060
Download: ML19262G576 (5)
v • d • e


Text

LO-0919-67060 September 19, 2019 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 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

REFERENCES:

Letter from NuScale Power, LLC to Nuclear Regulatory Commission, NuScale Power, LLC Submittal of the NuScale Standard Plant Design Certification Application, Revision 3, dated August 22, 2019 (ML19241A315)

During an August 27, 2019 public teleconference with NRC Project Manager and NRC reviewers, NuScale Power, LLC (NuScale) discussed potential updates to Final Safety Analysis Report (FSAR),

Section 14.2 Initial Plant Test Program. As a result of this discussion, NuScale changed the Section 14.2. The Enclosure to this letter provides a mark-up of the FSAR pages incorporating revisions to Section 14.2, in redline/strikeout format. NuScale will include this change as part of a future revision to the NuScale Design Certification Application.

The enclosure to this letter is the nonproprietary version of the changes to NuScale Final Safety Analysis Report, Section 14.2, Initial Plant Test Program, Table 14.2-2, Pool Cleanup Systems Test

  1. 2, and Table 14.2-50, Module Assembly Equipment Test #50.

This letter makes no regulatory commitments or revisions to any existing regulatory commitments.

If you have any questions, please feel free to contact Nadja Joergensen at 541-452-7338 or at njoergensen@nusclepower.com.

Sincerely, Zackary W. Rad Director, Regulatory Affairs NuScale Power, LLC Distribution: Samuel Lee, NRC, OWFN-8H12 Gregory Cranston, NRC, OWFN-8H12 Cayetano Santos, NRC, OWFN-8H12 Michael Dudek, NRC, OWFN-8H12

Enclosure:

Changes to NuScale 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 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com

LO-0919-67060

Enclosure:

Changes to NuScale 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 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com

NuScale Final Safety Analysis Report Initial Plant Test Program is applicable to the system) unless the preoperational test verifies an ITAAC. The component tests are standardized to provide the same level of test detail across all systems. This graded approach does not affect system-level tests which require integrated system operation. The standardized component tests are:

  • Remote operation of equipment.
  • Manual control of variable-speed pump or fan.
  • Automatic start of standby pump or fan.
  • Automatic operation of pump recirculation valve.
  • Pump start does not create a water hammer.
  • Remote operation of valve or damper.
  • Valve or damper fails to its safe position on loss of air.
  • Valve or damper fails to its safe position on loss of electrical power to its solenoid.
  • Damper or fan responds to fire or smoke alarm.
  • Equipment response to automatic signals to protect plant equipment.
  • Automatic operation of tank or basin level control valve.
  • Automatic bus transfer via bus tie breaker.
  • System instrument calibration.
  • Each instrument is monitored in the MCR and the remote shutdown station (RSS), if the signal is designed to be displayed in the RSS. (Test not required if the instrument calibration verified the MCR and RSS display.)

14.2.3.3 Testing of First-of-a-Kind Design Features RAI 03.09.02-10, RAI 14.02-1 First-of-a-kind (FOAK) tests are new, unique, or special tests used to verify design features that are being reviewed for the first time by the NRC. The NuScale Power Plant contains design features which are new and unique and have not been tested previously; therefore, testing of these design features is treated as FOAK. For the FOAK tests, the testing frequency is specified in the test abstract. The NuScale comprehensive vibration assessment program (CVAP) is a FOAK program. The program is implemented consistent with the requirements of the NuScale Comprehensive Vibration Assessment Program Technical Report", TR-0716-50439, and the NuScale Comprehensive Vibration Assessment Program Measurement and Inspection Plan Technical Report, TR-0918-60894. The CVAP is addressed in Section 3.9.2.

RAI 03.09.02-10, RAI 14.02-1, RAI 14.03-3 The following ITP test abstracts describe the on-site CVAP testing of FOAK design features:

  • Table 14.2-72Table 14.2-75: Steam Generator Flow-Induced Vibration Test #72.
  • Table 14.2-108: NuScale Power Module Vibration Test #108 Tier 2 14.2-10 Draft Revision 4

NuScale Final Safety Analysis Report Initial Plant Test Program RAI 14.03-3 Table 14.2-2: Pool Cleanup System Test # 2 Preoperational test is required to be performed once.

The pool cleanup system (PCUS) is described in Section 9.1.3.2.3 and the functions verified by this test are:

System Function System Function Categorization Function Verified by Test #

1. The spent fuel pool cooling system nonsafety-related Test #2-1 (SFPCS) supports the PCUS by providing spent fuel pool water for purification of the ultimate heat sink (UHS).
2. The reactor pool cooling system nonsafety-related Test #2-1 (RPCS) supports the PCUS by providing reactor pool water for purification of the UHS.
3. The pool surge control system (PSCS) nonsafety-related Component level tests supports the PCUS by providing Pool Surge Control System Test #4-1 water from the dry dock for UHS inventory control.
4. The PCUS supports the PSCS, RPCS, nonsafety-related Component level tests and SFPCS by providing a flowpath to cross-connect the PSCS, RPCS, and SFPCS.

Prerequisites

i. Verify an instrument calibration has been completed, with approved records and within all calibration due dates, for all instruments required to perform this test.

ii. Verify a pump curve test has been completed and approved for the RPCS pumps.

iii. Verify a pump curve test has been completed and approved for the SFPCS pumps.

iv. Verify a UHS leakage test has been performed.

Component Level Tests Test Objective Test Method Acceptance Criteria

i. Verify each PCUS remotely-operated Operate each valve from the main MCR display and local, visual valve can be operated remotely. control room (MCR) and local control observation indicate each valve fully panel (if design has local valve control). opens and fully closes.

ii. Verify each PCUS air-operated valve Place each valve in its non-safe position. MCR display and local, visual fails to its safe position on loss of air. Isolate and vent air to the valve. observation indicate each valve fails to its safe position.

iii. Verify each PCUS air-operated valve Place each valve in its non-safe position. MCR display and local, visual fails to its safe position on loss of Isolate electrical power to each observation indicate each valve fails to electrical power to its solenoid. air-operated valve. its safe position.

iv. Verify a local grab sample can be Place the system in service to allow flow A local grab sample is successfully obtained from a PCUS grab sample through the grab sampling device. obtained.

device.

v. Verify each PCUS instrument is Initiate a single real or simulated The instrument signal is displayed on an available on a module control system instrument signal from each PCUS MCS or PCS display, or is recorded by the (MCS) or plant control system (PCS) transmitter. applicable control system historian.

display.

(Test not required if the instrument calibration verified the MCS or PCS display.)

Tier 2 14.2-22 Draft Revision 4

NuScale Final Safety Analysis Report Initial Plant Test Program RAI 14.03-3 Table 14.2-50: Module Assembly Equipment Test # 50 There are no preoperational tests for module assembly equipment (MAE).

The MAE consists of module import trolley, the upender, and the inspection rack.

System Function System Function Categorization Function Verified by Test #

NoneMAE supports the NuScale Power Nonenonsafety-related Nonecomponent-level tests Module actively by providing material handling to allow its transport in the horizontal orientation to travel from outside the Reactor Building to its interior and to rotate it to operational orientation.

Prerequisites N/AAn MAE factory acceptance test has been successfully completed and approved, if required.

Component Level Tests Test Objective Test Method Acceptance Criteria

i. NoneVerify the operation of MAE Actuate or simulate actuation of the The MAE equipment controls limit controls that limit motion and speed. interlocks. motion and speed per design.

(This test may be performed as part of site acceptance testing.)

System-Level Tests None Tier 2 14.2-115 Draft Revision 4

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