ML19179A183
| ML19179A183 | |
| Person / Time | |
|---|---|
| Site: | NuScale |
| Issue date: | 06/28/2019 |
| From: | Rad Z NuScale |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| LO-0619-66052 | |
| Download: ML19179A183 (5) | |
Text
LO-0619-66052 June 28, 2019 Docket No.52-048 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One W hite Flint North 11555 Rockville Pike Rockville, MD 20852-2738 S U B J E C T : NuScale Power, LLC Submittal of NuScale Powers Status Update for Containment Isolation Valves and Reactor Safety Valves Design Document Audit Follow-Up Items R E F E R E N C E S : 1. Letter from NuScale Power, LLC to Nuclear Regulatory Commission, NuScale Power, LLC Submittal of the NuScale Standard Plant Design Certification Application, Revision 2, dated October 30, 2018 (ML18311A006)
- 2. The U.S. Nuclear Regulatory Commission Staffs Report of the Regulatory Audit of NuScale Power LLC, Design Documents for Containment Isolation Valves and Reactor Safety Valves, dated December 7, 2018 (ML18331A042)
- 3. Letter from NuScale Power, LLC to Nuclear Regulatory Commission, NuScale Power, LLC Submittal of Resolution Plans for Containment Isolation Valves and Reactor Safety Valves Design Document Audit Follow-Up Items, dated January 31, 2019 (ML19031C973)
The purpose of this letter is to provide the NRC with a status update regarding follow-up items recorded in the NRC Audit Report (Reference 2) as agreed to by NuScale in the closure plan (Reference 3). The attachment to this letter provides that status information.
This letter makes no regulatory commitments or revisions to any existing regulatory commitments.
If you have any questions, please contact Rebecca Norris at 541-602-1260 or at rnorris@ nuscalepower.com.
Sincerely, Zackary W . Rad Director, Regulatory Affairs NuScale Power, LLC Distribution: Samuel Lee, NRC, OW FN-8H12 G regory Cranston, NRC, OW FN-8H12 Marieliz Vera, NRC, OW FN-8H12
Attachment:
NuScale Powers Status Update for Containment Isolation Valves and Reactor Safety Valves Design Document Audit Follow-Up Items N u S c a le P o w e r , L L C 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com
LO-0619- 66052 Attachment Page 1 of 4 NuScale Powers Status Update for Containment Isolation Valves and Reactor Safety Valves Design Document Audit Follow-Up Items The following table provides NuScales status and closure details regarding the Containment Isolation Valves and Reactor Safety Valves Design Document Audit Follow-Up Items agreed to by NuScale in Reference 3.
Issue Description Proposed Resolution Completed Action (Action)
Containment Isolation Valves Final Safety Analysis Report (FSAR) Updates Apparent inconsistency in the NuScale understands the Open Action: On track to be fourth paragraph of Section requested FSAR change and completed as proposed.
6.2.4.2.2. The second will clarify the FSAR Section Changes are being made to sentence states that the 6.2.4.2.2 text to resolve the FSAR Section 6.2.4.2.2 to PSCIVs in the Control Rod above apparent address the Follow-Up Item.
Drive System (CRDS), inconsistency. These changes will be Containment Evacuation provided to the NRC in the System (CES), and next revision of the FSAR.
Containment Flooding and Drain System (CFDS) are designed and constructed to Class 1, while the third sentence states that these PSCIVs are designed, fabricated, constructed, tested, and inspected in accordance with ASME BPV Code,Section III, Class 2.
Section 6.2.4.2.2 discusses NuScale understands the Open Action: On track to be thermal relief devices requested FSAR change and completed as proposed.
included in the design of the will update the FSAR Changes are being made to PSCIVs to relieve excessive description of 10 CFR Part FSAR Sections 3.9.6.3.2 and pressurization. The 50, Appendix J containment 6.2.4.2.2 to address the description in the FSAR for leakage testing and the IST Follow-Up Item. These the 10 CFR Part 50, program to include provisions changes will be provided to Appendix J, containment for the PSCIV thermal relief the NRC in the next revision leakage testing and 10 CFR valves. of the FSAR.
50.55a inservice testing (IST) program testing requires revision to include provisions for the PSCIV thermal relief valves.
FSAR Section 6.2.4.2.2 NuScale understands the Open Action: On track to be requires revision to clarify requested FSAR change and completed as proposed.
whether the CIV rack and will update the FSAR to Changes are being made to pinion mechanism or the gas indicate how the CIV will be FSAR Section 5.4.3.2.1 for cylinder will be qualified to qualified to hold the valve DHRS valves and 6.4.2.2 for hold the valve closed for the closed for the time period CIVs. These changes will be time period specified for its specified for its design-basis
LO-0619- 66052 Attachment Page 2 of 4 Issue Description Proposed Resolution Completed Action (Action) design-basis and beyond or beyond design-basis provided to the NRC in the design-bases functions. functions. next revision of the FSAR.
The diagrams of the include NuScale understands the Open Action: On track to be valves (such as relief and requested FSAR change and completed as proposed.
check valves) that perform will update the FSAR to Changes are being made to safety functions for the identify the CIV internal FSAR Sections 3.9.6.3.2 and proper performance of the valves and specify the 6.2.4.2.2 to address the CIV actuators, nitrogen gas applicable IST testing of the Follow-Up Item. These cylinders, and hydraulic lines. valves. changes will be provided to Update the FSAR to identify the NRC in the next revision these CIV internal valves and of the FSAR.
specify the applicable IST testing of those valves consistent with the ASME OM Code, Section IST (OM Code) provisions, such as skid-mounted components where appropriate.
Update the FSAR as required NuScale understands the Open Action: On track to be to provide the SSCIV design requested FSAR change and completed as proposed.
details to prevent pressure will update the FSAR to Changes are being made to locking or thermal binding provide the SSCIV design FSAR section 6.2.4.2.2 to conditions. details to prevent pressure address the Follow-Up Item.
locking or thermal binding These changes will be conditions. provided to the NRC in the next revision of the FSAR.
Containment Isolation Valve Design Document Updates The PSCIV and SSCIV NuScale understands the Action completed as Design Specifications requested specification proposed. SSCIV and indicate ODI-16-0221 update and will provide for PSCIV mechanical and concerning the Reactor audit documentation thermal design loading has Module Loading Specification demonstrating that the CIVs been updated in their for mechanical loads is open. accommodate piping respective specifications.
This open item is required to mechanical and thermal be completed. design loads.
Document CIV hydraulic NuScale understands the Action completed as actuator sizing and settings in requested document update proposed. CIV actuator sizing vendor design documents. and will provide for audit and setting design vendor documentation development calculations including the CIV actuator have been completed and sizing and settings. are available for audit. These parameters will be verified by CIV prototype testing and are subject to change.
Reactor Safety Valve Design Document Updates Update Target Rock Drawing NuScale understands the Action completed as No. 14Z539-RSV2 to reflect requested document update proposed. RSV design and will provide the updated drawing indicates compliance
LO-0619- 66052 Attachment Page 3 of 4 Issue Description Proposed Resolution Completed Action (Action) the 2013 Edition of the ASME document for audit, which with ASME BPVC 2013 BPV Code. reflects the correct ASME edition, section III, subsection Code Edition. NB.
Revise the RSV Design NuScale understands the Action completed as Specification to correctly requested document update proposed. RSV design reflect an actuation time of 1 and will provide the updated drawing has been updated to second. specification for audit, which an actuation time of one reflects the one second second.
actuation time.
During the NRC staff audit NuScale understands the Action completed as review of the RSV Design requested document update proposed. RSV design Specification, NuScale and will provide for audit the specification includes valve indicated that the design updated specification to size and type.
specification is intended to specify the valve size.
establish requirements but does not specify size or type.
NuScale noted that the size will result from the specified flow coefficient, and the type will result from the functional requirements listed in the design specification.
However, NuScale stated that the specification does not include a table that specifies the valve size.
Therefore, NuScale will revise the design specification to include this information.
The RSV Design NuScale understands the Partially open actions as Specification indicates that requested specification described below:
ODI-15-0220 (pressure and update and will close the ODI temperature for pneumatic or provide documentation for
- ODI-15-0220 has been leak testing and hydrostatic audit demonstrating that the removed from the RSV testing), ODI-15-0329 RSV design adequately design specification.
(minimum reactor pool addresses the respective Hydrostatic testing is temperature), ODI- 15-0472 open item. specified in the RSV (Inservice examination design specification.
requirements),16-021 There is no pneumatic (Reactor Module Nozzle actuator associated with loads), and 16-0684 the RSV, so leak testing is (pressure and temperature not required.
curves for prototype and
- ODI-15-0329 still resides qualification) remain open. in the RSV design These open items are specification. Minimum required to be closed. reactor pool temperature has been determined, but
LO-0619- 66052 Attachment Page 4 of 4 Issue Description Proposed Resolution Completed Action (Action) document revisions are still pending.
- ODI-15-0472 has been removed from the RSV design specification and is complete.
- ODI 16-0021 has been removed from the RSV specification. New ODI 19-0008 has been opened to provide a clearer description of the required design loading needs.
Piping design is not finalized, therefore, nozzle loads have not been completed.
- ODI-16-0684 has been removed from the RSV specification and is complete.