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{{#Wiki_filter:June 20, 2018 MEMORANDUM TO:              Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors FROM:                        Demetrius Murray, Project Manager    /RA/
Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors
 
==SUBJECT:==
 
==SUMMARY==
OF THE JANUARY 31, 2018, CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC IN RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 9122 RELATED TO NUSCALE STANDARD DESIGN CERTIFICATION 10.04.07 - CONDENSATE AND FEEDWATER SYSTEM APPLICATION SECTION: 10.4.7 - QUESTION 10.4.7-1 The U.S. Nuclear Regulatory Commission (NRC) staff held a Category 1 public teleconference with NuScale Power, LLC (NuScale) on January 31, 2018, to discuss NuScales response to Request for Additional Information (RAI) No. 9122 Question 10.04.07 Condensate and Feedwater System Application. Participants included personnel from NuScale and a members of the public.
The public meeting notice can be found in the Agencywide Documents Access and Management Systems under Accession No. ML18026A564. This meeting notice was also posted on the NRC public website.
The meeting agenda and list of participants can be found in Enclosures 1 and 2, respectively.
The technical issues discussed are included in Enclosure 3.
CONTACT: Demetrius Murray, NRO/DLSE 301-415-7646
 
S. Lee                                    2
 
==SUMMARY==
:
The purpose of this teleconference was to discuss the response to RAI 9122. The comments presented by the NRC staff (Enclosure 3) for Response will be addressed by an upcoming Design Certification Application (DCA) change and NuScale supplementing the RAI response.
No comments from members of the public were received.
Docket No. 52-048
 
==Enclosure:==
: 1. Meeting Agenda
: 2. List of Attendees
: 3. Comments presented by NRC staff cc: w/encls.: DC NuScale Power LLC Listserv
 
          *via email              NRO-002 NRO/DLSE/LB1/PM      NRO/DLSE/LB1/LA      NRO/DLSE/LB1/LPM OFFICE DMurray*            MBrown*              GCranston*
NAME 2/5/2018            6/20/2018            6/20/2018 DATE
 
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLCS DESIGN CERTIFICATION APPLICATION REQUEST FOR ADDITIONAL INFORMATION 9122 RESPONSE, RELATED TO NUSCALE STANDARD DESIGN CERTIFICATION 048 - 10.04.07 - CONDENSATE AND FEEDWATER SYSTEM APPLICATION SECTION: 10.4.7 January 31, 2018 1:00 p.m. - 3:00 p.m.
AGENDA Public meeting 1:00 - 1:10 pm      Introductions 1:10 - 1:50 pm      Discussion of RAI 9122 1:50 - 2:00 pm      Public comments Enclosure 3
 
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLCS DESIGN CERTIFICATION APPLICATION REQUEST FOR ADDITIONAL INFORMATION 9122 RESPONSE, RELATED TO NUSCALE STANDARD DESIGN CERTIFICATION 048 - 10.04.07 - CONDENSATE AND FEEDWATER SYSTEM APPLICATION SECTION: 10.4.7 List of Attendees January 31, 2018 NAME                                  AFFLIATION Demetrius Murray              U.S. Nuclear Regulatory Commission (NRC)
Angelo Stubbs                                  NRC Antonio Dia                                  NRC Carrie Fosaaen                      NuScale Power, LLC (NuScale)
Mark Chitty                                NuScale Dustin Greenwood                              NuScale Gary Becker                                  NuScale Lisa Davies                                NuScale Bob Bromm                                  NuScale Ryan Welch                                    Public Enclosure 2
 
U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLCS DESIGN CERTIFICATION APPLICATION REQUEST FOR ADDITIONAL INFORMATION RESPONSE 9122, RELATED TO NUSCALE STANDARD DESIGN CERTIFICATION 048 - 10.04.07 - CONDENSATE AND FEEDWATER SYSTEM APPLICATION SECTION: 10.4.7 January 31, 2018 General Comments
: 1. Question 10.4.7-1 requested condensate and feedwater system piping and instrumentation diagram (P&ID) be provided and included in the NuScale final safety analysis report (FSAR). In its response the applicant did not include the requested P&ID instead revised power cycle block diagram FSAR Figure 10.1-1.
: a. NuScale Power, LLC (NuScale) would provide a simplified system diagram of the condensate feed water system that will be available at the NuScale Rockville, Maryland, office for audit.
: 2. Question 10.4.7-1 requested information on condensate and feedwater system (CFWS) inspection and testing after the nuclear plant module (NPM) is reinstalled in its bay and connected back to the CFWS system after refueling is completed. In its response to the question the applicant states that the CFWS is outside the scope of general design criteria (GDC) 45 and 46, and propose removing what they consider erroneous language from the FSAR. The U.S. Nuclear Regulatory Commission staff disagrees with the applicant conclusion that GDC 45 and 46 is not applicable.
: a. NuScales assertion that GDC 45 and 46 are not applicable, because the CFWS contains SSCs that are part of the DHRS boundary. There would be no change to their RAI response.
: 3. Question 10.4.7-3 requested the applicant propose a combined operating license (COL) item to provide operating and maintenance procedures to address water hammer issues for the CFWS. The applicant response did not include the addition of the requested COL item. The COL items should have applicant provide procedures in accordance with NUREG-0927 as was done in APR 1400 DCD COL Item 10.4(8), and USAPWR DCD COL item 10.4(6).
: a. NuScale stated that FSAR Tier 2, Section 3.6.3.1.4 indicates that The feedwater system (FWS) and steam generator (SG) contain design features that minimize the potential for and effect of water hammer. There would be no change to their RAI response.
Enclosure 3}}

Revision as of 17:20, 21 October 2019

01/31/2018 Summary of Category 1 Public Teleconference with Nuscale Power, LLC in Response to Requests for Additional Information 9122 Related to Nuscale Standard Design Certification 10.04.07 - Condensate and Feed Water System Application
ML18071A360
Person / Time
Site: NuScale
Issue date: 06/20/2018
From: Demetrius Murray
NRC/NRO/DNRL/LB1
To: Samson Lee
NRC/NRO/DNRL/LB1
Murray D / 415-7646
References
Download: ML18071A360 (6)


Text

June 20, 2018 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors FROM: Demetrius Murray, Project Manager /RA/

Licensing Branch 1 Division of Licensing, Siting, and Environmental Analysis Office of New Reactors

SUBJECT:

SUMMARY

OF THE JANUARY 31, 2018, CATEGORY 1 PUBLIC TELECONFERENCE WITH NUSCALE POWER, LLC IN RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 9122 RELATED TO NUSCALE STANDARD DESIGN CERTIFICATION 10.04.07 - CONDENSATE AND FEEDWATER SYSTEM APPLICATION SECTION: 10.4.7 - QUESTION 10.4.7-1 The U.S. Nuclear Regulatory Commission (NRC) staff held a Category 1 public teleconference with NuScale Power, LLC (NuScale) on January 31, 2018, to discuss NuScales response to Request for Additional Information (RAI) No. 9122 Question 10.04.07 Condensate and Feedwater System Application. Participants included personnel from NuScale and a members of the public.

The public meeting notice can be found in the Agencywide Documents Access and Management Systems under Accession No. ML18026A564. This meeting notice was also posted on the NRC public website.

The meeting agenda and list of participants can be found in Enclosures 1 and 2, respectively.

The technical issues discussed are included in Enclosure 3.

CONTACT: Demetrius Murray, NRO/DLSE 301-415-7646

S. Lee 2

SUMMARY

The purpose of this teleconference was to discuss the response to RAI 9122. The comments presented by the NRC staff (Enclosure 3) for Response will be addressed by an upcoming Design Certification Application (DCA) change and NuScale supplementing the RAI response.

No comments from members of the public were received.

Docket No.52-048

Enclosure:

1. Meeting Agenda
2. List of Attendees
3. Comments presented by NRC staff cc: w/encls.: DC NuScale Power LLC Listserv
  • via email NRO-002 NRO/DLSE/LB1/PM NRO/DLSE/LB1/LA NRO/DLSE/LB1/LPM OFFICE DMurray* MBrown* GCranston*

NAME 2/5/2018 6/20/2018 6/20/2018 DATE

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLCS DESIGN CERTIFICATION APPLICATION REQUEST FOR ADDITIONAL INFORMATION 9122 RESPONSE, RELATED TO NUSCALE STANDARD DESIGN CERTIFICATION 048 - 10.04.07 - CONDENSATE AND FEEDWATER SYSTEM APPLICATION SECTION: 10.4.7 January 31, 2018 1:00 p.m. - 3:00 p.m.

AGENDA Public meeting 1:00 - 1:10 pm Introductions 1:10 - 1:50 pm Discussion of RAI 9122 1:50 - 2:00 pm Public comments Enclosure 3

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLCS DESIGN CERTIFICATION APPLICATION REQUEST FOR ADDITIONAL INFORMATION 9122 RESPONSE, RELATED TO NUSCALE STANDARD DESIGN CERTIFICATION 048 - 10.04.07 - CONDENSATE AND FEEDWATER SYSTEM APPLICATION SECTION: 10.4.7 List of Attendees January 31, 2018 NAME AFFLIATION Demetrius Murray U.S. Nuclear Regulatory Commission (NRC)

Angelo Stubbs NRC Antonio Dia NRC Carrie Fosaaen NuScale Power, LLC (NuScale)

Mark Chitty NuScale Dustin Greenwood NuScale Gary Becker NuScale Lisa Davies NuScale Bob Bromm NuScale Ryan Welch Public Enclosure 2

U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 PUBLIC TELECONFERENCE TO DISCUSS NUSCALE POWER, LLCS DESIGN CERTIFICATION APPLICATION REQUEST FOR ADDITIONAL INFORMATION RESPONSE 9122, RELATED TO NUSCALE STANDARD DESIGN CERTIFICATION 048 - 10.04.07 - CONDENSATE AND FEEDWATER SYSTEM APPLICATION SECTION: 10.4.7 January 31, 2018 General Comments

1. Question 10.4.7-1 requested condensate and feedwater system piping and instrumentation diagram (P&ID) be provided and included in the NuScale final safety analysis report (FSAR). In its response the applicant did not include the requested P&ID instead revised power cycle block diagram FSAR Figure 10.1-1.
a. NuScale Power, LLC (NuScale) would provide a simplified system diagram of the condensate feed water system that will be available at the NuScale Rockville, Maryland, office for audit.
2. Question 10.4.7-1 requested information on condensate and feedwater system (CFWS) inspection and testing after the nuclear plant module (NPM) is reinstalled in its bay and connected back to the CFWS system after refueling is completed. In its response to the question the applicant states that the CFWS is outside the scope of general design criteria (GDC) 45 and 46, and propose removing what they consider erroneous language from the FSAR. The U.S. Nuclear Regulatory Commission staff disagrees with the applicant conclusion that GDC 45 and 46 is not applicable.
a. NuScales assertion that GDC 45 and 46 are not applicable, because the CFWS contains SSCs that are part of the DHRS boundary. There would be no change to their RAI response.
3. Question 10.4.7-3 requested the applicant propose a combined operating license (COL) item to provide operating and maintenance procedures to address water hammer issues for the CFWS. The applicant response did not include the addition of the requested COL item. The COL items should have applicant provide procedures in accordance with NUREG-0927 as was done in APR 1400 DCD COL Item 10.4(8), and USAPWR DCD COL item 10.4(6).
a. NuScale stated that FSAR Tier 2, Section 3.6.3.1.4 indicates that The feedwater system (FWS) and steam generator (SG) contain design features that minimize the potential for and effect of water hammer. There would be no change to their RAI response.

Enclosure 3