ML15041A168
| ML15041A168 | |
| Person / Time | |
|---|---|
| Site: | Summer |
| Issue date: | 02/13/2015 |
| From: | Shawn Williams Plant Licensing Branch II |
| To: | |
| Williams S | |
| References | |
| TAC ME7586 | |
| Download: ML15041A168 (10) | |
Text
LICENSEE:
South Carolina Electric & Gas Company FACILITY:
Virgil C. Summer Nuclear Station, Unit 1
SUBJECT:
SUMMARY
OF SITE AUDIT TO SUPPORT THE REVIEW OF A LICENSE AMENDMENT REQUEST FOR VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1, TO TRANSITION TO THE NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 FIRE PROTECTION LICENSING BASIS (TAC NO. ME7586)
The purpose of this summary is to document the results of an audit performed at Virgil C.
Summer Nuclear Station (VCSNS), Unit 1, associated with a National Fire Protection Standard 805 (NFPA 805) license amendment requested (LAR) dated November 15, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11321A172), as supplemented.
A review team, consisting of U.S. Nuclear Regulatory Commission (NRC) staff and contractors from the Center for Nuclear Waste Regulatory Analyses (CNWRA) and the Pacific Northwest National Laboratories (PNNL) participated in a regulatory audit of VCSNS, Unit 1, located in Jenkinsville, SC from June 4 to 8, 2012. The regulatory audit supported the review of the LAR filed by South Carolina Electric and Gas Company, to transition the plant's fire protection licensing basis to Title 10 of the Code of Federal Regulations Part 50.48(c), which endorses with exceptions the NFPA Standard 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition.
The purpose of the audit was to gain an understanding of the information needed to support the staff's licensing decision regarding the LAR and to develop requests for additional information (RAI), as needed.
The audit team consisted of 1 O NRC, 3 CNWRA (NRC contractor), and 1 PNNL (NRC contractor) staff, of which 1 NRC staff member was an audit observer. Enclosure 1 provides the schedules of activities during the audit. Enclosure 2 lists the NRC staff, the CNWRA staff, the PNNL staff, the licensee staff, and the licensee contractors who participated in the audit.
The Audit Team held an entrance meeting on Monday, June 4, 2012, with the licensee staff anp contractors, licensee management and NRC resident inspectors. During the remainder of the audit, team members met in smaller groups according to the Audit Plan. VCSNS staff provided plant walkdowns focusing on fire protection engineering, safe shutdown, fire probaqilistic risk assessment (PRA), and fire modeling.
Technical discussions were focused on five major areas: fire protection engineering, post-safe shutdown/circuit analysis, fire PRA, fire modeling, and programmatic review. Documents reviewed during the audit were made previously available on the VCSNS reference portal and some additional documents were placed on the portal based on discussions during the audit. contains a list of documents that were made available for review on the portal during the audit. In addition, hard copies that were reviewed during the audit are presented in this enclosure.
At the conclusion of the audit, the audit team participated in a summary exit meeting with VCSNS staff and management on June 8, 2012. The NRG staff expressed its appreciation to the VCSNS staff for providing informative walkdowns and presentations for the regulatory audit team.
Docket No.* 50-395 Facility Operating License No.: NPF-12
Enclosures:
1. Audit Schedule
- 2. Audit Participants
- 3. Audit Documents cc w/encls: Distribution via Listserv
Schedule of Activities Monday, June 4, 2012 8:00 am Audit team members met onsite at V.C. Summer Station 9:30 am Audit entrance meeting r
10:00 am Technical discussions commenced: LAR overview, Fire PRA Overview, Fire PRA 11:00am 12:00 pm
- 1:00 pm 4:45 pm 5:00 pm Quality/F&O resolution, Main Control Room Fire: CFAST Main Control Room Abandonment Time, Fire Modeling Generic Approach, Safe Shutdown: NSCA Development/Non Power Operations Development/Circuit Analysis/ Cable Selection Badging Lunch Breakout sessions conducted: Detailed review of FPE Attachments (1,L,T),
Detailed review of Safe Shut Down, Detailed review of fire modeling began, Detailed review of fire PRA began Review Areas: Continuation of technical discussions initiated in the morning Licensee debrief Adjourn TuesdayJune5,2012 8:00pm 12:00pm 5:00 pm Morning breakout sessions and interviews were conducted and the following technical presentations commenced:
- Rad Release - Conference Call Programmatic/Configuration Management/Quality Assurance/Training Modifications
. Fire Modeling: Performance Based Approach Safe Shutdown/Circuit Analysis Walkdowns/Tours were conducted: Turbine Building, Intermediate Building, Control Building, Diesel Generator Building; and Service Water Pumphouse
. Adjourn (Debrief held the morning of 6/6)
Wednesday, June 6, 2012 8:30 am 9:00am 4:00pm 4:30 pm 5:00 pm NRG staff conducted an audit team debrief to licensee staff on 06/05/2012 activities The following presentations, breakout sessions, and reviews were conducted:
NRG RAI process Fire Protection Engineering Fire Modeling Performance Based Approach Fire PRA Main Control Room Abandonment Main Control Room Fire/NSCA/Recovery Actions (high level)
Simulator tour was conducted NRG staff conducted an audit team debrief NRG debriefed licensee staff on the day's activities Adjourn ENCLOSURE 1 Thursday, June 7, 2012 8:00 am The following are presentations, breakout sessions, and reviews that were conducted:
4:00 pm 4:30 pm Configuration ManagemenVProgrammatic Feature Monitoring Fire Modeling Fire Protection Engineering Defense in Depth/Fire Risk Evaluation Fire Protection Engineering Unit 2 &3 Simulator Tour NRC Audit team debrief meeting NRC debriefed licensee Friday, June 8, 2012 8:30 am NRC conducted exit meeting with RAI Discussion 9:30 am Adjourn
List of Participants U.S. Nuclear Regulatory Commission (NRC) Team Alexander Klein Benjamin Beasley Leslie Fields Harry Barrett Robert Martin Jay Robinson Alayna Pearson Brian Metzger Gary Cooper JS Hyslop Jigar Patel Michael Snodderly Branch Chief/Oversight Branch Chief/Oversight Audit Team Leader Audit Technical Lead DORL PM Programmatic/RAI Coordinator FPE FM SSD/CA PRA PRA PRA Pacific Northwest National Laboratories (PNNL) Team Robert Layton FPE Center for Nuclear Waste Regulatory Analyses (CNWRA) Team Jason Huczek FM (lead)
Marc Janssens FM Eric Nette Programmatic Pat Mackin Programmatic VC Summer Staff (South Carolina Electric and Gas)
Mike Kammer Doug Edwards Tom Keckeisen Eric Rumfelt George Robertson Tammy Price Gerald Loignon Leo Kachnik Gil Williams Jody Galloway Brian Boucher Jeff Wagner Jeff Cook Tim Fanguy NFPA 805 Project Manager/Fire Protection Engineer Operations Management Station Fire Protection Coordinator-Ops Licensing Supervisor/Operations Licensing Engineer Licensing Administrative Support PRA Supervisor Fire PAA Engineer
- Design Supervisor:NSCNNPO/FM NSCNNPO Engineer Fire Protection Engineer: FM NEI00-01, Circuit Analysis NEI00-01, Circuit Analysis NEI00-01, Circuit Analysis VC Summer Contractor (SAIC)
Suzanne Loyd Paul Amico Fire PRA Analyst Contract Project Manager/Fire PRA ENCLOSURE 2 VC Summer Contractor (Worley Parsons)
Donn Kelly PCCKS/Circuit Analysis VC Summer Contractor (Kleinsorg)
FirePRA/FM Francisco Joglar Dan Funk NEI00-01, Circuit Analysis VC Summer Contractor (Nexus)
Bill Guess Steve Barrett NFPA 805 LAR Development Radioactive Release VC Summer Contractor (Tri En)
Fleur DePeralta John Cote NSCA/NPO Analysis NSCA/NPO Analysis Industry Representatives Paul Bemis Pacific Gas & Electric Co.
VC Summer Documents Available for Review on the Portal Presentations VCSNS NFPA805 Circuits Funk 20120602 VCSNS NFPA805 Configuration Control 20120531 VCSNS NFPA805 Fire Modeling FPRA CFAST VCSNS NFPA805 Fire Modeling FPRA FDTs VCSNS NFPA805 Fire Modeling FPRA Part 1 General VCSNS NFPA805 Fire Modeling MCR Analysis VCSNS NFPA805 Fire Modeling PB CFAST VCSNS NFPA805 FPRA MCR Abandonment Modeling VCSNS NFPA805 FPRA Quality 20120602 VCSNS NFPA805 Inspection Intro VCSNS NFPA805 Monitoring Program 20120531 VCSNS NFPA805 NPO 20120531 VCSNS NFPA805 NSCA20120603 VCSNS NFPA805 Rad Release Study 20120601 Engineering Evaluations TR0780E-001 FPEEE Safe Shutdown Separation TR0780E-004 FPEEE Fire Admin Features and Materials TR0780E-005 FPEE Fire Suppression TR0780E-006 FPEEE Fire Protection Calculations DC07810-033 Evaluation of Fire System Flooding Effects DC08010-007 Identification of Class 1 E Equipment Subject to Water Flooding Code Compliances DC0780D-001 NFPA Code of Record DC0780D-002 NFPA Code Compliance DC0780D-003 Code Compliance Auto Fire Suppression DC0780D-004 Code Compliance Manual Fire Suppression DC0780D-005 Code Compliance Fire Alarm_ Fire Detection DC0780D-006 Code Compliance Administrative Controls DC0780D-007 Code Compliance Passive Fire Protection Features DC0780D-008 Code Compliance Industrial Fire Brigade DC0780D-009 Code Compliance Life Safety DC00300-148 Revision 0 DC00300-146 Revision 0 DC00300-146 Revision 2 DC00300-146 Revision 1 ENCLOSURE 3
Fire Protection Program Documents 20120403 QAPD Final FPP022 Fire Prevention Rev 3 FPP031 Fire Preplans Rev 3B Fire Pre-plan Drawings 001- 098 NFPA805 LAR Quality Assurance Summary SAP131 Fire Protection Program Rev 6 TRP 2 Fire Protection R8D
- Fire Protection Evaluation Report (FPER) November 2011 Drawings - Analysis Boundary 023-050 Site Yard Plan 023-051 Typical Details for Conduit Area Boundaries 023-052 Yard Area and Manhole Locations 023-053 Auxiliary Building-Reactor Building. - Plan Subbasements EL. 374' 023-054 Auxiliary Building-Reactor Building. - Plan Subbasements EL. 388' 397' 023-055 Auxiliary Building-Plan Shield Slab - EL. 400 023-056 Auxiliary. Reactor, and Fuel Handling Building-Plan EL. 412' 023-057 Auxiliary Building-Plan Shield Slab EL. 426'-6 023-058 Intermediate and Diesel Generator Building -Plan EL. 412' 023-059 Auxiliary. Reactor, and Fuel Handling Building-Plan Mezzanine EL. 436' 023-060 Drumming Station, Hot Machine Shop-Plan EL. 436' and 447' 023-061 Auxiliary Building-Plan Shield Slab EL. 446' and 452' 023-062 Intermediate and Diesel Generator Buildings-Plan EL. 436' 023-063 Auxiliary. Reactor, and Fuel Handling Building-Plan EL. 463' 023-064 Intermediate and Diesel Generator Buildings-Plan EL. 463' 023~065 Reactor Building-Plan EL. 515' and 552'
- 023-066 Auxiliary Building-Plan EL. 485' 023-067 Reactor and Fuel Handling Building Section A-A Looking West 023-068 Auxiliary and Reactor Buildings-Section B-B Looking North 023-069 Intermediate and Diesel Generator Buildings-Misc. Sections 023-070 Control Building Plans EL. 412', 436', 463', and 482' 023-071 Control Building Plans EL. 425', 448', and Roof EL. 505' 023-072 Control Building Miscellaneous Sections 023-073 Turbine Building - Plan El. 412' 023-074 Turbine Building - Plan El. 436' 023-075 Turbine Building - Plan El. 463' 023-080 Service Water Intake Screen and Pumphouse 023-081 Circulation Water Intake Screen and Pumphouse EL. 436'-0 Plant Layout Drawings 001-001_AB_RB_EL374 001-002_AB_RB_EL388-397 001-011_AB_RB_FB_EL412 001-012_1B_DB_EL412 001-013_ TB_EL412 001-014_AB_MISC PLANS 001-021_AB_RB_FB_EL436
001-022_1B_DB_EL436 001-023_ TB_EL436 001-031 _AB_RB_FB_EL463 001-032_1 B_DB_EL463 001-033_ TB_EL463 001-034_RB_EL515-552 001-035_AB_EL485 001-061_BLDG LAYOUT 001-062_PLANT LAYOUT Hard Copies Reviewed Fire PRA Methods Report VCS Fire PRA Plant Final Report - Task 5 16 Rev 0 Portal Fire Protection Drawings VCS Fire PRA Plant Final Report Task 5 16 Rev O Fire PRA Quantification Calculations Fire Risk Quantifications Task 14 PSA-05, "Data Update Guideline with Emphasis on Bayesian Updating," Revision 2 DC-00300-150, Revision 0 DC00340-001, "Fire PRA Human Reliability Analyses Report, Task 5.12," Revision O PSA-08, "PRA Model Updates," Revision 4 PSA-03, "PRA Quantification Guideline," Revision 2 PRA Evaluation LK19897, "Dependent Event Analysis for the Fire HRA," August 9, 201 O Performance-Based Calculations:
- a.
DC0780F-096 Fire Modeling Fire Area CB10 VFDR
- b.
DC0780F-097 Fire Modeling Fire Area CB12 VFDR
- c.
DC0780F-103 Fire Modeling Fire Area CB 18 VFDR
- d.
DC0780F-173 Fire Modeling Fire Area IB11 VFDR MCR Abandonment Study (Calculation DC0780B-100, Fire Modeling: CB17.01)
Generic Methodology Document (Calculation DC0780B-001)
Multi Compartment Fire Modeling Generic Methodology (Calculation DC0780C-001)
Structural Steel Methodology (Calculation DC0780A-001)
Fire Modeling Scoping Report Task 5.8, Revision 0 Fire Modeling Calculations General Area 463' Elevation: DC0780B-027 Fire Modeling Fire Subzone AB01.21.02 Switchgear Room 436' Elevation: DC0780B-186 Fire Modeling Fire Zone IB22.02a General Area 436' Elevation: DC0780B-192 Fire Modeling Fire Zone IB25.01.02 Lower Cable Spreading Room: DC0780B-086 Fire Modeling Fire Zone CB04 Relay Room: DC0780B-088 Fire Modeling Fire Zone CB06 Upper Cable Spreading Room: DC0780B-099 Fire Modeling Fire Zone CB15 MCR-Horseshoe Area: DC0780B-100 Fire Modeling Fire Zone CB17.01 MCR-Support Area: DC0780B-101 Fire Modeling Fire Zone CB17.02 during the audit In addition, hard copies that were reviewed during the audit are presented in this enclosure.
At the conclusion of the audit, the audit team participated in a summary exit meeting with VCSNS staff and management on June 8, 2012. The NRC staff expressed its appreciation to the VCSNS staff for providing informative walkdowns and presentations for the regulatory audit team.
Docket No. 50-395 Facility Operating License No.: NPF-12
Enclosures:
- 1. Audit Schedule
- 2. Audit Participants
- 3. Audit Documents cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL2-1 R/F RidsAcrs_AcnwMailCTR Resource RidsNrrDorlDpr Resource RidsNrrDraAfpb Resource RidsNrrDraAhpb Resource RidsNrrDraApla Resource ADAMS Accession No. ML15041A168 RidsNrrDssStsb Resource RidsNrrLASFigueroa Resource RidsRgn2MailCenter Resource RidsNrrPMSummer Resource SWilliams, NRR OFFICE NRR/DORL/PM NRR/DORL/LPL2-1 /LA NRR/DORL/LPL2-1 /BC NRR/DORL/PM NAME SWilliams SFigueroa RPascarelli SWilliams DATE 02/12/15 02/12/15 02/12/15 02/13/15 Official Record Copy