ML15343A071

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September 22-26, 2014, Summary of H. B. Robinson Steam Electric Plant, Unit 2 - Audit Associated with License Amendment Request to Transition to the National Fire Protection Association 805 Standard
ML15343A071
Person / Time
Site: Robinson Duke energy icon.png
Issue date: 12/23/2015
From: Martha Barillas
Plant Licensing Branch II
To:
Barillas M
References
CAC MF2746
Download: ML15343A071 (8)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 23, 2015 LICENSEE: Duke Energy Progress, Inc.

FACILITY: H. B. Robinson Steam Electric Plant Unit No. 2

SUBJECT:

SUMMARY

OF THE H. B. ROBINSON STEAM ELECTRIC PLANT UNIT NO. 2 - SEPTEMBER 22 - 26, 2014, AUDIT ASSOCIATED WITH LICENSE AMENDMENT REQUEST TO TRANSITION TO THE NATIONAL FIRE PROTECTION ASSOCIATION 805 STANDARD (CAC NO. MF2746)

By letter dated September 16, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13267A211), Duke Energy Progress, Inc. (Duke Energy), the licensee, for the H. B. Robinson Steam Electric Plant Unit No. 2 (Robinson), submitted a license amendment request (LAR) to adopt a new fire protection licensing basis that complies with the requirements of Title 10 of the Code of Federal Regulations, Sections 50.48(a) and (c); the guidance in Regulatory Guide 1.205, Revision 1, "Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants"; and National Fire Protection Association (NFPA) 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants" (2001 Edition). The purpose of this summary is to document the results of the audit performed at Robinson associated with this LAR.

An audit team, consisting of U.S. Nuclear Regulatory Commission (NRC) staff and contractors from the Pacific Northwest National Laboratories (PNNL) and Southwest Research Institute (SwRl)/Center for Nuclear Waste Regulatory Analyses (CNWRA) conducted a regulatory audit of Robinson, which occurred during September 22 - 26, 2014, at the Duke Energy offices in Charlotte, North Carolina. The purpose of the audit was to understand what information the NRC staff needed to support its review of the LAR and to develop requests for additional information as needed. The information submitted in support of the LAR is under final review, and the staff will request any additional information needed to support its review in accordance with NRC Office of Nuclear Reactor Regulation, Office Instruction LIC-101, "License Amendment Review Procedures" (ADAMS Accession No. ML113200053).

The audit team consisted of ten NRC staff, three PNNL staff, and one CNWRA staff. provides the schedule of activities during the audit. Enclosure 2 lists NRC staff, PNNL staff, CNWRA staff, and the licensee's staff and contractors that participated in the audit. contains a list of documents reviewed by the team. The audit plan, dated September 4, 2014, is available in ADAMS at Accession No. ML14246A509.

The audit team held an entrance meeting with the licensee's staff and contractors on September 22, 2014. During the remainder of the audit, the licensee's staff provided plant walkdowns and presentations on fire protection engineering, post-fire safe shutdown circuit analysis, fire probabilistic risk assessment, and fire modeling. NRC and licensee discussions focused on these subjects and on fire protection programmatic review.

At the conclusion of the audit, the NRC's audit team participated in a summary exit meeting with the licensee's staff and management on September 25, 2014.

Please direct any inquiries to Dennis Galvin at (301) 415-6256 or Dennis.Galvin@nrc.gov.

Sincerely, Martha Barillas, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-261

Enclosures:

1. Schedule of Activities
2. List of Participants
3. List of Documents Reviewed During the Audit cc w/enclosures: Distribution via Listserv

Schedule of Activities Monday September 22. 2014 9:00AM Audit entrance meeting Plant overview discussions Virtual tour Self-induced station blackout discussion Overview of fire event 1:00 PM Technical breakout sessions performed: fire modeling (FM), radioactive release, safe shutdown, fire probabilistic risk assessment (PRA), main control room (MCR) abandonment, multiple spurious operations, recovery actions, non-power operations, nuclear safety capability assessment, and fire protection engineering (FPE)

Review of plant walkdown plans and tour areas 4:45 PM U.S. Nuclear Regulatory Commission (NRC) end of day debrief 5:00 PM Licensee wrap-up briefing Tuesday September 23. 2014 8:30 AM Plant walkdowns and tour - preparation for tours: safe shutdown analysis (SSA),

FM, PRA, and FPE Pre-tour safety/security briefing 1:00 PM Technical discussion/breakouts for all focus areas 4:30 PM NRC debrief 4:45 PM Licensee wrap-up briefing Enclosure 1

Wednesday September 24, 2014 9:00 AM PRA breakout Joint FM/PRA breakout - MCR abandonment 10:30 AM FM breakout SSA breakout 1:00 PM Observer meeting 2:00 PM Request for additional (RAI) information timeline discussion 2:30 PM Joint session 4:45 PM NRC debrief 5:00 PM Licensee wrap-up briefing Thursday September 25, 2014 9:00AM Final RAI closeout meetings for SSA, FM, and FPE Internal PRA meeting 10:00 AM Joint PRA discussion 11:30 AM Lunch 12:30 PM PRA closeout 1:30 PM Audit exit meeting

List of Participants U.S. Nuclear Regulatory Commission (NRC) Team

  • Alex Klein NRC Branch Chief
  • Hossein Hamzehee NRC Branch Chief
  • Paul Lain NRC Quality Assurance/FPE
  • Harold Barrett NRC FPE/SSA
  • Daniel O'Neal NRC PRA Pacific Northwest National Laboratory (PNNL) Team
  • Karl Bohlander PNNL FPE/SSA
  • Garill Coles PNNL PRA Center for Nuclear Waste Regulatory Analyses (CNWRA) Team
  • Jason Huczek CNWRA Fire Modeling Duke Energy Response Team
  • Jeff Ertman Duke Energy (Corporate) Fleet NFPA 805 Program Manager (FPE) Lead
  • Kelly*Lavin Duke Energy (Corporate) Robinson (RNP) NFPA 805 Implementation Project Manager
  • Justin Wild Duke Energy (RNP) Regulatory Affairs
  • Bob Rishel Duke Energy (Corporate) PRA Director
  • Bruce Morgen Duke Energy (Corporate) PRA Manager
  • Jamie McCrory Duke Energy (Corporate) PRA Lead
  • Harold Stiles Duke Energy (Corporate) PRA
  • Alan Holder Duke Energy (Corporate) Programmatic Lead
  • Joelle DeJoseph Duke Energy (Corporate) FM Lead
  • Cathy Chan Duke Energy (Corporate) SSA
  • Derek Schroeder Duke Energy (RNP) RNP Program Manager
  • Frank Modlin Duke Energy (RNP) SSA
  • Marie Conrad Duke Energy (RNP) SSA
  • Tim Groch Duke Energy (RNP) FPE
  • Stan Chingo Duke Energy (RNP) FPE Enclosure 2
  • Jason Outlaw Duke Energy (RNP) FPE
  • Kevin McGee Duke Energy (RNP) Operations Fire Marshall
  • Bob Femal Duke Energy (RNP) Operations Support (SSA and NPO)
  • Richardson, Michael Reg Srvs Lead/Licensing
  • Baker, Steve Engr Audit Lead/Design Engr
  • Hampshire, Dave Engr Lead/FP Engr
  • Hromyak, Dan Engr Sys Engr/FP Engr
  • Arsene, Alex Engr FP Engr/FP Engr
  • Baradaran, Rasool PRA Lead/PRA
  • Pyo, John PRA Analyst/PRA
  • Barber, Nathan PRA Analyst/PRA (Seismic)
  • Shepard, Matt PRA Analyst/PRA
  • lmbaratto, David PRA Analyst/PRA
  • Montoya, Ariel Engr Lead EE/EE
  • Lodolo, Larry Engr SSD EE/EE (CIRCAL)
  • Leatham, Russ Engr EE/EE
  • Chitwood, Tony Operations Support/OPS (NPO)
  • Williams, Dave Operations Support/OPS (NPO)
  • Wernet, Todd Fire Chief Support/OPS (Fire Dept.)
  • Horstman, Bill Engr Lead CE/Engr (Seismic)

List of Documents Reviewed During the Audit

1. Hughes Report No. 0004-0042-000-001, "Evaluation of Development and Timing of HGL

[Hot Gas Layer] Conditions in RNP [Robinson Nuclear Plant] Fire Zone 20," Revision 1

2. Hughes Report No. 0004-0042-412-002, "Evaluation of MCR [Main Control Room]

Abandonment Times at the H.B. Robinson NP," Revision 1

3. NED-M-MECH-1008, "Fire Zone of Influence Calculation," Revision 0
4. NED-M-MECH-1009, Thermal Damage Times of Cables Above a Burning Ignition Source," Revision 0, January 2008
5. RND-M-MECH-1826, "Hot Gas Layer Calculation," Revision 1, August 2013
6. RNP-M-MECH-1884, "V&V [Verification and Validation] of Fire Models Supporting RNP Fire PRA [Probabilistic Risk Assessment]," Revision 0, August 2013
7. RNP-0206, "Compressor Oil Fires in Fire Zone 7," Revision 0, November 2013 (in subfolder RNP-0206)
8. RNP-F/PSA-0089, "RNP Fire PRA [Probabilistic Risk Assessment] Multi-Compartment Analysis," Revision 0, May 2013
9. RNP-F/PSA-0094 Part 1, Attachment 09, "Structural Steel-Fire Interaction Analysis,"

Revision 3, April 2013

10. Thermal-hydraulic analysis used as a basis for timing used in fire PRA success criteria Enclosure 3

At the conclusion of the audit, the NRC's audit team participated in a summary exit meeting with the licensee's staff and management on September 25, 2014.

Please direct any inquiries to Dennis Galvin at (301) 415-6256 or Dennis.Galvin@nrc.gov.

Sincerely, IRA CPfefferkorn for/

Martha Barillas, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-261

Enclosures:

1. Schedule of Activities
2. List of Participants
3. List of Documents Reviewed During the Audit cc w/enclosures: Distribution via Listserv DISTRIBUTION:

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NAME DGalvin MBarillas (LRonewicz for) LFields BClavton DATE 12/15/2015 12/15/2015 12/15/2015 5/11/2015 OFFICE DRA/AFPB/BC* DRA/APLA/BC* DORL/LPLll-2/BC DORL/LP LI 1-2/PM NAME AKlein SRosenberg BBeasley ( CPfefferkorn for)

MBarillas DATE 5/11/2015 5/11/2015 12/22/2015 12/23/2015 OFFICAL RECORD COPY