ML15203A188

February 23-26, 2015, Summary of Beaver Valley Audit Associated with License Amendment Request to Transition to National Fire Protection Association 805 Standards

ML15203A188
Person / Time
Site:	Beaver Valley
Issue date:	07/28/2015
From:	Taylor Lamb Plant Licensing Branch 1
To:	Emily Larson FirstEnergy Nuclear Operating Co
Lamb T, NRR/DORL/LPLI-2, 415-7128
References
TAC MF3301, TAC MF3302
Download: ML15203A188 (8)

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Mr. Eric A. Larson, Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077

SUBJECT:

BEAVER VALLEY POWER STATION, UNIT NOS. 1AND2,

SUMMARY

OF AUDIT OF FEBRUARY 23-26, 2015, ASSOCIATED WITH LICENSE AMENDMENT REQUEST TO TRANSITION TO NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 (TAC NOS. MF3301 AND MF3302)

Dear Mr. Larson:

A review team, consisting of U.S. Nuclear Regulatory Commission (NRC) staff, and contractors from the Pacific Northwest National Laboratory (PNNL) and Southwest Research Institute/Center for Nuclear Waste Regulatory Analyses (CNWRA), conducted a regulatory audit at the Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1 and 2) in Shippingport, Pennsylvania on February 23 - 26, 2015. This audit was associated with the National Fire Protection Association Standard 805 (NFPA 805), "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," 2001 Edition, license amendment request (LAR) dated December 23, 2013 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML14002A086), as supplemented.

The regulatory audit supports the review of the LAR filed by First Energy Nuclear Operating Company to transition the plant's fire protection licensing basis to Title 10 of the Code of Federal Regulations (1 O CFR) Section 50.48(c), which endorses, with exceptions, NFPA 805, 2001 Edition.

The purpose of the audit was to gain an understanding of the information needed to support the NRC staff's licensing decision regarding the LAR and to develop high quality requests for additional information (RAI}, as needed. The information submitted in support of the BVPS-1 and 2 LAR is under final review. Any additional information needed to support the LAR review will be formally requested by the staff using the RAI process in accordance with Office of Nuclear Reactor Regulation Office Instruction LIC-101 , "License Amendment Review Procedures."

The audit team consisted of twelve NRC staff from NRC headquarters located in Rockville, Maryland, four NRC staff from NRC Region 1, two NRC contractors from PNNL, and two NRC contractors from CNWRA. Enclosure 1 provides the schedule of activities during the audit.

Enclosure 2 lists audit team participants from NRC, PNNL, CNWRA, BVPS, and the licensee's contractors who participated in the audit.

The NRC audit team held an entrance meeting on February 23, 2015, with the licensee's staff and contractors. During the remainder of the audit, team members participated in technical discussions based on their discipline according to the audit plan available in ADAMS under Accession No. ML15027A235. Technical discussions were focused on five major areas: fire

E. Larson protection engineering , safe shutdown/circuit analyses, fire probabilistic risk assessment, fire modeling, and programmatic* review. The audit team participated in plant walkdowns , tours, and technical presentations focusing on these topical areas.

At the conclusion of the audit, the audit team participated in a summary exit meeting with the licensee on February 26, 2015. The NRC staff provided a brief conclusion of the team goals, objectives, walkdown experience , and technical discussions.

Please direct any inquiries to me at (301) 415-7128 orTaylor.Lamb@nrc.gov.

Sine~ CJ!/a4 Taylor A. Lamb, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412

Enclosures:

1. Schedule of Activities

2. List of Participants

3. List of Documents Reviewed cc w/

Enclosures:

Distribution via Listserv

ML15203A188 *via memo OFFICE NRR/DORL/LPL 1-2/PM NRR/DORL/LPLI 1-2/LA N RR/ORA/AF PB/BC NAME TLamb LRonewicz AKlein*

DATE 7/27/15 7/28/15 6/9/15 OFFICE NRR/DRA/APRA/BC NRR/DORL/LPL 1-2/BC NRR/DORL/LPL 1-2/PM NAME SRosenberg* DBroaddus (REnnis for) TLamb DATE 6/9/15 7/27/15 7/28/15 Schedule of Activities Monday. February 23, 2015 8:00 am Audit team .members met onsite at the Beaver Valley Power Station 9:00 am Audit entrance meeting and virtual tour were conducted 10:00 am Commence technical discussions for fire probabilistic risk assessment (PRA),

fire modeling (FM) , and safe shutdown (SSD)/fire protection engineering (FPE). Breakout sessions started.

12:30 pm Dosimetry badges were distributed 1:15 pm Continue technical discussions for fire PRA and FM in support of fire PRA and SSD/FPE 4:00 pm Technical discussion on incipient detection plant modification 4:55 pm U.S. Nuclear Regulatory Commission (NRC) debrief meeting 5:00 pm Licensee wrap-up meeting Tuesday. February 24, 2015 8:00 am Briefings and preparations for plant walkdowns completed . Walkdowns conducted in predetermined areas according in accordance with walkdown plan. Groups were broken into SSD, PRA, and FM disciplines.

1:15 pm Continue technical reviews for fire PRA, FM , and SSD 4:00 pm Presentation on plant Attachment S and presentation of plant modifications 4:30 pm

• NRC debrief meeting 5:00 pm Licensee wrap-up meeting Wednesday. February 25, 2015 8:00 am Continued technical reviews for fire PRA and FM in support of fire PRA and SSD 1:00 pm Request for additional information timeline discussion 2:00 pm Combined SSD/PRA meeting 2:30 pm Radiation release discussion 3:00 pm Additional modification discussion with licensee 4:30 pm NRC debrief meeting 4:45 pm Licensee wrap-up 5:00 pm Simulator tour conducted Thursday, February 26, 2015 8:15 am Additional modification discussion with licensee 9:00 am Closeout meeting for FPE/SSD 9:30 am Closeout meeting for Fire Modeling 12:00 pm Exit meeting Enclosure 1

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

• Leslie Fields NRC Audit Team Leader

• Alex Klein NRC Branch Chief

• Hossein Hamzehee NRC Branch Chief

• Barry Miller NRC RAI Coordinator

• Taylor Lamb NRC Project Manager

• Charles Moulton NRC Quality Assurance

• Harold Barrett NRC FPE

• Thinh Dinh NRC SSD

• Naeem Iqbal NRC Fire Modeling

• David Gennardo NRC FPRA

• JS Hyslop NRC FPRA

• Mihaela Biro NRC Observer

• Stephanie Galbreath NRC Region I Observer

• Jeff Rady NRC Region I Observer

• John Richmond NRC Region I Observer

• Keith Young NRC Region I Observer Pacific Northwest National Lab (PNNL) Team

• Fleur de Peralta PNNL FPE

• Garill Coles PNNL FPRA Center for Nuclear Waste Regulatory Analyses (CNWRA) Team

• Marc Janssen CNWRA FM

• Nathan Hall CNWRA Programmatic Beaver Valley Power Station Team

• Eric Larson FE NOC Site Vice President

• Chaz McFeaters FE NOC Director, Site Operation

• Tim Steed FE NOC Director, Performance Improvement

• Dave Huff FE NOC Director, Maintenance

• Mark Manoleras FE NOC Director, Engineering

• Will Cothen FE NOC Manager, Compliance

• Carmen Mancuso FE NOC Manager, Design Engineering

• Francy Mantine FE NOC NFPA 805 Project Manager

• Thomas Migdal FE NOC Operations Enclosure 2

• Samantha Milosh FE NOC Operations

. Dave Held FENOC . Operations

• Rick Stremple FE NOC PRA Engineer

• Chris Lord FE NOC FPE

• Tom Collopy FE NOC FM

• Jeff Miller FE NOC Fire Marshall

. Derek Gmys FE NOC Fire System Engineer

. Brian Sepelak FE NOC Supervisor, Regulatory Compliance

• Dave McCreary FE NOC Licensing

List of Documents Reviewed

• Letter from J.J. Carey of Duquesne Light Company (DLC) to Steven A. Varga of the U.S. Nuclear Regulatory Commission (NRC), Re : Beaver Valley Power Station, Supplemental Information to Fire Protection -Appendix R Review Report, dated October 22, 1982

• Letter from J.J. Carey of DLC to Steven A. Varga of the NRC,

Reference:

Fire Protection - Response to Appendix R Requirements and Generic Letter 81-12 , dated June 30, 1982, and enclosures related to Chapters 6, 8, 9, 11

• Letter from Steven A. Varga of NRC to J.J. Carey of DLC,

Subject:

Request for Exemption from Some Requirements of Appendix R to 10 CFR 50, dated March 14, 1983

• Letter from Steven A. Varga of NRC to J.J. Carey of DLC,

Subject:

Request for Additional Information from Some Requirements of 10 CFR Part 50, dated August 30, 1984

• Letter from J.J. Carey of DLC to Steven A. Varga of the NRC , Reference : Appendix R -

Additional Exemption Requests Based on Generic Letter 83-33

• Document 8700-01 -062-0012, Fire PRA Task 11 Detailed Fire Modeling of 1-CV-3

• Document PRA-BV1-AL-R052, Level 2 LERF Analysis Notebook, Rev. 5a

• Report #2601 .620-000-001 : Detailed Fire Modeling Procedure

• Report #2701.620-000-004: V&V of Fire Modeling Tools

• Report #2701.620-000-020 : Unit 2 MCR Detailed Fire Modeling

• Report #2701.620-000-022 : Multi-Compartment Fire Analysis

• Report #2701 .620-000-026: Detailed Fire Modeling Report for 2-CB-1

• Report #2701.620-000-027 : Detailed Fire Modeling Report for 2-CB-6

• Report #2701 .620-000-028: Detailed Fire Modeling Report for 2-CV-1

• Report #2701 .620-000-039: Detailed Fire Modeling Report for 2-SB-2

• Report #2701 .620-000-040: Detailed Fire Modeling Report for 2-SB-3

• Report #2701 .620-000-050: Fire Modeling V&V

• Report #8700- 01.062~0017 : Detailed Fire Modeling Report for 1-CR-4 Enclosure 3

• Report #8700-01 .062-0023: Detailed Fire Modeling Report for 1-ES-1

• Report #8700-01 .062-0024: Detailed Fire Modeling Report for 1-ES-2

• Report #8700-01 .062:-0027: Detailed Fire Modeling Report for 1-NS-1

• Report #8700-01 .062-0034: Unit 1 MCR Detailed Fire Modeling