ML121090042
| ML121090042 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/30/2012 |
| From: | Peter Bamford Plant Licensing Branch 1 |
| To: | Harden P FirstEnergy Nuclear Operating Co |
| Bamford, Peter J., NRR/DORL 415-2833 | |
| References | |
| Download: ML121090042 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 30, 2012 Mr. Paul A. Harden 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. 1 AND 2 - NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 LICENSE AMENDMENT APPLICATION ONLINE REFERENCE PORTAL
Dear Mr. Harden:
By letter dated June 29, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML111800765), FirstEnergy Nuclear Operating Company (FENOC, the licensee) provided a submittal date for a license amendment request (LAR) incorporating National Fire Protection Association Standard (NFPA) 805 for the Beaver Valley Power Station, Unit Nos. 1 and 2.
To improve the efficiency of the U.S. Nuclear Regulatory Commission (NRC) reviews, the NRC staff has discussed the use of an online reference portal with the NFPA 805 licensees (see meeting summary dated December 20, 2011, ADAMS Accession No. ML113340218) that would allow the NRC staff and contractors limited read-only access to the basis documents and other reference materials cited in the applications. While creating and maintaining a reference portal site is voluntary, the NRC understands that all NFPA 805 licensees have agreed to participate in this activity in support of the NRC staff review of the NFPA 805 LAR The online reference portal would allow the NRC staff to audit basis documents to determine whether the information included in the documents support the application. Documents identified as necessary for analysis of the application will be identified by the NRC staff. The licensee will be formally requested to submit those documents on the NRC docket. Use of the online reference portal is acceptable as long as the following conditions are met:
- The online reference portal will be password-protected and passwords will be assigned to those directly involved in the review on a need-to-know basis; The online reference portal will be sufficiently secure to prevent staff from printing, saving, or downloading any documents; and
- Conditions of use of the online reference portal will be displayed on the log-in screen and will require concurrence by each user.
The NRC staff requests that the portal be populated with the documents listed in the enclosure to this letter when the NFPA 805 LAR is submitted to the NRC. This will help with the preparation for the site audits and increase effectiveness of the review prior to the audit. Once
P. Harden
- 2 the NRC accepts the LAR for review, it would be helpful if the portal is ready for immediate access to the NRC staff. Therefore, we request that information to access the portal, such as username and password, be sent to your NRC plant project manager immediately after the LAR has been accepted by the NRC.
The conditions associated with the online reference portal must be maintained throughout the duration of the review process. Please provide written confirmation to the NRC Document Control Desk that you agree to the terms and conditions set forth in this letter.
Should you have any questions regarding this letter, please contact me at 301-415-2833, or via email at peter.bamford@nrc.gov. Should you have any questions regarding the NFPA 805 portal, please contact Ms. Leslie Fields, Senior Project Engineer, at 301-415-1186, or via email at leslie.fields@nrc.gov.
Sincerely,
~Lt Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412
Enclosure:
As stated cc w/encl: Distribution via Listserv
GENERIC LIST OF SHAREPOINT PORTAL REQUESTED DOCUMENTS FOR NFPA 805
- 1.
National Fire Protection Association (NFPA) Code Deviations and Justifications
- 2.
All applicable Probabilistic Risk Assessment (PRA) Peer Review Reports
- 3.
All site calculations referenced in the License Amendment Request (LAR)
- 4.
Credited Fire Protection (FP) System and Feature Drawings
- a.
Layout Drawings: fire barriers, installed fire detection and suppression systems, fire areas, fire zones, stairwells, fire doors, fire dampers, etc.
- b.
Piping and Instrumentation Diagrams (P&IDs): FP Water System
- c.
System Descriptions for Fire Suppression, Water Supply, and Detection (including incipient or very early warning fire detection (VEWFD>>
- d.
Hydraulic Calculations for Fire Service and Fire Suppression System Water Demand (if used to support non-fire water use in Title 10 of the Code of Federal Regulations, Section 50.48(c)(2)(vii>>
- 5.
Drawings related to systems credited in the Nuclear Safety Capability Assessment (NSCA) as well as those required to fully understand plant response:
- a.
P&IDs: Reactor Coolant System, Main Steam, Main Feedwater, Circulating Water, Service Water, etc.
- b.
Safe Shutdown/NSCA Logic Diagrams (if used)
- c.
Electrical Distribution System One-Lines (alternating current (AC) and direct current (DC>>
- 6.
Those documents that fulfill the NFPA 805 requirement for "Design Basis Document (DBD)"
- a.
Fire Area Calculations (e.g., Fire Safety Analyses, Fire Risk Analyses, Plant Change Evaluations, Fire Risk Evaluations, etc.)
- b.
NSCA Calculation (Safe Shutdown/Circuit Analysis)
- c.
Multiple Spurious Operation (MSO) Expert Panel Report
- d.
Thermo-Hydraulic Analysis serving as the basis for Variance from Deterministic Requirements (VFDR) and recovery action (RA) timing
- e.
Evaluation of Recovery Actions for feasibility
- f.
Fire Hazards Analysis (FHA) (if separate from the fire area calculations)
- g.
Non-Power Operation (NPO) Calculation(s)
- h.
Radioactive Release Calculation(s)
- i.
Pre-Fire Plans
- 7.
Fire PRA Calculations
- a.
Plant Boundary/Partitioning Methods and Results (TASK 1)
- b.
Component Selection Calculation (TASK 2)
- c.
Cable Selection and Circuit Analysis (TASKS 3, 9, and 10)
- d.
Ignition Frequency Calculation (TASK 6)
- e.
Fire PRA Quantification Calculations (TASK 5) including:
- i.
Seismic Fire Interactions (TASK 13) Methodologies and Results (including assumptions) ii.
Screening Methodologies and Results (TASKS 4 and 7) (including assumptions)
Enclosure
- 2 iii.
Fire Risk Quantifications (TASK 14) Methodologies and Results (including assumptions) iv.
Multi-Compartment Screening and Analysis
- v.
Post-Fire Human Reliability Analysis (HRA) Methodologies and Results (including assumptions) (TASK 12) vi.
Detailed proposed modification descriptions (Engineering Change Requests/Records) sufficient to comprehend potential impact/improvement to Fire PRA
- f.
NFPA 80S Application Calculation (provides all the delta risk calculations for VFDRs)
- g.
Control Room Risk Calculation
- h.
Uncertainty and Sensitivity Calculations (TASK 1S)
- i.
Fire Modeling Calculations used to support the Fire PRA (zone of influence (ZOI), hot gas layer, bounding, detailed fire modeling, etc.)
ii Plant Specific Verification and Validation (V&V) Analysis iii.
Non-Public V&V References (e.g., Electric Power Research Institute (EPRI) Fire Modeling, Generic Treatment) iv.
Fire Modeling Assumptions and Calculations performed to support target selection (e.g., ZOI, secondary fires, transient combustible/ignition sources) including those that deviate from NUREG/CR-68S0 (TASKS 8 and 11)
- 8.
Fire Modeling used in the Fire Modeling Performance-Based Approach
- a.
Plant Specific V&V Analysis performed
- b.
Non-Public V&V References (e.g., EPRI Fire Modeling, Generic Treatments, etc.)
- c.
Fire Modeling Assumptions and Calculations performed to support Performance Based Evaluations (e.g., ZOI, secondary fires, transient combustible/ignition sources, etc.) considered outside NUREG/CR 68S0 Assumptions and Parameters (TASKS 8 and 11)
- d.
Hot Gas Layer (HGL) Determination Calculations (including assumptions)
- 9.
Fire Protection Program Manual
- 10.
Fire Protection Quality Assurance (QA) Program (including FP Structure System Components (SSCs) and FP Features)
- 11.
NFPA 80S Monitoring Program Calculations and Procedures
- 12.
Technical Requirements Manual (TRM)
- 13.
Updated Final Safety Analysis Report (UFSAR) Changes (including current UFSAR 9.S.1 Fire Protection and Section 7.4 Alternate Shutdown/lnstrumentation)
P. Harden
-2 the NRC accepts the LAR for review, it would be helpful if the portal is ready for immediate access to the NRC staff. Therefore, we request that information toaccess the portal, such as username and password, be sent to your NRC plant project manager immediately after the LAR has been accepted by the NRC.
The conditions associated with the online reference portal must be maintained throughout the duration of the review process. Please provide written confirmation to the NRC Document Control Desk that you agree to the terms and conditions set forth in this letter.
Should you have any questions regarding this letter, please contact me at 301415-2833, or via email at peter.bamford@nrc.gov. Should you have any questions regardingthe NFPA 805 portal, please contact Ms. Leslie Fields, Senior Project Engineer, at 301-415-1186, or via email at leslie.fields@nrc.gov.
Docket Nos. 50-334 and 50-412
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsAcrsAcnw_MailCTR Resource RidsRgn1 MailCenter Resource RidsNrrPMBeaverValley Resource JRobinson, AFPB Sincerely, IRAJ Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsOgcRp Resource RidsNrrDraAfpb Resource RidsNrrDorlDpr Resource RidsNrrLAABaxter Resource PLain, AFPB LPLI-2 R/F RidsNrrDraAplb Resource RidsNrrDorlLpl1-2 Resouce LFields, AFPB HBarrett, AFPB ADAMS Accession Number: ML121090042;;......__===;=-=_
OFFICE LPLI-2/PM LPLI*2/LA NAME PBamford ABaxter DATE 9/18/12 4/23/12 AFPB/BC
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