ML102980099
| ML102980099 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/27/2010 |
| From: | Nadiyah Morgan Plant Licensing Branch 1 |
| To: | Harden P FirstEnergy Nuclear Operating Co |
| Morgan N, NRR/DORL, 415-1016 | |
| References | |
| TAC ME1052, TAC ME4104 | |
| Download: ML102980099 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Octoher 7.7, 2010 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 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE RISK-INFORMED INSERVICE INSPECTION PROGRAM RELIEF REQUESTS (TAC NOS. ME4104 AND ME4105)
Dear Mr. Harden:
By letter dated June 10, 2010, FirstEnergy Nuclear Operating Company (the licensee) submitted a request for authorization of a proposed alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI Categories B-F, B-J, C-F-1, and C-F-2 requirements for examining Class 1 and 2 piping components via non-destructive examination at Beaver Valley Power Station, Unit NO.1 (BVPS-1) during the fourth inservice inspection (lSI) interval and at BVPS-2 during the BVPS-2 third lSI interval.
The Nuclear Regulatory Commission (NRC) staff is reviewing the submittals and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The NRC staff is requesting a response to the RAI within 45 days of receipt.
The NRC staff considers that timely responses to RAls help ensure sufficient time is available for NRC staff review and contribute toward the NRC goal of efficient and effective use of staff resources.
P. Harden
- 2 If you have any questions regarding this issue, please contact me at (301) 415-1016.
Sincerely, adiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412
Enclosure:
RAI cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE RISK-INFORMED INSERVICE INSPECTION RELIEF REQUESTS FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP.
OHIO EDISON COMPANY THE TOLEDO EDISON COMPANY BEAVER VALLEY POWER STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412 By letter dated June 10, 2010 (Agencywide Documents Access and Management System Accession No. ML101650649), FirstEnergy Nuclear Operating Company (the licensee) submitted a request for authorization of a proposed alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)Section XI, Categories B-F, B-J, C-F-1, and C-F-2 requirements for examining Class 1 and 2 piping components via non-destructive examination at Beaver Valley Power Station, Unit NO.1 (BVPS-1) during the fourth inservice inspection (lSI) interval and at BVPS-2 during the BVPS-2 third lSI interval. In order to complete the review, the Nuclear Regulatory Commission (NRC) staff needs the following additional information:
Probabilistic Risk Assessment Licensing Branch Review:
- 1. In Enclosure C, "Probabilistic Risk Assessment [PRA] Technical Adequacy for Risk-Informed Inservice Inspection [RI-ISI]," of the submittal, the licensee stated that the, "risk management process ensures that the applicable PRA model remains an accurate reflection of the as-built and as-operated plant." Describe how you plan to maintain a living RI-ISI program for BVPS-1 and 2 during the fourth and third 1O-year intervals, respectively, which can be affected by changes in plant design or operations.
- 2. Were the risk calculations performed according to all the guidelines provided on page 213, Section 4.4.2 of WCAP-14572, Revision 1-NP-A? If not, provide a description and justification of any deviation. In addition, provide a statement that verifies that the risk from the revised program continues to remain lower when compared to the last deterministic ASME Code,Section XI inspection program.
- 3. Regulatory Guide 1.200, Rev. 2 includes supporting requirements describing acceptable fire and seismic PRA analyses. Describe how fire and seismic initiating events are accounted for in the proposed RI-ISI program for BVPS-1 and 2.
Enclosure
- 2 Piping and Non-Destructive Examination Review:
- 4. Identify the PRA model number used for the current RI-ISI program.
- 5. Provide values for the changes in core damage frequency and changes in large early release frequency for BVPS-1 and 2 compared to ASME Code,Section XI lSI program values, and to the third lSI interval RI-ISI program values.
- 6. For the 24 pipe segments of BVPS-1 and the 6 pipe segments of BVPS-2 that were moved from the High Safety Significant category to the Low Safety Significant category, as a result of the expert panel evaluation, identify these pipe segments, provide the Risk Reduction Worth value, and explain why each segment's safety significance changed.
- 7. Identify any augmented inspection programs which have been subsumed in the proposed RI-ISI program and discuss the reason(s) for the change.
- 8. Describe how the industry initiative Materials Reliability Program-139, Revision 1, inspection guidelines have been implemented in conjunction with the RI-ISI program.
'.. ML102980099 OFFICE DORL/LPLI-1/PM DORL/LPLI-1/LA DCI/CPNB/BC DRAIAPLAlBC DORULPLI-1/BC NAME NMorgan SUttle TLupold DHarrison NSalgado DATE 10/27/10 10/26/10 09/29/2010 08/25/2010 10/27/10