ML13023A158
| ML13023A158 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/23/2013 |
| From: | Peter Bamford Plant Licensing Branch 1 |
| To: | Meena Khanna Plant Licensing Branch 1 |
| Bamford P NRR/DORL/LPL1-2 301-415-2833 | |
| References | |
| TAC ME9626 | |
| Download: ML13023A158 (4) | |
Text
January 23, 2013 MEMORANDUM TO: Meena Khanna, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
Peter Bamford, Project Manager /RA/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING CONTAINMENT LINER RANDOM AND NON-RANDOM REPORTS (TAC NO. ME9626)
The attached draft request for additional information (RAI) was transmitted by electronic transmission on January 23, 2013, to Mr. Phil Lashley, at FirstEnergy Nuclear Operating Company, LLC (FENOC, the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with FENOC in order to clarify the licensees submitted reports regarding examinations of the Beaver Valley Nuclear Power Station, Unit 1 containment liner.
The draft RAI is related to the licensees submittals dated February 14, 2011, and July 11, 2012.
The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow FENOC to evaluate and agree upon a schedule to respond to the RAI.
This memorandum and the attachment do not represent an NRC staff position.
Docket No. 50-334
Enclosure:
As stated
January 23, 2013 MEMORANDUM TO: Meena Khanna, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
Peter Bamford, Project Manager /RA/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING CONTAINMENT LINER RANDOM AND NON-RANDOM REPORTS (TAC NO. ME9626)
The attached draft request for additional information (RAI) was transmitted by electronic transmission on January 23, 2013, to Mr. Phil Lashley, at FirstEnergy Nuclear Operating Company, LLC (FENOC, the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with FENOC in order to clarify the licensees submitted reports regarding examinations of the Beaver Valley Nuclear Power Station, Unit 1 containment liner.
The draft RAI is related to the licensees submittals dated February 14, 2011, and July 11, 2012.
The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow FENOC to evaluate and agree upon a schedule to respond to the RAI.
This memorandum and the attachment do not represent an NRC staff position.
Docket No. 50-334
Enclosure:
As stated DISTRIBUTION:
Public RidsNrrPMBeaverValley Resource LPL1-2 R/F Accession No.: ML13023A158
- via email OFFICE LPL1-2/PM DLR/RASB/BC*
NAME PBamford MMarshall DATE 01/23/13 01/14/13 OFFICIAL RECORD COPY
DRAFT Enclosure REQUEST FOR ADDITIONAL INFORMATION REGARDING
SUMMARY
OF RESULTS FROM THE CONTAINMENT LINER RANDOM AND NON RANDOM EXAMINATIONS REPORT FIRST ENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION, UNIT 1 DOCKET NO. 50-334 By letter dated February 14, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110470404), FirstEnergy Nuclear Operating Company, (FENOC, the licensee) submitted the containment liner random and non-random examinations report for the Beaver Valley Power Station, Unit 1, fall 2010 refueling outage to satisfy portions of Commitment Nos. 32 and 33 of Appendix A of Supplement 1 to NUREG-1929, Safety Evaluation Report Related to the License Renewal of Beaver Valley Power Station, Units 1 and
- 2. By letter dated July 11, 2012 (ADAMS Accession No. ML12195A155), the licensee submitted the containment liner random and non-random examinations report for the Unit 1 Spring 2012 refueling outage. Additionally, the letter dated July 11, 2012, stated that Commitment Nos. 32, 33, and 34 of Appendix A to Supplement 1 to NUREG-1929 are considered closed by FENOC. Both reports stated that there was no evidence of degradation; therefore, the licensee stated that no additional sampling or successive re-examinations were required. The U.S. Nuclear Regulatory Commission (NRC, or Commission) staff is currently performing a technical review of the submittals and has determined that the additional information requested below is needed to complete its review.
Background/Regulatory Basis:
The commitments listed in NUREG-1929, Supplement 1, Appendix A, are required to be completed as specified in BVPS, Unit 1 license condition 2.F. According to the BVPS, Unit 1 Updated Final Safety Analysis Report, Section 5.2.4.1, the thickness of the containment liner cylinder section is 3/8 (.375) and the containment dome liner is 1/2 (.500). The submittal dated February 14, 2011, does not identify the locations of the measurements (i.e, cylinder or dome) and thus does not clearly identify the nominal thickness and corresponding acceptance criteria for the measurements reported. Without this information, the licensees conclusions regarding the measurements cannot be verified by the NRC staff. In addition, Commitment No.
32 states that if degradation is identified, it will be addressed through the corrective action program (as described in FENOC letter L-09-243). In FENOC letter L-09-243, dated September 4, 2009 (ADAMS Accession No. ML092530241), the licensee stated that locations with identified loss of material less than 10% but with a breadth and shape will be entered into the corrective action program and tracked as a point of interest for monitoring during subsequent outages until dispositioned. Five locations in the July 11, 2012, report had measurements below what appears to be the nominal thickness of the liner; however, it is not clear if these locations would be monitored in the future.
DRAFT Request for Additional Information:
- 1.
Identify the appropriate nominal thickness and acceptance criteria of all the measurement locations (random and non-random) in the letter dated February 14, 2011.
- 2.
Explain how it was determined what breadth and shape was necessary for degradation to be entered into the corrective action program and tracked. If none of the five locations below nominal thickness have been identified for future monitoring, explain why future monitoring is unnecessary. If any locations from the 2011 submittal fall below nominal thickness, include them in the discussion as well.