L-12-437, Containment Liner Random and Non-Random Examinations Report
| ML12353A595 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/18/2012 |
| From: | Harden P FirstEnergy Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| L-12-437 | |
| Download: ML12353A595 (10) | |
Text
FENOC FirstEnergy Nuclear Operating Company Paul A. Harden Site Vice President December 18, 2012 L-12-437 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No.2 Docket No. 50-412, License No. NPF-73 Containment Liner Random and Non-Random Examinations Report Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 724-682-5234 Fax: 724-643-8069 FirstEnergy Nuclear Operating Company (FENOC) hereby submits a revised Containment Liner Random and Non-Random Examinations Report for the Beaver Valley Power Station, Unit No.2 spring 2011 refueling outage (2R15). This report supersedes the report previously submitted by FENOC letter dated June 27,2011 (Accession No ML111790129).
The minimum containment liner thickness for location 2RN-039 and the maximum containment liner thickness for location 2RN-074 are corrected in Appendix I, "2R15 Completed Random Examinations," of the enclosed report. The need for the first correction was entered in the FENOC corrective action program. An extent of condition review identified the need for the second correction. The corrections did not change the conclusion that there was no evidence of loss of material at these examination locations.
There are no regulatory commitments contained in this letter. If there are questions or if additional information is required, please contact Mr. Thomas A Lentz, Manager - Fleet Licensing, at (330) 315-6810.
Sincerely, 2-
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Paul A Harden
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Beaver Valley Power Station, Unit No.2 L-12-437 Page 2
Enclosure:
2R15 Containment Liner Random and Non-Random Examinations Report, Revision 1 cc:
NRC Region I Administrator NRC Resident Inspector NRR Project Manager Director BRP/DEP Site BRP/DEP Representative
BEAVER VALLEY POWER STATION UNIT 2 2R15 Containment Liner Random and Non-Random Examinations Report, Revision 1 Issue date:
Prepared by:
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2R15 CONTAINMENT LINER RANDOM AND NON-RANDOM EXAMINATIONS REPORT, REVISION 1 TABLE OF CONTENTS Page Number Cover Page 1
Table of Contents 2
Examination Summary 3
References 5
Appendix I - Summary of Random Exams 2 pages Appendix II - Summary of Non-Random Exams 1 page 2
EXAMINATION
SUMMARY
FirstEnergy Nuclear Operating Company (FENOC) performed supplemental volumetric examinations on the Beaver Valley Power Station, Unit No.2 (BVPS-2) containment liner during the fifteenth refueling outage (2RI5) to satisfy BVPS-2 license renewal commitments 33 (random) and 34 (non-random). These commitments are listed in BVPS-2 Updated Final Safety Analysis Report Table 19-1. A summary of the commitments are as follows:
License Renewal Commitment 33:
The following paragraph provides a summary of commitment 33.
Supplemental volumetric examinations will be performed on the BVPS-2 containment liner prior to the period of extended operation. A minimum of seventy-five randomly selected (as described in FENOC Letter L-09-205) sample locations will be examined (as described in FENOC Letter L-09-243). If degradation is identified, it will be addressed through the corrective action program (as described in FENOC Letter L-09-243).
If degradation (greater than 10 percent of the nominal thickness not attributable to fabrication/erection practices) is identified in the random samples examined using ultrasonic testing (UT), UT examinations shall be performed on additional random samples, to ensure a 95 percent confidence that 95 percent of the unexamined accessible containment liner is not degraded. If additional degradation is identified, the sample size for the UT examinations shall be further expanded until the statistical sampling has achieved the 95 percent confidence goal described previously. All areas with degradation shall be reexamined over at least the next three successive inspection periods to ensure that progression of the degradation is not occurring.
The initial BVPS-2 sample lot of random ultrasonic examinations will commence by the end of the Unit 2 Refueling Outage in 2011. The random sample plan (including additional examinations, if required) will be completed by May 27, 2027.
License Renewal Commitment 34:
The following paragraph provides a summary of commitment 34.
Supplemental volumetric examinations will be performed on the BVPS-2 containment liner. A minimum of 8 non-randomly selected locations will be examined, focusing on areas most likely to experience degradation based on past operating experience (as described in FENOC Letter L-09-242). If degradation is identified, it will be addressed through the corrective action program.
If degradation (greater than 10 percent of the nominal thickness not attributable to fabrication/erection practices) is identified in the non-random areas examined using ultrasonic testing (UT), UT examinations shall be performed at additional non-random areas, to be selected based on this operating experience. Should additional degradation be 3
identified, additional non-random areas shall be UT examined until no further degradation (greater than 10 percent of the nominal thickness) is identified. All areas with degradation shall be reexamined over at least the next three successive inspection periods to ensure that progression of the degradation is not occurring.
Examinations will be completed by May 27,2027.
Summary of Random Scope Examinations:
Sixty-one of the seventy-five randomly selected examinations were performed during the BVPS-2 2R15 refueling outage. Sixty of sixty-one locations examined as part of the sample plan were completed with no evidence of loss of material. The UT examination of Location 2RN-063 revealed an area of lower than expected thickness and is addressed below.
The statistical screening criterion for the examinations had been established as ninety percent of the nominal wall thickness (0.337 inches for the shell and 0.450 inches for the dome). Appendix I contains the 2R15 random examinations results.
Subsequent Random Examination Evaluations:
Examination of random location (2RN-063) required additional actions during 2R15.
Manual UT examination of location 2RN-063 identified an indication on the inaccessible side of the liner, having a general thickness below the statistical screening criterion. The lowest thickness measured within the 2RN-063 examination area was 0.310 inch. A subsequent autoscan examination of2RN-063 verified the presence of the indication along with an approximately 2 inch (vertical) by 10 inch (horizontal) area, extending beyond location 2RN-063, with lower thickness than the surrounding area. The general thickness of this 2 inch by 10 inch area was between 0.300 inch and 0.400 inch. The lowest thickness observed within the extended area was 0.267 inch at a localized point.
The minimum design thickness for the general wall of the liner at this location is 0.213 inch. The localized point dimension is 0.250 inch in the vertical axis by 0.300 inch in the horizontal axis. For a localized point having the dimensions noted above, the minimum required thickness is 0.032 inch.
The apparent cause of the thinner liner thickness cannot be determined with certainty at this time since the concrete covering of the liner precludes access to visually examine the area. 2RN-063 and the extended area will be examined for at least the next three successive inspection periods as required by the renewed operating license to ensure that the degradation is not progressing. The results of these successive examinations will determine the extent of potential examination scope expansion.
Summary of Non-Random Scope Examinations:
Eight non-random locations were performed during the BVPS-2 2R15 refueling outage.
The locations selected included irregular contours of the liner, non-coated below grade areas and repainted areas of the liner. Acceptance criterion for the examinations had been established as ninety percent of the nominal wall thickness (0.337 inches). All eight non-4
random locations were completed with no evidence of loss of material. Appendix II contains the 2R15 non-random examination results.
References
- 1. FENOC Letter L-09-205, "Supplemental Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application (T AC Nos. MD6593 and MD6594), and License Renewal Application Amendment No. 39," dated July 28,2009, Accession Number ML092110117.
- 2. FENOC Letter L-09-242, "Supplemental Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application (T AC Nos. MD6593 and MD6594), and License Renewal Application Amendment No. 40," dated September 2,2009, Accession Number ML092510168.
- 3. FENOC Letter L-09-243, "Supplemental Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application (T AC Nos. MD6593 and MD6594), and License Renewal Application Amendment No. 41," dated September 4,2009, Accession Number ML092530241.
5
APPENDIX I 2R15 COMPELETED RANDOM EXAMINATIONS Component 10 2RN-015 2RN-016 2RN-017 2RN-018 2RN-019 2RN-020 2RN-021 2RN-022 2RN-023 2RN-024 2RN-025 2RN-026 2RN-027 2RN-028 2RN-029 2RN-030 2RN-031 2RN-032 2RN-033 2RN-034 2RN-035 2RN-036 2RN-037 2RN-038 2RN-039 2RN-040 2RN-041 2RN-042 2RN-043 2RN-044 2RN-045 2RN-046 2RN-047 2RN-048 2RN-049 Report No.
UT-11-1066 UT-11-1067 UT-11-1056 UT-11-1075 UT-11-1076 UT-11-1073 UT-11-1072 UT-11-1062 UT-11-1068 UT-11-1054 UT-11-1055 UT-11-1032 UT-11-1069 UT-11-1070 UT-11-1053 UT-11-1074 UT-11-1071 UT-11-1027 UT-11-1077 UT-11-1010 UT-11-1022 UT-11-1021 UT-11-1008 UT-11-1037 UT-11-1018 UT-11-1023 UT-11-1041 UT-11-1042 UT-11-1020 UT-11-1061 UT-11-1045 UT-11-1038 UT-11-1043 UT-11-1019 UT-11-1011 Lowest 0.517" 0.506" 0.526" OA95" OA60" 0.501" OA99" OA87" 0.361" OA11 "
OA06" 0.380" 0.387" 0.375" OA02" 0.383" 0.387" 0.390" 0.383" 0.384" OA14" 0.393" 0.393" 0.394" OA04" 0.398" 0.363" 0.369" 0.387" 0.387" 0.360" 0.394" 0.394" 0.390" 0.396" FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, OH 44308 Beaver Valley Power Station Unit 2, Route 168, Shippingport, PA 15077 Commerical Service Date: 11/17/1987 Highest 0.534" 0.515" 0.534" 0.506" 0.506" 0.572" 0.508" 0.500" 0.374" OA18" OA14" OA02" 0.397" OA06" OA17" 0.396" 0.394" OA14" OAOT' OA12" OA20" OA04" OA08" OA01" OA10" OA15" 0.378" 0.384" OA04" 0.394" 0.384" OA01" OA08" OA15" OA09" General 0.526" 0.506" 0.530" OA98" 0.500" 0.506" 0.501" OA96" 0.367" OA14" OA10" 0.397" 0.391" 0.392" OA08" 0.389" 0.390" OA08" 0.399" OAOO" OA16" 0.396" OAOO" OA01" OA06" OA10" 0.374" 0.374" OA04" OAOO" 0.372" 0.398" OAOO" OA10" OAOO"
APPENDIX I FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, OH 44308 2R15 COMPELETED RANDOM EXAMINATIONS Beaver Valley Power Station Unit 2, Route 168, Shippingport, PA 15077 Commerical Service Date: 11/17/1987 Component 10 Report No.
Lowest Highest General 2RN-050 UT-11-1012 0.402" 0.417" 0.402" 2RN-051 UT-11-1007 0.394" 0.412" 0.399" 2RN-052 UT-11-1044 0.360" 0.384" 0.375" 2RN-053 UT-11-1030 0.417" 0.432" 0.427" 2RN-054 UT-11-1013 0.400" 0.406" 0.400" 2RN-055 UT-11-1039 0.401" 0.436" 0.411" 2RN-056 UT-11-1040 0.391" 0.412" 0.401" 2RN-057 UT-11-1026 0.380" 0.401" 0.390" 2RN-058 UT-11-1033 0.406" 0.418" 0.410" 2RN-059 UT-11-1015 0.398" 0.406" 0.400" 2RN-060 UT-11-1051 0.389" 0.401" 0.393" 2RN-061 UT-11-1050 0.388" 0.405" 0.400" 2RN-062 UT-11-1063 0.394" 0.408" 0.400" 2RN-063*
UT-11-10041 UT-11-086 0.310" 0.393" 0.381" 2RN-064 UT-11-1005 0.378" 0.404" 0.383" 2RN-065 UT-11-1006 0.388" 0.410" 0.395" 2RN-066 UT-11-1014 0.398" 0.410" 0.400" 2RN-067 UT-11-1046 0.397" 0.407" 0.402" 2RN-068 UT-11-1052 0.397" 0.412" 0.404" 2RN-069 UT-11-1048 0.397" 0.402" 0.400" 2RN-070 UT-11-1047 0.407" 0.414" 0.410" 2RN-071 UT-11-1049 0.380" 0.412" 0.405" 2RN-072 UT-11-1031 0.388" 0.411 "
0.400" 2RN-073 UT-11-1060 0.387" 0.396" 0.392" 2RN-074 UT-11-1034 0.393" 0.402" 0.402" 2RN-075 UT-11-1064 0.404" 0.412" 0.407"
- Refer to the Examination Summary of Subsequent Random Examination Evaluations for discussion of expanded examination area extending beyond Location 2RN-063.
APPENDIX II COMPELETED 2R15 NON-RANDOM EXAMINATIONS Component 10 Report No.
Lowest 2NR-01 UT-11-1016 OA04" 2NR-02 UT-11-1058 OA15" 2NR-03 UT-11-1059 OAOO" 2NR-04 UT-11-1024 OAOO" 2NR-05 UT-11-1001 0.384" 2NR-06 UT-11-1002 0.379" 2NR-07 UT-11-1003 0.379" 2NR-08 UT-11-1025 OA18" FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, OH 44308 Beaver Valley Power Station Unit 2, Route 168, Shippingport, PA 15077 Commerical Service Date: 11/17/1987 Highest General Type OA21" OA09" Irregular Contour OA30" OA26" Paint Repair OA32" OA26" Paint Repair OA28" OA09" Paint Repair 0.399" 0.385" Non-Coated Area OA06" 0.389" Non-Coated Area OA02" 0.393" Non-Coated Area OA37" OA24" Non-Coated Area