L-11-181, Containment Liner Random and Non-Random Examinations Report
| ML111790129 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/27/2011 |
| From: | Harden P FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-11-181 | |
| Download: ML111790129 (9) | |
Text
FENOC FirstEnergy Nuclear Operating Company Paul A. Harden Site Vice President June 27, 2011 L-11-181 A TIN: 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 In accordance with license renewal commitment 35 listed in Beaver Valley Power Station, Unit No.2, Updated Final Safety Analysis Report, Table 19-1, enclosed is the Containment Liner Random and Non-Random Examinations Report for the Beaver Valley Power Station, Unit No.2 spring 2011 refueling outage (2R15).
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) 761-6071.
Enclosure:
2R15 Containment Liner Random and Non-Random Examinations Report cc:
NRC Region I Administrator NRC Resident Inspector NRR Project Manager Director BRP/DEP Site BRP/DEP Representative
BEAVER V ALLEY POWER STATION UNIT 2 2R15 Containment Liner Random and Non-Random Examinations Report ;".
Issue date:
l., l;;; \\ I, \\
Prepared bY~
I/ozA.J \\-\\<c"-wr c&L."
ReviewedbY:~~ ~-r ~~v.e.r1V\\
Supervis~rograms Approved by: __ D_rC_,_flee_-o./_l-?-...::.---------
Manager, Technical Services Engineering Date: to I ~\\ \\\\
Date:
6- '=5 ~ \\ ~
Date:
6"5-11
Cover Page Table of Contents 2R15 CONTAINMENT LINER RANDOM AND NON-RANDOM EXAMINATIONS REPORT TABLE OF CONTENTS Examination Summary References Appendix I - Summary of Random Exams Appendix II - Summary of Non-Random Exams Page Number 1
2 3
5 2 pages 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-2license 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 thiclmess) 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 oflower than expected thiclmess and is addressed below.
The statistical screening criterion for the examinations had been established as ninety percent of the nominal wall thiclmess (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 oflocation 2RN-063 identified an indication on the inaccessible side of the liner, having a general thiclmess below the statistical screening criterion. The lowest thiclmess 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 thiclmess than the surrounding area. The general thiclmess of this 2 inch by 10 inch area was between 0.300 inch and 0.400 inch. The lowest thiclmess observed within the extended area was 0.267 inch at a localized point.
The minimum design thiclmess 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 these dimensions, the minimum required thiclmess is 0.032 inch.
The apparent cause of the thinner liner thiclmess 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 thiclmess (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. FEN OC Letter L-09-205, "Supplemental Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application (TAC 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 (TAC 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 (TAC 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" 0.495" 0.460" 0.501" 0.499" 0.487" 0.361" 0.411" 0.406" 0.380" 0.387" 0.375" 0.402" 0.383" 0.387" 0.390" 0.383" 0.384" 0.414" 0.393" 0.393" 0.394" 0.337" 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" 0.418" 0.414" 0.402" 0.397" 0.406" 0.417" 0.396" 0.394" 0.414" 0.407" 0.412" 0.420" 0.404" 0.408" 0.401" 0.410" 0.415" 0.378" 0.384" 0.404" 0.394" 0.384" 0.401" 0.408" 0.415" 0.409" General 0.526" 0.506" 0.530" 0.498" 0.500" 0.506" 0.501" 0.496" 0.367" 0.414" 0.410" 0.397" 0.391" 0.392" 0.408" 0.389" 0.390" 0.408" 0.399" 0.400" 0.416" 0.396" 0.400" 0.401" 0.406" 0.410" 0.374" 0.374" 0.404" 0.400" 0.372" 0.398" 0.400" 0.410" 0.400"
APPENDIX I 2R15 COMPELETED RANDOM EXAMINATIONS Component 10 2RN-050 2RN-051 2RN-052 2RN-053 2RN-054 2RN-055 2RN-056 2RN-057 2RN-058 2RN-059 2RN-060 2RN-061 2RN-062 2RN-063*
2RN-064 2RN-065 2RN-066 2RN-067 2RN-068 2RN-069 2RN-070 2RN-071 2RN-072 2RN-073 2RN-074 2RN-075 Report No.
UT-11-1012 UT-11-1007 UT-11-1044 UT-11-1030 UT-11-1013 UT-11-1039 UT-11-1040 UT-11-1026 UT-11-1033 UT-11-1015 UT-11-1051 UT-11-1050 UT-11-1063 UT-11-10041 UT-11-086 UT-11-1005 UT-11-1006 UT-11-1014 UT-11-1046 UT-11-1052 UT-11-1048 UT-11-1047 UT-11-1049 UT-11-1031 UT-11-1060 UT-11-1034 UT-11-1064 Lowest 0.402" 0.394" 0.360" 0.417" 0.400" 0.401" 0.391" 0.380" 0.406" 0.398" 0.389" 0.388" 0.394" 0.310" 0.378" 0.388" 0.398" 0.397" 0.397" 0.397" 0.407" 0.380" 0.388" 0.387" 0.393" 0.404" 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 0.417" 0.412" 0.384" 0.432" 0.406" 0.436" 0.412" 0.401" 0.418" 0.406" 0.401" 0.405" 0.408" 0.393" 0.404" 0.410" 0.410" 0.407" 0.412" 0.402" 0.414" 0.412" 0.411 "
0.396" 0.404" 0.412" General 0.402" 0.399" 0.375" 0.427" 0.400" 0.411" 0.401" 0.390" 0.410" 0.400" 0.393" 0.400" 0.400" 0.381" 0.383" 0.395" 0.400" 0.402" 0.404" 0.400" 0.410" 0.405" 0.400" 0.392" 0.402" 0.407"
- Refer to the Examination Summary of Subsequent Random Examination Evaluations for discussion of expanded examination area extending beyond Location 2RN-063.
APPENDIX" COMPELETED 2R15 NON-RANDOM EXAMINATIONS Component 10 Report No.
Lowest 2NR-01 UT-11-1016 0.404" 2NR-02 UT-11-1058 0.415" 2NR-03 UT-11-1059 0.400" 2NR-04 UT-11-1024 0.400" 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 0.418" 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 0.421" 0.409" Irregular Contour 0.430" 0.426" Paint Repair 0.432" 0.426" Paint Repair 0.428" 0.409" Paint Repair 0.399" 0.385" Non-Coated Area 0.406" 0.389" Non-Coated Area 0.402" 0.393" Non-Coated Area 0.437" 0.424" Non-Coated Area