L-11-181, Containment Liner Random and Non-Random Examinations Report

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 Beaver Valley Power Station P.O. Box 4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077 Paul A. Harden 724-682-5234 Site Vice President Fax: 724-643-8069 June 27, 2011 L-11-181 ATIN: 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 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 VALLEY POWER STATION UNIT 2 2R15 Containment Liner Random and Non-Random Examinations Report ;".

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2R15 CONTAINMENT LINER RANDOM AND NON-RANDOM EXAMINATIONS REPORT 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-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. FENOC 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.

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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-015 UT-11-1066 0.517" 0.534" 0.526" 2RN-016 UT-11-1067 0.506" 0.515" 0.506" 2RN-017 UT-11-1056 0.526" 0.534" 0.530" 2RN-018 UT-11-1075 0.495" 0.506" 0.498" 2RN-019 UT-11-1076 0.460" 0.506" 0.500" 2RN-020 UT-11-1073 0.501" 0.572" 0.506" 2RN-021 UT-11-1072 0.499" 0.508" 0.501" 2RN-022 UT-11-1062 0.487" 0.500" 0.496" 2RN-023 UT-11-1068 0.361" 0.374" 0.367" 2RN-024 UT-11-1054 0.411" 0.418" 0.414" 2RN-025 UT-11-1055 0.406" 0.414" 0.410" 2RN-026 UT-11-1032 0.380" 0.402" 0.397" 2RN-027 UT-11-1069 0.387" 0.397" 0.391" 2RN-028 UT-11-1070 0.375" 0.406" 0.392" 2RN-029 UT-11-1053 0.402" 0.417" 0.408" 2RN-030 UT-11-1074 0.383" 0.396" 0.389" 2RN-031 UT-11-1071 0.387" 0.394" 0.390" 2RN-032 UT-11-1027 0.390" 0.414" 0.408" 2RN-033 UT-11-1077 0.383" 0.407" 0.399" 2RN-034 UT-11-1010 0.384" 0.412" 0.400" 2RN-035 UT-11-1022 0.414" 0.420" 0.416" 2RN-036 UT-11-1021 0.393" 0.404" 0.396" 2RN-037 UT-11-1008 0.393" 0.408" 0.400" 2RN-038 UT-11-1037 0.394" 0.401" 0.401" 2RN-039 UT-11-1018 0.337" 0.410" 0.406" 2RN-040 UT-11-1023 0.398" 0.415" 0.410" 2RN-041 UT-11-1041 0.363" 0.378" 0.374" 2RN-042 UT-11-1042 0.369" 0.384" 0.374" 2RN-043 UT-11-1020 0.387" 0.404" 0.404" 2RN-044 UT-11-1061 0.387" 0.394" 0.400" 2RN-045 UT-11-1045 0.360" 0.384" 0.372" 2RN-046 UT-11-1038 0.394" 0.401" 0.398" 2RN-047 UT-11-1043 0.394" 0.408" 0.400" 2RN-048 UT-11-1019 0.390" 0.415" 0.410" 2RN-049 UT-11-1011 0.396" 0.409" 0.400"

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" 0.404" 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" FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, OH 44308 COMPELETED 2R15 NON-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 Type 2NR-01 UT-11-1016 0.404" 0.421" 0.409" Irregular Contour 2NR-02 UT-11-1058 0.415" 0.430" 0.426" Paint Repair 2NR-03 UT-11-1059 0.400" 0.432" 0.426" Paint Repair 2NR-04 UT-11-1024 0.400" 0.428" 0.409" Paint Repair 2NR-05 UT-11-1001 0.384" 0.399" 0.385" Non-Coated Area 2NR-06 UT-11-1002 0.379" 0.406" 0.389" Non-Coated Area 2NR-07 UT-11-1003 0.379" 0.402" 0.393" Non-Coated Area 2NR-08 UT-11-1025 0.418" 0.437" 0.424" Non-Coated Area