ML110470404

Containment Liner Random and Non-Random Examinations Report

ML110470404
Person / Time
Site:	Beaver Valley
Issue date:	02/14/2011
From:	Harden P A FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-11-001
Download: ML110470404 (8)

Text

FENOC FirstEnergy Nuclear Operating Company Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 Paul A. Harden Site Vide President 724-682-5234 Fax: 724-643-8069 February 14, 2011 L-1 1-001 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Containment Liner Random and Non-Random Examinations Report In accordance with an updated commitment described by the, FirstEnergy Nuclear Operating Company (FENOC) in correspondence dated September 14, 2009 and confirmed by the Nuclear Regulatory Commission in NUREG-1929, Appendix A, enclosed is the Containment Liner Random and Non-Random Examinations Report for the Beaver Valley Power Station, Unit No. 1 fall 2010 refueling outage.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.Paul A. Harden

Enclosure:

1 R20 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 MVL~

BEAVER VALLEY POWER STATION UNIT 1 1R20 Containment Liner Random and Non-Random Examinations Report Issue date: Z- kcý --.oý\Prepared by: Reviewed by: FENOC UT4Level III Date: z-,o --Lo\\Date: d- -t -., Date: a -I/ -0 oi (Reviewed by: Approved by: Manager, Technical Services Engineering Date: 2 -/P -/(

1R20 CONTAINMENT LINER RANDOM AND NON-RANDOM EXAMINATIONS REPORT TABLE OF CONTENTS Item Table of Contents Examination Summary Appendix I -Summary of Random Exams Appendix II -Summary of Non-Random Exams Page Number 1 2 2 pages 1 page EXAMINATION

SUMMARY

Supplemental volumetric examinations were performed on the Beaver Valley Power Station, Unit No. 1 (BVPS-1) containment liner prior to and during the twentieth refueling outage fall 2010 (1R20) to satisfy BVPS-1 license commitments 32 (random) and 33 (non-random). A summary of the commitments are as follows: License Commitment 32: Supplemental volumetric examinations will be performed on the BVPS-1 containment liner prior to the period of extended operation.

A minimum of 75 randomly selected (as described in First Energy Nuclear Operating Company Letter L-09-205) 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- 1 sample lot of a minimum of 75 random ultrasonic examinations will be completed in the next three refueling outages, beginningwith the BVPS-1 refueling outage in 2010. The entire sample plan (including additional examinations, if required)will be completed by January 29, 2016.License Commitment 33: Supplemental volumetric examinations will be performed on the BVPS-1 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 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.

2 Examinations will commence on-line, prior to the beginning of the BVPS-1 refueling outage in 2010. Non-Random examinations will be completed by December 31, 2010.Summary of Random Scope Examinations:

Thirty-eight of the 75 randomly selected examinations were performed during the BVPS- 1 1R20 refueling outage.Acceptance criterion for the examinations had been established as 90 percent (less than 10 percent degradation) of the nominal wall thickness (that is, 0.337 inches for the shell and 0.450 inches for the dome). Appendix I contains the 1R20 random examinations results.All 38 locations examined during 1R20 were completed with no evidence of loss of material.Summary of Non-Random Scope Examinations:

Eight non-random locations were performed during the BVPS-1 1R20 refueling outage.Two non-random examinations were completed prior to the outage, in May 2010. The locations selected included irregular contours of the liner, repainted areas of the liner, areas adjacent to the discovered through-wall hole, the below-grade area between elevations 725 feet and 735 feet, and the area below the 2006 steam generator replacement opening. Acceptance criterion for the examinations had been established as 90 percent of the nominal wall thickness (0.337 inches). Appendix II contains the 1R20 non-random examination results. All 10 locations examined online and during 1R20 were completed with no evidence of loss of material.3 APPENDIX I 1R20 COMPELETED RANDOM EXAMS FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, OH 44308 Beaver Valley Power Station Unit 1, Route 168, Shippingport, PA 15077 Commerical Service Date: 9/30/1976 Comoonent ID Report No.Lowest Hicihest General I RN-020 1 RN-025 1 RN-026 1 RN-029 1 RN-030 1 RN-031 1 RN-034 1 RN-036 1 RN-037 1 RN-039 1 RN-040 1 RN-041 1 RN-042 1 RN-047 1 RN-048 1 RN-050 1 RN-052 1RN-053 1RN-054 1RN-055 1 RN-056 1RN-057 1 RN-058 1 RN-059 1 RN-060 1 RN-062 1RN-063 1 RN-064 1 RN-065 1 RN-067 1RN-068 1RN-069 1 RN-070 1 RN-071 1 RN-072 UT-10-1063 UT-10-1067 UT-1 0-1058 UT-1 0-1047 UT-10-1065 UT-1 0-1060 UT-10-1069 UT-10-1059 UT-10-1070 UT-1 0-1072 UT-10-1052 UT-10-1053 UT-1 0-1032 UT-10-1064 UT-1 0-1066 UT-10-1015 UT-10-1012 UT-1 0-1031 UT-1 0-1033 UT-10-1029 UT-10-1027 UT-10-1016 UT-1 0-1030 UT-10-1028 UT-10-1017 UT-10-1054 UT-1 0-1026 UT-10-1025 UT-1 0-1008 UT-1 0-1024 UT-10-1055 UT-10-1009 UT-10-1011 UT-10-1013 UT-10-1014 0.516 0.516 0.527 0.371 0.403 0.399 0.382 0.389 0.382 0.402 0.405 0.400 0.401 0.403 0.412 0.379 0.392 0.403 0.396 0.386 0.403 0.406 0.376 0.399 0.357 0.404 0.401 0.394 0.396 0.410 0.387 0.362 0.416 0.401 0.387 0.555 0.551 0.558 0.405 0.420 0.437 0.438 0.412 0.419 0.425 0.428 0.421 0.425 0.420 0.422 0.450 0.420 0.415 0.413 0.398 0.415 0.445 0.394 0.419 0.415 0.425 0.414 0.425 0.424 0.425 0.407 0.435 0.444 0.424 0.402 0.532 0.532 0.539 0.390 0.412 0.409 0.402 0.401 0.399 0.411 0.416 0.410 0.413 0.412 0.416 0.410 0.400 0.409 0.405 0.392 0.409 0.415 0.385 0.410 0.390 0.414 0.407 0.412 0.412 0.417 0.397 0.405 0.432 0.410 0.394 APPENDIX I 1R20 COMPELETED RANDOM EXAMS Component ID 1 RN-073 1RN-074 1 RN-075 Report No.UT-10-1018 UT-10-1019 UT-10-1010 Lowest 0.363 0.396 0.378 Highest 0.420 0.460 0.460 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, OH 44308 Beaver Valley Power Station Unit 1, Route 168, Shippingport, PA 15077 Commerical Service Date: 9/30/1976 General 0.390 0.380 0.425 d APPENDIX II COMPELETED NON-RANDOM EXAMS FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, OH 44308 Beaver Valley Power Station Unit 1, Route 168, Shippingport, PA 15077 Commerical Service Date: 9/30/1976 Component ID 1NR-01 1NR-02 1NR-03 1NR-04 1NR-05 1N R-06 1NR-07 1NR-08 1NR-09 1NR-10 Report No.UT-10-1020 UT-10-1021 UT-10-1002 UT-10-1001 UT-10-1022 UT-10-1048 UT- 10-1056 UT-10-1023 UT-10-1057 UT-10-1051 Lowest 0.383 0.391 0.421 0.406 1.020 0.391 0.402 0.413 0.415 0.404 Highest 0.420 0.430 0.455 0.435 1.110 0.420 0.411 0.445 0.429 0.433 General 0.400 0.410 0.435 0.412 1.075 0.405 0.405 0.425 0.421 0.421 Type Irregular contour Irregular contour Repainted Repainted Repainted Near thru-wall Near thru-wall 725-735 coating Below S/G opening Below S/G opening