NRC 2019-0040, Owner'S Activity Report: 48th Year Iwl for Class CC Examinations
| ML19352F059 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/18/2019 |
| From: | Schultz E Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2019-0040 | |
| Download: ML19352F059 (10) | |
Text
NEXTera ENERGY.
POINT BEACH December 18, 2019 NRC 2019-0040 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units1 and 2 Docket 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Owner's Activity Report - 48 1h Year IWL for Class CC Examinations NextEra Energy Point Beach , LLC (NextEra) is submitting the 48TH year IWL Owner's Activity Report for Class CC examinations. The enclosed report is submitted pursuant to the requirements of Subarticle IWA-6240 of Section XI of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code and ASME Code Case N-532-5.
The Enclosure to this letter contains the summary report, Form OAR-1, "Owner's Activity Report" for class CC examinations. The report is for the third ten-year interval for CC examinations at Point Beach Nuclear Plant (PBNP) Units 1 and 2.
Sincerely, Eric Schultz Licensing Manager NextEra Energy Point Beach, LLC Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW Kim Schmitt, DSPS Boilers, State of Wisconsin NextEra Energy Point Beach, LLC 6610 Nuclear Road, Two Rivers, WI 54241
ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 FORM OAR-1, OWNER'S ACTIVITY REPORT 48TH YEAR IWL FOR CLASS CC EXAMINATONS 8 Pages Follow
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number: 481h year IWL for Class CC Examinations Plant: NextEra Energy Point Beach Nuclear Power Plant Unit 1 661 O Nuclear Road Twin Rivers, Wisconsin 54241 Commercial Service Date: December 1970 Refueling Outage No.: 481h year IWL for Class CC Examinations Current Inspection Interval: IWL Third Interval Edition and Addenda of Section XI applicable to the inspection plans: 2007 Edition through 2008 Addenda.
Date and Revision of inspection plans: 3/29/18 3rd lnterval-IWL-PB-1/2-Program Plan Rev. o Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan: Same Code Cases Used: N-532-5 CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of 481h ~ear I L examin ion nform to the requirements of Section XI.
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by Hartford Steam Boiler Inspection and Insurance Company of Hartford Connecticut have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspe<riion.
Date vnt
--1~~~~-~=*~~-W<<=~-'______ Commission_ _ _ __..N~B~1=26~9=2~A...._.N_.I,____
lflSPector's Signature
[J- J..- / 7 National Board Number and Endorsements I of4
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE IWL Third Interval Examination Category and Item Number Item Description Evaluation Descriotion In accordance with 10 CFR 50.55a(b)(2)(v1ii)(D),
any tendon grease leakage detected during general visual examination of the containment surface is to be reported. Identified grease leakage is considered relatively minor, resulting in staining/discoloration of surrounding tendon can and/or concrete. The quantity of grease leakage is small relative to the volumes of the tendons as was confirmed by the grease volumes captured and/or replaced during can removal and/or tendon lift off, which consistently indicate no excessive grease input to tendons, and thus no loss of L-A/ L1.11 Multiple Tendons grease.
Also the grease has consistently been noted to have proper coloration and no indications of water, thus also indicating no significant loss of grease/contamination which would be likely if significant grease was lost.
Tendons which have noted minor leakage are acceptable as-is and no additional action is required.
(Reference AR 02329073-02)
Concrete distress in the area of the tendon anchorages noted included minor cracks (<0.010" in width) which were not recordable, however other relatively minor mechanisms such as voids or spalls were noted. Based on review of the indications these items were likely present from original construction as minor areas of poorly consolidated concrete and spalls due to loading during strand tensioning and minor inconsistencies in the concrete.
L-A IL1.11 Containment Concrete The items are not exposed to the elements, as the Unit 1 containment is located within a steel-framed facade building, therefore there is no credible driving force to cause these areas to "grow prior to the next scheduled examination.
There is no impact to the structure and no additional actions required.
(Reference AR 02329073-02) 2of4
FORM OAR-1 OWNER'S ACTIVITY REPORT Split buttonheads were encountered and documented per the field reports. Based on review of previous years the split buttonheads were previously noted (in the common review tendons) and did not change. Splits were noted during original construction and during the U2 03-225 tendon replacement. Follow-up indicated that the frequency of button head splitting was related to the hardness of the tendon strand steel. During construction, typical splits of less than 0.060" L-B I L2.30 Multiple Tendons were considered acceptable. The location of the split is also significant, with radial splits are less likely to impact the shearing of a button than those that are parallel to button shear surface (Block failure mode).
Based on review of the splits noted above the splits are structurally acceptable. No additional actions, supplemental, or follow-up examinations are required.
(Reference AR 02329073-02)
Missing buttonheads are typically from original construction. When tendons are detensioned they are carefully inspected to ensure there are no changes in button heading (e.g., All strands flush at start return to flush, etc.).
L-B I L2.30 Multiple Tendons There were no strand breakages noted during tendon lift-off, etc.
No additional actions, supplemental, or follow-up examinations are required.
<Reference AR 02329073-02) 3 of4
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE IWL Third Interval Description Date Repair/Replacement Code Class Item Description of Work Completed Plan Number None None None None None 4of4
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number: 481h year IWL for Class CC Examinations Plant: NextEra Energy Point Beach Nuclear Power Plant Unit 2 6610 Nuclear Road Twin Rivers, Wisconsin 54241 Commercial Service Date: October 1972 Refueling Outage No.: N/A Current Inspection Interval: IWL Third Interval Edition and Addenda of Section XI applicable to the inspection plans: 2007 Edition through 2008 Addenda.
Date and Revision of inspection plans: 3/29/18 3rd lnterval-IWL-PB-1/2-Program Plan Rev. O Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan: Same Code Cases Used: N-532-5, CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of 481h year IWL amin tion onform to the requirements of Section XI.
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by Hartford Steam Boiler Inspection and Insurance Company of Hartford Connecticut have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspectiop.
---~"'""""~'--'-U-=--"'-"-"""'"'""'""""~""t""£..-""'-'-------commission: ------~N~B~12~5~9~2~A~N~1_ __
{/'ff.TriSPeCtOr'SSi9nature National Board Number and Endorsements Date -=----l d-:~-;)__~-/--t-1_
1of4
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE IWL Third Interval Examination Category and Item Number Item Description Evaluation Description In accordance with 10 CFR 50.55a(b)(2)(viii)(D),
any tendon grease leakage detected during general visual examination of the containment surface is to be reported. Identified grease leakage is considered relatively minor, resulting in staining/discoloration of surrounding tendon can and/or concrete. The quantity of grease leakage is small relative to the volumes of the tendons as was confirmed by the grease volumes captured and/or replaced during can removal and/or tendon lift off, which consistently indicate no excessive grease input to tendons, and thus no loss of L-A IL 1.11 Multiple Tendons grease.
Also the grease has consistently been noted to have proper coloration and no indications of water, thus also indicating no significant loss of grease/contamination which would be likely if significant grease was lost.
Tendons which have noted minor leakage are acceptable as-is and no additional action is required.
(Reference AR 02329073-02)
Concrete distress in the area of the tendon anchorages noted included minor cracks (<0.01 O" in width) which were not recordable, however other relatively minor mechanisms such as voids or spalls were noted. Based on review of the indications these items were likely present from original construction as minor areas of poorly consolidated concrete and spalls due to loading during strand tensioning and minor inconsistencies in the concrete.
L-A/ L1.11 Containment Concrete The items are not exposed to the elements, as the Unit 2 containment is located within a steel-framed facade building, therefore there is no credible driving force to cause these areas to "grow" prior to the next scheduled examination.
There is no impact to the structure and no additional actions required.
(Reference AR 02329073-02) 2 of4
FORM OAR-1 OWNER'S ACTIVITY REPORT Split buttonheads were encountered and documented per the field reports. Based on review of previous years the split buttonheads were previously noted (in the common review tendons) and did not change. Splits were noted during original construction and during the U2 03-225 tendon replacement. Follow-up indicated that the frequency of button head splitting was related to the hardness of the tendon strand steel. During construction, typical splits of less than 0.060" L-B I L2.30 Multiple Tendons were considered acceptable. The location of the split is also significant, with radial splits are less likely to impact the shearing of a button than those that are parallel to button shear surface (Block failure mode).
Based on review of the splits noted above the splits are structurally acceptable. No additional actions, supplemental, or follow-up examinations are required.
(Reference AR 02329073-02)
Missing buttonheads are typically from original construction. When tendons are detensioned they are carefully inspected to ensure there are no changes in button heading (e.g., All strands flush at start return to flush, etc.).
L-B I L2.30 Multiple Tendons There were no strand breakages noted during tendon lift-off, etc.
No additional actions, supplemental, or follow-up examinations are required.
(Reference AR 02329073-02) 3 of4
FORM OAR-1 OWNER'S ACTIVITY REPORT TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE IWL Third Interval Description Date Repair/Replacement Code Class Item Description of Work Completed Plan Number None None None None None 4 of4