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| Post Office Box 2000, Decatur, Alabama 35609-2000 | | Post Office Box 2000, Decatur, Alabama 35609-2000 |
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| June 23, 2024 10 CFR 50.55a | | June 23, 2024 10 CFR 50.55a |
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| ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 | | ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 |
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| Browns Ferry Nuclear Plant, Unit 3 Renewed Facility Operating License No. DPR-68 NRC Docket No. 50-296 | | Browns Ferry Nuclear Plant, Unit 3 Renewed Facility Operating License No. DPR-68 NRC Docket No. 50-296 |
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| American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear Plant, Unit 3, Cycle 21 Operation | | American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear Plant, Unit 3, Cycle 21 Operation |
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| cc (Enclosure): NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant Enclosure | | cc (Enclosure): NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant Enclosure |
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| Tennessee Valley Authority | | Tennessee Valley Authority |
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| See Enclosed | | See Enclosed |
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| FORM OAR-1 OWNER'S ACTIVITY REPORT | | FORM OAR-1 OWNER'S ACTIVITY REPORT |
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| Report Number _,B""F'--'N'--'----'U"--'3"-'R--"2=-1.,__ ___________________________________ _ | | Report Number _,B""F'--'N'--'----'U"--'3"-'R--"2=-1.,__ ___________________________________ _ |
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| Plant Browns Ferry Nuclear Plant P 0. Box 2000 Decatur . AL 35609 | | Plant Browns Ferry Nuclear Plant P 0. Box 2000 Decatur. AL 35609 |
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| Unit No . --~3~- date March 1 1977 Refueling Outage no . Refueling Outage 21 | | Unit No. --~3~- date March 1 1977 Refueling Outage no. Refueling Outage 21 |
| {if applicable) Commercial service | | {if applicable) Commercial service |
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| Current Inspe c tion Interval FO L![(h Ten Y ear lnspectio~n~ ln=t~e~rv~a~I __________ _______________ _ | | Current Inspe c tion Interval FO L![(h Ten Y ear lnspectio~n~ ln=t~e~rv~a~I __________ _______________ _ |
| (1st, 2nd, 3rd, other) | | (1st, 2nd, 3rd, other) |
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| Current Inspection Period ~T~h=ir~d~P_e=r~io~d~--------------------------------- | | Current Inspection Period ~T~h=ir~d~P_e=r~io~d~--------------------------------- |
| (1st. 2nd. 3rd) | | (1st. 2nd. 3rd) |
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| 2007 Edition , 2008 Addenda ( ISi) | | 2007 Edition, 2008 Addenda ( ISi) |
| Edition and Addenda of Section X I applicable to the inspection plans ~2=0-'-1=3_,E=-d=i=ti=o~n__,_(=C~IS"'-'-'1)----------------- ~ | | Edition and Addenda of Section X I applicable to the inspection plans ~2=0-'-1=3_,E=-d=i=ti=o~n__,_(=C~IS"'-'-'1)----------------- ~ |
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| 0 -T PP -E NG -376. Re vision 0006, 02/07/2024 0-Tl-364 , Revision 0026, 11 /28/2023 Date and Revision of inspection plan 0-TPP-ENG-467 Revision 0002 02/05/2024 | | 0 -T PP -E NG -376. Re vision 0006, 02/07/2024 0-Tl-364, Revision 0026, 11 /28/2023 Date and Revision of inspection plan 0-TPP-ENG-467 Revision 0002 02/05/2024 |
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| Edition and Addenda of Section X I applicable to repairs and replacemen ts, if different than the inspection plan ~N~/A~-- | | Edition and Addenda of Section X I applicable to repairs and replacemen ts, if different than the inspection plan ~N~/A~-- |
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| Code Cases used for inspection and evaluation N-508 -4 N-532 -- 5 N -6 13-2 N-648- 1 N-702 and N- 7 16-1 N-747 N-864. | | Code Cases used for inspection and evaluation N-508 -4 N-532 -- 5 N -6 13-2 N-648-1 N-702 and N-7 16-1 N-747 N-864. |
| (if applicable , including cases modified by Case N-532 and later revisions) | | (if applicable, including cases modified by Case N-532 and later revisions) |
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| CERTIFICATE OF CONFORMANCE | | CERTIFICATE OF CONFORMANCE |
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| I certify tl1at (a) the statempn tq m a de in this report are corre ct; (b) the exam inations and tests meet the In spection Plan as required by the ASME' Code , Section XI; and (c) the repai,/replacement act ivities and evaluations supporting the comp letion of --~U~ 3~R~2~1 __ _ | | I certify tl1at (a) the statempn tq m a de in this report are corre ct; (b) the exam inations and tests meet the In spection Plan as required by the ASME' Code, Section XI; and (c) the repai,/replacement act ivities and evaluations supporting the comp letion of --~U~ 3~R~2~1 __ _ |
| conform to 11,e requireme *' -,ec tion XI. (refueling outage number) | | conform to 11,e requireme *' -,ec tion XI. (refueling outage number) |
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| Signed ______________________ Date _______________ _ | | Signed ______________________ Date _______________ _ |
| Owner or Owner s Designee , Title | | Owner or Owner s Designee, Title |
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| CERTIFICATE OF INSERVICE INSPECTION | | CERTIFICATE OF INSERVICE INSPECTION |
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| I, the undersigned, holding a valid commission issued by the Na tiona l Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and In surance Company of Hartford Connecticu t have inspected the items described in this Owner's Activity Report and state tha t, to the best of my knowledge and be lief, the Owner has performed all activities represented by this report in accordance w ith the requirements of Section XI. | | I, the undersigned, holding a valid commission issued by the Na tiona l Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and In surance Company of Hartford Connecticu t have inspected the items described in this Owner's Activity Report and state tha t, to the best of my knowledge and be lief, the Owner has performed all activities represented by this report in accordance w ith the requirements of Section XI. |
| By signing this certificate neither the In spector n or his emp loyer makes any war ranty, expressed or im plied , concerning the repair/replacement activities and evaluation described in this report. Furthermore, n e ither the Inspector nor his employer shall be liable in any manner for any persona l injury or property damage *r lo s of an r connected with this In spection. | | By signing this certificate neither the In spector n or his emp loyer makes any war ranty, expressed or im plied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, n e ither the Inspector nor his employer shall be liable in any manner for any persona l injury or property damage *r lo s of an r connected with this In spection. |
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| --;--f,-'-"---,.,-:-':-::&c~+/---:._,,...,.--=--+------ --'--""'Na'-ti-on-al~B.,_oa~,d=-N-u-'-m-be-r a-n~d ~En-do-rs_e_m-en-, --'-'--'---J/'---Comm issions N ;3 i '19 '7 1 -r , IV R..
| | --;--f,-'-"---,.,-:-':-::&c~+/---:._,,...,.--=--+------ --'--""'Na'-ti-on-al~B.,_oa~,d=-N-u-'-m-be-r a-n~d ~En-do-rs_e_m-en-, --'-'--'---J/'---Comm issions N ;3 i '19 '7 1 -r, IV R.. |
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| Date __ l;)'--lif----+,-"=--------/,/ lo/ 1 vt FORM OAR-1 OWNER'S ACTIVITY REPORT | | Date __ l;)'--lif----+,-"=--------/,/ lo/ 1 vt FORM OAR-1 OWNER'S ACTIVITY REPORT |
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| TABLES Report Number BFN U3R21 ------ - ----- -------------- --- - - | | TABLES Report Number BFN U3R21 ------ - ----- -------------- --- - - |
| PI ant Browns Ferry Unit No . 3 Commercial service date 03/01/1977 Refueling outage no . 21 - --- | | PI ant Browns Ferry Unit No. 3 Commercial service date 03/01/1977 Refueling outage no. 21 - --- |
| Current inspection interval 4th Current inspection period 3rd ----- ----- -- | | Current inspection interval 4th Current inspection period 3rd ----- ----- -- |
| TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATIONS FOR CONTINUED SERVICE Exam ination Category and Item Number Item Description Evaluation Description CR 1911989, NOi U3R21-001 | | TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATIONS FOR CONTINUED SERVICE Exam ination Category and Item Number Item Description Evaluation Description CR 1911989, NOi U3R21-001 |
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| During VT-3 examination of Mechanical Snubber Support, 3-47B400-75 , examiners identified the pin was displaced, not fully engaged with the suppo rt bracket, resulting in examination failure. | | During VT-3 examination of Mechanical Snubber Support, 3-47B400-75, examiners identified the pin was displaced, not fully engaged with the suppo rt bracket, resulting in examination failure. |
| Civil Engineering evaluated the condition and F-A / F1.10D Main Steam System Snubber, concluded that the snubber in the "as found " | | Civil Engineering evaluated the condition and F-A / F1.10D Main Steam System Snubber, concluded that the snubber in the "as found " |
| 3-4 7B40 0- 75 condition would still be able to perform its intended design function and sustain the imposed design seismic loads. The design loads would have been transferred from the main steam piping to the EL 584 ' floor steel features. The snubber pin was reinstalled and a new cotter pin was installed topside of the support bracket. The support was then re examined with no recordable indication. | | 3-4 7B40 0- 75 condition would still be able to perform its intended design function and sustain the imposed design seismic loads. The design loads would have been transferred from the main steam piping to the EL 584 ' floor steel features. The snubber pin was reinstalled and a new cotter pin was installed topside of the support bracket. The support was then re examined with no recordable indication. |
| CR 1914074, WO 124338851 , NOi U3R21-003 | | CR 1914074, WO 124338851, NOi U3R21-003 |
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| During Owner Elected VT-3 examination of 3-47B455-628 the variable spring support was observed at an as found setting of 1650 lbs. The High Pressure Coolant Injection affected support nominal range setting is 1663 - | | During Owner Elected VT-3 examination of 3-47B455-628 the variable spring support was observed at an as found setting of 1650 lbs. The High Pressure Coolant Injection affected support nominal range setting is 1663 - |
| F-A / F1 .20C System Support , 3-47B455 -628 1738 lbs. The as found setting was roughly 1 % | | F-A / F1.20C System Support, 3-47B455 -628 1738 lbs. The as found setting was roughly 1 % |
| outside of the acceptable nominal range, constituting a relevant condition as defined in IWF-3410(a)(4) , "Improper hot or cold settings of spring supports" . The spring can was reset to 1700 lbs. | | outside of the acceptable nominal range, constituting a relevant condition as defined in IWF-3410(a)(4), "Improper hot or cold settings of spring supports". The spring can was reset to 1700 lbs. |
| and an a s left examination was performed with no relevant indications identified. | | and an a s left examination was performed with no relevant indications identified. |
| FORM OAR-1 OWNER'S ACTIVITY REPORT | | FORM OAR-1 OWNER'S ACTIVITY REPORT |
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| TABLES Report Number BFN U3R21 ------------------------------- | | TABLES Report Number BFN U3R21 ------------------------------- |
| PI ant Browns Ferry Unit No . 3 Commercial service date 03/01/1977 Refueling outage no . 21 ---- | | PI ant Browns Ferry Unit No. 3 Commercial service date 03/01/1977 Refueling outage no. 21 ---- |
| Current inspection interval 4th ----- Current inspection period 3rd ------- | | Current inspection interval 4th ----- Current inspection period 3rd ------- |
| TABLE 2 AB STRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FO R CONTINUED SERVICE Code Item Description Description of Work Date Repair/Replacement Class Completed Plan Number During a pre-shutdown walk down a defect was revealed when a 1/2" drain pipe sheared at the heat affected zone at the Tee-to-Pipe interface due to cyclic fatigue cracking . (The valve at the end of the pipe was not supported and created a catalever at the pipe-to-tee joint.) | | TABLE 2 AB STRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FO R CONTINUED SERVICE Code Item Description Description of Work Date Repair/Replacement Class Completed Plan Number During a pre-shutdown walk down a defect was revealed when a 1/2" drain pipe sheared at the heat affected zone at the Tee-to-Pipe interface due to cyclic fatigue cracking. (The valve at the end of the pipe was not supported and created a catalever at the pipe-to-tee joint.) |
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| The defect was removed and 21 , | | The defect was removed and 21, |
| Replace reducing Pipe Engineering Change (BFN Tee upstream of valve 010 (AWA-TVA-2024-04 38)) t~ | | Replace reducing Pipe Engineering Change (BFN Tee upstream of valve 010 (AWA-TVA-2024-04 38)) t~ |
| 2 BFN-3-VTV-074-0683A was performed to replace a c- o- 03/25/2024 124312449 with a 90-degree elbow degree elbow joint removing the and reducing insert catalever design issue with the drain valve. | | 2 BFN-3-VTV-074-0683A was performed to replace a c-o- 03/25/2024 124312449 with a 90-degree elbow degree elbow joint removing the and reducing insert catalever design issue with the drain valve. |
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| The cause of the unacceptab ility is being documented in the BFN corrective action program CR 1911200 with an engineering evaluation shown in the Prompt Determination of Operability (PDQ) 1911200. An ECP was created to address the issue to prevent reoccurance . | | The cause of the unacceptab ility is being documented in the BFN corrective action program CR 1911200 with an engineering evaluation shown in the Prompt Determination of Operability (PDQ) 1911200. An ECP was created to address the issue to prevent reoccurance. |
| FORM OAR-1 OWNER'S ACTIVITY REPORT | | FORM OAR-1 OWNER'S ACTIVITY REPORT |
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| TABLES Report Number BFN U3R21 --------- - ---------- - ------ | | TABLES Report Number BFN U3R21 --------- - ---------- - ------ |
| PI ant Browns Ferry Unit No. 3 Commercial service date 03/01/1977 Refueling outage no . 21 ---- | | PI ant Browns Ferry Unit No. 3 Commercial service date 03/01/1977 Refueling outage no. 21 ---- |
| Current inspection interval 4th ---- Current inspection period 3rd ------ | | Current inspection interval 4th ---- Current inspection period 3rd ------ |
| REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)(A) | | REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)(A) |
| ASME Section XI, Subsection IWE Steel Containment Vessel Inspection program | | ASME Section XI, Subsection IWE Steel Containment Vessel Inspection program |
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| 10 CFR 50.55a(b )(2)(ix)(A) requires reporting of the degradation assessment for inaccessible areas when conditions are identified in accessible areas during the perform a nce of the ASME Section XI, Subsection IWE Steel Containment Vessel (SCV) | | 10 CFR 50.55a(b )(2)(ix)(A) requires reporting of the degradation assessment for inaccessible areas when conditions are identified in accessible areas during the perform a nce of the ASME Section XI, Subsection IWE Steel Containment Vessel (SCV) |
| Inspection Program that could indicate the presence of or result in degradation to such inaccessible areas. | | Inspection Program that could indicate the presence of or result in degradation to such inaccessible areas. |
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| During BFN U3R21, isolat ed locations of the Moisture Seal Barrier (MSB) of the SCV was identified to have disbonding conditions requiring excavations and examination of in acc e ssi le areas beneath the barrier. The inaccessible areas of the SCV Le neath the MSB we rP-. determined to be acceptable by General Visual examinat ion . Th e P. Xam ination irlGntifa:. d | | During BFN U3R21, isolat ed locations of the Moisture Seal Barrier (MSB) of the SCV was identified to have disbonding conditions requiring excavations and examination of in acc e ssi le areas beneath the barrier. The inaccessible areas of the SCV Le neath the MSB we rP-. determined to be acceptable by General Visual examinat ion. Th e P. Xam ination irlGntifa:. d |
| * 1:J evidence of complete separation from the drywell liner that wou; ~1 ailow moistu 1 *~: to enter the area below the seal. Conditions were corrected by clea n ing and replacing damaged areas of the MSB with no Repair/ Replacement Activity required.}} | | * 1:J evidence of complete separation from the drywell liner that wou; ~1 ailow moistu 1 *~: to enter the area below the seal. Conditions were corrected by clea n ing and replacing damaged areas of the MSB with no Repair/ Replacement Activity required.}} |
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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan CNL-23-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472023-07-0303 July 2023 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML23171A9132023-06-20020 June 2023 Amse, Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report ML23171A9572023-06-20020 June 2023 Replacement Steam Dryer Visual Inspection Results (U2R22) ML23025A0752023-01-25025 January 2023 American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report Cycle . ML23024A1632023-01-24024 January 2023 Replacement Steam Dryer Visual Inspection Results (U1R14) ML22182A1632022-07-0101 July 2022 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner'S Activity Report for Browns ML21202A2422021-07-21021 July 2021 American Society of Mechanical Engineers, Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner'S Activity Report for Browns Ferry Nucle ML21201A3112021-07-20020 July 2021 Replacement Steam Dryer Visual Inspection Results ML21036A1532021-02-0505 February 2021 Owner'S Activity Report for Cycle 13 Operation ML21032A1302021-02-0101 February 2021 Replacement Steam Dryer Visual Inspection Results (U1R13) ML20176A3652020-06-24024 June 2020 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner'S Activity Report for Browns Ferry Nucl CNL-20-019, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Request for Alternative 0-ISI-472020-02-28028 February 2020 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Request for Alternative 0-ISI-47 ML19190A0722019-07-0909 July 2019 American Society of Mechanical Engineers, Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner'S Activity Report for Browns Ferry Nucle ML19051A0182019-02-20020 February 2019 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report Cycle 12 Operation CNL-18-123, Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second Ten Year Interval Request for Relief 1-ISI-272018-12-27027 December 2018 Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second Ten Year Interval Request for Relief 1-ISI-27 ML18186A6042018-07-0505 July 2018 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Browns Ferry Nuclear Plant, Unit 3, Cycle 1 CNL-18-080, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-Year Interval Request for Relief for 1-ISI-28 and 1-ISI-292018-05-31031 May 2018 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-Year Interval Request for Relief for 1-ISI-28 and 1-ISI-29 ML17180A3862017-06-29029 June 2017 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Browns Ferry Nuclear Plant, Unit 2, Cycle 1 CNL-17-013, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 3 Third Ten Year Interval Request for Relief for 3-ISI-28 and 3-ISI-292017-01-31031 January 2017 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 3 Third Ten Year Interval Request for Relief for 3-ISI-28 and 3-ISI-29 ML16176A2842016-06-24024 June 2016 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 17 Operation ML15190A3302015-07-0909 July 2015 ASME Section XI, Lnservice Inspection, System Pressure Test, Containment Lnservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 18 Operation ML15028A4032015-01-27027 January 2015 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 10 Operation ML14260A3652014-09-12012 September 2014 3 - ASME, Code Section XI-Inservice Inspection Program for the Unit 1 Second Ten-Year Inspection Interval, Unit 2 Fourth Ten-Year Inspection Interval and Unit 3 Third Ten-Year Inspection Interval, Request for an Alternative. ML14169A4042014-06-16016 June 2014 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Browns Ferry Plant, Unit 3, Cycle 16 Operat ML14056A2682014-02-11011 February 2014 ASME, Section XI Code, Inservice Inspection Program for Unit I Second Ten-Year Inspection Interval, Unit 2 Fourth Ten-Year Inspection Interval, and Unit 3 Third Ten-Year Inspection Interval, Request for Relief ISI-44 ML13291A3842013-10-0202 October 2013 Inservice Testing Program for the Fourth Ten Year Interval ML13256A1012013-09-11011 September 2013 CFR 72.48 Changes, Tests, and Experiments, Biennial Summary Report Associated with the Independent Spent Fuel Storage Installation ML13253A1392013-08-0202 August 2013 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 17 Operation ML13119A3862013-04-29029 April 2013 Ti 182 RFI 2013003_AS Doc ML13067A4012013-03-0101 March 2013 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection and Repair and Replacement Programs - Owner'S Activity Report for Cycle 9 Operation ML12240A1052012-08-24024 August 2012 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 15 Operation ML12150A3672012-05-24024 May 2012 American Society of Mechanical Engineers, Section Xl Code, Inservice Inspection Program for the Unit 2 Third Ten-Year Inspection Interval, Request for Relief 2-ISI-28 ML11189A1122011-07-0606 July 2011 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 16 Operation ML1108300372011-03-21021 March 2011 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection Program, Third Ten-Year Inspection Interval, Request for Relief 3-ISI-26 ML1102603952011-01-21021 January 2011 American Society of Mechanical Engineers, Section XI Inservice Inspection Program for the Unit 3 Third Ten-Year Inspection Interval, Request for Relief 3-ISI-25 ML1018705992010-07-0101 July 2010 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section Xl, Inservice Inspection Program, Request to Use Subsequent Edition of ASME Section Xl Code for Repair and Replacement Activities ML1014700692010-05-24024 May 2010 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, System Pressure Test Program for the Fourth 10-Year Inspection Interval ML1009205422010-03-31031 March 2010 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section Xl, Inservice Inspection Program for the Fourth Ten-Year Inspection Interval ML1005704132010-02-24024 February 2010 American Society of Mechanical Engineers, Section Xl, Inservice Inspection Program for the Unit 2 Third Ten-Year Inspection Interval, Request for Relief 2-1S1-18, Revision 2 ML1004801252010-02-11011 February 2010 American Society of Mechanical Engineers, Section XI Inservice Inspection Program for Unit 1 Second Ten-Year Inspection Interval, Request for Relief 1-ISI-26, Risk-Informed Inservice Inspection Program ML1001917972010-01-15015 January 2010 American Society of Mechanical Engineers, Section XI Inservice Inspection Program for Browns Ferry Unit 1 Second Ten-Year Inspection Interval and Units 2 & 3 Third Ten-Year Inspection Interval, Request for Relief ISI-23 ML0928005122009-10-0505 October 2009 Comments Regarding NRC Letter and Associated Safety Evaluation for the Browns Ferry Nuclear Plant, Unit 2, Inservice Inspection Program Related to Examination of Piping Weld Overlays ML0926606142009-09-21021 September 2009 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs - Summary Report for Cycle 15 Operation ML0928707662009-09-17017 September 2009 Response to NRC Request for Additional Information for Third 10-Year Interval Inservice Inspection Program Plan, Relief Request 2-ISI-19, Revision 1 ML1019002472009-07-0707 July 2009 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs - Summary Report for Cycle 14 Operation ML0914702082009-05-22022 May 2009 American Society of Mechanical Engineers (ASME) Section Xl, Inservice Inspection Program for the Third Ten-Year Inspection Interval - Request for Relief 2-1Sl-21, Revision 1 - Resubmittal ML0913906422009-05-18018 May 2009 American Society of Mechanical Engineers Section XI, Inservice Inspection Program - Request for Relief 2-ISI-21, Revision 1 - Examination of Piping Weld Overlays ML0906304232009-03-0202 March 2009 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inspection (IWE, and Repair and Replacement Programs - Summary Reports for Cycle 7 Operation 2024-06-23
[Table view] Category:Letter
MONTHYEARML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information ML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report ML24116A2522024-04-25025 April 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A2302024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update ML24106A2612024-04-16016 April 2024 Ltr to State Recognized Tribes-Everhart, Piqua Shawnee Tribe ML24106A2452024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Cernek, Couchatta Tribe of Louisiana ML24106A2472024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Hicks, Eastern Band of Cherokee Indians ML24106A2632024-04-16016 April 2024 Ltr to State Recognized Tribes-Hamilton, Cher-O-Creek Intra Tribal Indians ML24106A2512024-04-16016 April 2024 Letter to Federally Recognized Tribes-Morrow, Thlopthlocco Tribal Town ML24102A0392024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Johnson, Absentee Tribe of Shawnee ML24106A2462024-04-16016 April 2024 Letter to Federally Recognized Tribes-Cypress, Miccosukee Tribe ML24106A2482024-04-16016 April 2024 Letter to Federally Recognized Tribes-Hill, Muscogee (Creek) Nation ML24106A2402024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Barnes, Shawnee Tribe 2024-09-03
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VALLEY TENNESSEE 1\\14 AUTHORITY
Post Office Box 2000, Decatur, Alabama 35609-2000
June 23, 2024 10 CFR 50.55a
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
Browns Ferry Nuclear Plant, Unit 3 Renewed Facility Operating License No. DPR-68 NRC Docket No. 50-296
Subject:
American Society of Mechanical Engineers,Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear Plant, Unit 3, Cycle 21 Operation
The Tennessee Valley Authority is submitting the Browns Ferry Nuclear Plant (BFN), American Society of Mechanical Engineers (ASME),Section XI, Owners Activity Report for BFN, Unit 3, Cycle 21 Operation. The report is contained in the enclosure to this letter and is in accordance with the requirements of ASME Code Case N-532-5, Repair/Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission,Section XI, Division 1.
The report is an overview of the inservice examination results that were performed on components within the ASME Section XI boundary, up to and including the BFN, Unit 3, Cycle 21 refueling outage, during the third inspection period of the Fourth 10 Year Inspection Interval. The applicable provisions of the ASME Code Case N-532-5 require that this report be submitted within 90 calendar days of the completion of each refueling outage. The BFN, Unit 3, Cycle 21 refueling outage ended on March 24, 2024. Accordingly, this submittal is due by June 22, 2024.
U.S. Nuclear Regulatory Commission Page 2 June 23, 2024
There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact David Renn, Site Licensing Manager, at (256) 729-2636.
Respectfully,
Manu Sivaraman Site Vice President
Enclosure:
American Society of Mechanical Engineers,Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear Plant, Unit 3, Cycle 21 Operation
cc (Enclosure): NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant Enclosure
Tennessee Valley Authority
Browns Ferry Nuclear Plant Unit 3
American Society of Mechanical Engineers,Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear Plant, Unit 3, Cycle 21 Operation
See Enclosed
FORM OAR-1 OWNER'S ACTIVITY REPORT
Report Number _,B""F'--'N'--'----'U"--'3"-'R--"2=-1.,__ ___________________________________ _
Plant Browns Ferry Nuclear Plant P 0. Box 2000 Decatur. AL 35609
Unit No. --~3~- date March 1 1977 Refueling Outage no. Refueling Outage 21
{if applicable) Commercial service
Current Inspe c tion Interval FO L![(h Ten Y ear lnspectio~n~ ln=t~e~rv~a~I __________ _______________ _
(1st, 2nd, 3rd, other)
Current Inspection Period ~T~h=ir~d~P_e=r~io~d~---------------------------------
(1st. 2nd. 3rd)
2007 Edition, 2008 Addenda ( ISi)
Edition and Addenda of Section X I applicable to the inspection plans ~2=0-'-1=3_,E=-d=i=ti=o~n__,_(=C~IS"'-'-'1)----------------- ~
0 -T PP -E NG -376. Re vision 0006, 02/07/2024 0-Tl-364, Revision 0026, 11 /28/2023 Date and Revision of inspection plan 0-TPP-ENG-467 Revision 0002 02/05/2024
Edition and Addenda of Section X I applicable to repairs and replacemen ts, if different than the inspection plan ~N~/A~--
Code Cases used for inspection and evaluation N-508 -4 N-532 -- 5 N -6 13-2 N-648-1 N-702 and N-7 16-1 N-747 N-864.
(if applicable, including cases modified by Case N-532 and later revisions)
CERTIFICATE OF CONFORMANCE
I certify tl1at (a) the statempn tq m a de in this report are corre ct; (b) the exam inations and tests meet the In spection Plan as required by the ASME' Code,Section XI; and (c) the repai,/replacement act ivities and evaluations supporting the comp letion of --~U~ 3~R~2~1 __ _
conform to 11,e requireme *' -,ec tion XI. (refueling outage number)
Signed ______________________ Date _______________ _
Owner or Owner s Designee, Title
CERTIFICATE OF INSERVICE INSPECTION
I, the undersigned, holding a valid commission issued by the Na tiona l Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and In surance Company of Hartford Connecticu t have inspected the items described in this Owner's Activity Report and state tha t, to the best of my knowledge and be lief, the Owner has performed all activities represented by this report in accordance w ith the requirements of Section XI.
By signing this certificate neither the In spector n or his emp loyer makes any war ranty, expressed or im plied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, n e ither the Inspector nor his employer shall be liable in any manner for any persona l injury or property damage *r lo s of an r connected with this In spection.
'w; ~ /'1*1"11
--;--f,-'-"---,.,-:-':-::&c~+/---:._,,...,.--=--+------ --'--""'Na'-ti-on-al~B.,_oa~,d=-N-u-'-m-be-r a-n~d ~En-do-rs_e_m-en-, --'-'--'---J/'---Comm issions N ;3 i '19 '7 1 -r, IV R..
Date __ l;)'--lif----+,-"=--------/,/ lo/ 1 vt FORM OAR-1 OWNER'S ACTIVITY REPORT
TABLES Report Number BFN U3R21 ------ - ----- -------------- --- - -
PI ant Browns Ferry Unit No. 3 Commercial service date 03/01/1977 Refueling outage no. 21 - ---
Current inspection interval 4th Current inspection period 3rd ----- ----- --
TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRE EVALUATIONS FOR CONTINUED SERVICE Exam ination Category and Item Number Item Description Evaluation Description CR 1911989, NOi U3R21-001
During VT-3 examination of Mechanical Snubber Support, 3-47B400-75, examiners identified the pin was displaced, not fully engaged with the suppo rt bracket, resulting in examination failure.
Civil Engineering evaluated the condition and F-A / F1.10D Main Steam System Snubber, concluded that the snubber in the "as found "
3-4 7B40 0- 75 condition would still be able to perform its intended design function and sustain the imposed design seismic loads. The design loads would have been transferred from the main steam piping to the EL 584 ' floor steel features. The snubber pin was reinstalled and a new cotter pin was installed topside of the support bracket. The support was then re examined with no recordable indication.
CR 1914074, WO 124338851, NOi U3R21-003
During Owner Elected VT-3 examination of 3-47B455-628 the variable spring support was observed at an as found setting of 1650 lbs. The High Pressure Coolant Injection affected support nominal range setting is 1663 -
F-A / F1.20C System Support, 3-47B455 -628 1738 lbs. The as found setting was roughly 1 %
outside of the acceptable nominal range, constituting a relevant condition as defined in IWF-3410(a)(4), "Improper hot or cold settings of spring supports". The spring can was reset to 1700 lbs.
and an a s left examination was performed with no relevant indications identified.
FORM OAR-1 OWNER'S ACTIVITY REPORT
TABLES Report Number BFN U3R21 -------------------------------
PI ant Browns Ferry Unit No. 3 Commercial service date 03/01/1977 Refueling outage no. 21 ----
Current inspection interval 4th ----- Current inspection period 3rd -------
TABLE 2 AB STRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FO R CONTINUED SERVICE Code Item Description Description of Work Date Repair/Replacement Class Completed Plan Number During a pre-shutdown walk down a defect was revealed when a 1/2" drain pipe sheared at the heat affected zone at the Tee-to-Pipe interface due to cyclic fatigue cracking. (The valve at the end of the pipe was not supported and created a catalever at the pipe-to-tee joint.)
The defect was removed and 21,
Replace reducing Pipe Engineering Change (BFN Tee upstream of valve 010 (AWA-TVA-2024-04 38)) t~
2 BFN-3-VTV-074-0683A was performed to replace a c-o- 03/25/2024 124312449 with a 90-degree elbow degree elbow joint removing the and reducing insert catalever design issue with the drain valve.
The cause of the unacceptab ility is being documented in the BFN corrective action program CR 1911200 with an engineering evaluation shown in the Prompt Determination of Operability (PDQ) 1911200. An ECP was created to address the issue to prevent reoccurance.
FORM OAR-1 OWNER'S ACTIVITY REPORT
TABLES Report Number BFN U3R21 --------- - ---------- - ------
PI ant Browns Ferry Unit No. 3 Commercial service date 03/01/1977 Refueling outage no. 21 ----
Current inspection interval 4th ---- Current inspection period 3rd ------
REPORTING REQUIRED BY 10 CFR 50.55a(b)(2)(ix)(A)
ASME Section XI, Subsection IWE Steel Containment Vessel Inspection program
10 CFR 50.55a(b )(2)(ix)(A) requires reporting of the degradation assessment for inaccessible areas when conditions are identified in accessible areas during the perform a nce of the ASME Section XI, Subsection IWE Steel Containment Vessel (SCV)
Inspection Program that could indicate the presence of or result in degradation to such inaccessible areas.
During BFN U3R21, isolat ed locations of the Moisture Seal Barrier (MSB) of the SCV was identified to have disbonding conditions requiring excavations and examination of in acc e ssi le areas beneath the barrier. The inaccessible areas of the SCV Le neath the MSB we rP-. determined to be acceptable by General Visual examinat ion. Th e P. Xam ination irlGntifa:. d
- 1:J evidence of complete separation from the drywell liner that wou; ~1 ailow moistu 1 *~: to enter the area below the seal. Conditions were corrected by clea n ing and replacing damaged areas of the MSB with no Repair/ Replacement Activity required.