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| | number = ML14318A196 | | | number = ML14318A196 |
| | issue date = 09/05/2014 | | | issue date = 09/05/2014 |
| | title = Browns Ferry, Units 1, 2 and 3, 10 CFR Part 21 Interim Report - Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX | | | title = CFR Part 21 Interim Report - Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX |
| | author name = Polson K J | | | author name = Polson K |
| | author affiliation = Tennessee Valley Authority | | | author affiliation = Tennessee Valley Authority |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:Dz5~cJ ie4c(jcbrAqmIt[ICATennessee Valley Authority, Post Office Box 2000. Decatur, Alabama 35609-2000September 5, 201410 CFR 21.21ATTN: Document Control DeskU.S. Nuclear Regulatory CommissionWashington, D.C. 20555-0001Browns Ferry Nuclear Plant, Units 1, 2, and 3Renewed Facility Operating License Nos. DPR-33,NRC Docket Nos. 50-259, 50-260, and 50-296DPR-52, and DPR-68 | | {{#Wiki_filter:It Dz5~cJie4c(j cbrAqm |
| | [ICA Tennessee Valley Authority, Post Office Box 2000. Decatur, Alabama 35609-2000 September 5, 2014 10 CFR 21.21 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296 |
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| ==Subject:== | | ==Subject:== |
| 10 CFR Part 21 Interim Report -Engine Systems, Inc. -Emergency Diesel Generator Heat Exchanger CEY564L-HEXThe Tennessee Valley Authority (TVA) recently identified a leak in the weld of theEmergency Equipment Cooling Water outlet piping on the head of the C2 EmergencyDiesel Generator (EDG) heat exchanger, CEY564L-HEX. Corrective Action Programdocuments were written to document the failure of the heat exchanger weld and toperform an engineering evaluation of the condition. TVA's evaluation concluded that thiscondition has the potential to constitute a reportable condition pursuant to Title 10 of theCode of Federal Regulations (10 CFR) Part 21, "Reporting of Defects andNoncompliance," and as such, requires additional evaluation.The TVA must perform additional analysis in order to determine the significance of theweld defect. TVA will submit a final 10 CFR Part 21 report by November 6, 2014. Theenclosure to this letter provides information required by 10 CFR Part 21.21 (a)(2) for theinterim report of this condition.There are no new regulatory commitments contained in this letter. Should you have anyquestions concerning this submittal, please contact J. L. Paul, Nuclear Site LicensingManager, at (256) 729-2636.RespectfullyS-/E3r U.S, Nuclear Regulatory CommissionPage 2September 5, 2014 | | 10 CFR Part 21 Interim Report - Engine Systems, Inc. - |
| | Emergency Diesel Generator Heat Exchanger CEY564L-HEX The Tennessee Valley Authority (TVA) recently identified a leak in the weld of the Emergency Equipment Cooling Water outlet piping on the head of the C2 Emergency Diesel Generator (EDG) heat exchanger, CEY564L-HEX. Corrective Action Program documents were written to document the failure of the heat exchanger weld and to perform an engineering evaluation of the condition. TVA's evaluation concluded that this condition has the potential to constitute a reportable condition pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 21, "Reporting of Defects and Noncompliance," and as such, requires additional evaluation. |
| | The TVA must perform additional analysis in order to determine the significance of the weld defect. TVA will submit a final 10 CFR Part 21 report by November 6, 2014. The enclosure to this letter provides information required by 10 CFR Part 21.21 (a)(2) for the interim report of this condition. |
| | There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact J. L. Paul, Nuclear Site Licensing Manager, at (256) 729-2636. |
| | Respectfully S-/E3r |
| | |
| | U.S, Nuclear Regulatory Commission Page 2 September 5, 2014 |
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| ==Enclosure:== | | ==Enclosure:== |
| 10 CFR Part 21 Interim Report -Engine Systems, Inc. -EmergencyDiesel Generator Heat Exchanger CEY564L-HEXcc (w/ Enclosure):NRC Regional Administrator -Region IINRC Senior Resident Inspector -Browns Ferry Nuclear Plant EnclosureBrowns Ferry Nuclear Plant,Units 1, 2, and 310 CFR Part 21 Interim ReportEngine Systems, Inc. -Emergency Diesel Generator Heat Exchanger CEY564L-HEXSee Enclosed 10 CFR Part 21 Interim Report -Engine Systems, Inc. -Emergency Diesel Generator HeatExchanger CEY564L-HEXName and Address of the Individual Making the Interim ReportMr. K. J. PoisonVice PresidentBrowns Ferry Nuclear PlantTennessee Valley AuthorityPost Office Box 2000Decatur, Alabama 35609-2000Identification of the facility, the activity, or basic component supplied for such facility or suchactivity within the United States which fails to comply or contains a defect (under evaluation)On July 10, 2013, the Tennessee Valley Authority (TVA) identified a leak in the weld of theEmergency Equipment Cooling Water (EECW) outlet piping on the head of the C2 EmergencyDiesel Generator (EDG) heat exchanger, CEY564L-HEX.Identification of the firm constructin-g the facility or supplying the basic component which fails tocomply or contains a defect (under evaluation)Engine Systems, Inc.175 Freight RdRocky Mount, NC 27804Description of the Deviation or Failure to Comply that is being EvaluatedA leak was identified in the weld of the EECW outlet piping on the head of the C2 EDG heatexchanger. The TVA determined the cause of the leak to be a vendor manufactured failed weldin the weld joint between the EECW line connection and the inlet / outlet heat exchanger head.Evaluation StatusThe TVA determined the cause of the leak to be a vendor manufactured failed weld in the weldjoint between the EECW line connection and the inlet / outlet heat exchanger head. The C2EDG heat exchanger will undergo additional analysis in order to determine the safetysignificance of the weld defect. Once the analysis is complete, TVA will complete the 10 CFRPart 21 evaluation.Date on which Evaluation will be CompletedThe TVA will submit a final 10 CFR Part 21 report by November 6, 2014.E-1 | | 10 CFR Part 21 Interim Report - Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX cc (w/ Enclosure): |
| ,NSTRUCTIONS FOR FORM 41LLICENSING TRANSMITTAL TO NRC SUMMARY AND CONCURRENCE SHEETDATE DUE: September 5, 2014 -(A) PREPARER: Mark B. Acker (7533) | | NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant |
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| | Enclosure Browns Ferry Nuclear Plant, Units 1, 2, and 3 10 CFR Part 21 Interim Report Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX See Enclosed |
| | |
| | 10 CFR Part 21 Interim Report - Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX Name and Address of the Individual Making the Interim Report Mr. K. J. Poison Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority Post Office Box 2000 Decatur, Alabama 35609-2000 Identification of the facility, the activity, or basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect (under evaluation) |
| | On July 10, 2013, the Tennessee Valley Authority (TVA) identified a leak in the weld of the Emergency Equipment Cooling Water (EECW) outlet piping on the head of the C2 Emergency Diesel Generator (EDG) heat exchanger, CEY564L-HEX. |
| | Identification of the firm constructin-g the facility or supplying the basic component which fails to comply or contains a defect (under evaluation) |
| | Engine Systems, Inc. |
| | 175 Freight Rd Rocky Mount, NC 27804 Description of the Deviation or Failure to Comply that is being Evaluated A leak was identified in the weld of the EECW outlet piping on the head of the C2 EDG heat exchanger. The TVA determined the cause of the leak to be a vendor manufactured failed weld in the weld joint between the EECW line connection and the inlet / outlet heat exchanger head. |
| | Evaluation Status The TVA determined the cause of the leak to be a vendor manufactured failed weld in the weld joint between the EECW line connection and the inlet / outlet heat exchanger head. The C2 EDG heat exchanger will undergo additional analysis in order to determine the safety significance of the weld defect. Once the analysis is complete, TVA will complete the 10 CFR Part 21 evaluation. |
| | Date on which Evaluation will be Completed The TVA will submit a final 10 CFR Part 21 report by November 6, 2014. |
| | E-1 |
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| | ,NSTRUCTIONS FOR FORM 41L LICENSING TRANSMITTAL TO NRC |
| | |
| | ==SUMMARY== |
| | AND CONCURRENCE SHEET DATE DUE: September 5, 2014 -(A) PREPARER: Mark B. Acker (7533) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Interim Part 21 Report -C2 Emergency Diesel Generator Heat Exchanger Weld Defect -PER 913911REGULATORY CONSIDERATIONS(B) Oath or Affirmation nl YES 0 NO (E) Posting Requirements Ii YES 0 NO(C) Licensing Verification 0 YES El NO (F) FSAR EFFECT El YES 0 NO(D) New Commitments E] YES Z NO (G) OGC Consultation El YES 0 NO(H) LIC-109 Review El YES 0 N/A (I) Engineering Independent El YES 0 NOTechnical Review (ITR)*Engineering (only): I Design Change # N/AINDEPENDENT TECHNICAL REVWER(J) Licensing (only):PEER CHECKERCONCURRENCE (K)A concurrence signature reflects that the signatory has assured that, with respect to the signatory's area of cognizance,the submittal is appropriate and consistent with TVA Policy, the submittal is complete and accurate, applicablecommitments are approved for implementation and supporting documentation for submittal completeness and accuracyhas been prepared.NAME ORGANIZATION SIGNATURE DATEICAREB26J. Paul Site Licensing Manager V<<.,'IS. Hunnewell Engineering Manager I/P. Summers Director Plant SupportB. Wetzel Corp Licensing 0(L) Licensing (only): S>--J(k&{ ,L -"'5rO .)QUALITY IEVIEWERTVA 41035Page 1 of 1NPG-SPP-03.10-1 [10-31-2013] | | Interim Part 21 Report - C2 Emergency Diesel Generator Heat Exchanger Weld Defect - |
| ,NSTRUCTIONS FOR FORM 41LICENSING TRANSMITTAL TO NRC SUMMARY AND CONCURRENCE SHEETDATE DUE September 5. 2014 (A) PREPARER Mark B. Acker (7533)SUBJECT Interim Part 21 Report -C2 Emergency Diesel Generator Heat Exchanger Weld Defect -PER 913911REGULATORY CONSIDERATIONS(B) Oath or Affirmation E YES & NO (E) Posting Requirements E YES 0 NO(C) Licensing Verification 09 YES C] NO (F) FSAR EFFECT LI YES 0 NO(D) New Commitments 0 YES Z NO (G) OGC Consultation f- YES 0 NO(H) LIC-109 Review C3 YES [D N/A (I) Engineering Independent C] YES 0 NOTechnical Review (ITR)*Engineering (only) Design Change # N/AINDEPENDENT TECHNICAL REVIWER(j) Licensing (only) -.C/ 74) 6?PEER CHECKERCONCURRENCE (K)A concurrence signature reflects that the signatory has assured that. with respect to the signatory's area of cognizance,the submittal is appropriate and consistent with TVA Policy. the submittal is complete and accurate, applicablecommttments are approved for implementation and supporting documentation for submittal completeness and accuracyhas been preparedNAME ORGANIZATION SIGNATURE DATEICA REB .7~a.L-- _____.1. uinul Site Liccnsingf Nlanag~erS. IlunnewelI Enginecrint! Manager1'. S.ummers Director Plant Support11. Wetzel Corp Licenring(L) Licensing (only).QUALITY REVIEWERTVA 41035Page 1 of 1NPG-SPP-03 10-1 110-31-20131 oNSTRUCTIONS FOR FORM 41LLICENSING TRANSMITTAL TO NRC SUMMARY AND CONCURRENCE SHEETDATEDUE Setembr 5 204 I(A) PREPARER: Mark B. Acker (7533) | | PER 913911 REGULATORY CONSIDERATIONS (B) Oath or Affirmation nl YES 0 NO (E) Posting Requirements Ii YES 0 NO (C) Licensing Verification 0 YES El NO (F) FSAR EFFECT El YES 0 NO (D) New Commitments E] YES Z NO (G) OGC Consultation El YES 0 NO (H) LIC-109 Review El YES 0 N/A (I) Engineering Independent El YES 0 NO Technical Review (ITR) |
| | *Engineering (only): I Design Change # N/A INDEPENDENT TECHNICAL REVWER (J) Licensing (only): |
| | PEER CHECKER CONCURRENCE (K) |
| | A concurrence signature reflects that the signatory has assured that, with respect to the signatory's area of cognizance, the submittal is appropriate and consistent with TVA Policy, the submittal is complete and accurate, applicable commitments are approved for implementation and supporting documentation for submittal completeness and accuracy has been prepared. |
| | NAME ORGANIZATION SIGNATURE DATE ICAREB26 J. Paul Site Licensing Manager V<<.,'I S. Hunnewell Engineering Manager I/ |
| | P. Summers Director Plant Support B. Wetzel Corp Licensing 0 (L) Licensing (only): S>--J(k&{ ,L -"'5rO .) |
| | QUALITY IEVIEWER TVA 41035 Page 1 of 1 NPG-SPP-03.10-1 [10-31-2013] |
| | |
| | ,NSTRUCTIONS FOR FORM 41 LICENSING TRANSMITTAL TO NRC |
| | |
| | ==SUMMARY== |
| | AND CONCURRENCE SHEET DATE DUE September 5. 2014 (A) PREPARER Mark B. Acker (7533) |
| | SUBJECT Interim Part 21 Report - C2 Emergency Diesel Generator Heat Exchanger Weld Defect - |
| | PER 913911 REGULATORY CONSIDERATIONS (B) Oath or Affirmation E YES & NO (E) Posting Requirements E YES 0 NO (C) Licensing Verification 09 YES C] NO (F) FSAR EFFECT LI YES 0 NO (D) New Commitments 0 YES Z NO (G) OGC Consultation f- YES 0 NO (H) LIC-109 Review C3 YES [D N/A (I) Engineering Independent C] YES 0 NO Technical Review (ITR) |
| | *Engineering (only) Design Change # N/A INDEPENDENT TECHNICAL REVIWER (j) Licensing (only) -. C/ 74) 6? |
| | PEER CHECKER CONCURRENCE (K) |
| | A concurrence signature reflects that the signatory has assured that. with respect to the signatory's area of cognizance, the submittal is appropriate and consistent with TVA Policy. the submittal is complete and accurate, applicable commttments are approved for implementation and supporting documentation for submittal completeness and accuracy has been prepared NAME ORGANIZATION SIGNATURE DATE ICA REB . 7~a.L-- _____ |
| | .1. uinul Site Liccnsingf Nlanag~er S. IlunnewelI Enginecrint! Manager 1'. S.ummers Director Plant Support 11.Wetzel Corp Licenring (L) Licensing (only). |
| | QUALITY REVIEWER TVA 41035 Page 1 of 1 NPG-SPP-03 10-1 110-31-20131 |
| | |
| | oNSTRUCTIONS FOR FORM 41L LICENSING TRANSMITTAL TO NRC |
| | |
| | ==SUMMARY== |
| | AND CONCURRENCE SHEET DATEDUE Setembr 5 204 I(A) PREPARER: Mark B. Acker (7533) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Interim Part 21 Report -C2 Emergency Diesel Generator Heat Exchanger Weld Defect -PER 913911REGULATORY CONSIDERATIONS(B) Oath or Affirmation []YES 0 NO (E) Posting Requirements El YES 0 NO(C) Licensing Verification [ YES El NO (F) FSAR EFFECT []YES [ NO(D) New Commitments [] YES [ NO (G) OGC Consultation El YES [] NO(H) LIC-109 Review E] YES Z N/A (I) Engineering Independent El YES | | Interim Part 21 Report - C2 Emergency Diesel Generator Heat Exchanger Weld Defect - |
| * NOTechnical Review (ITR)*Engineering (only): / Design Change # NIAINDEPENDENT TECHNICAL REWER(J) Licensing (only): A/5PEER CHECKERCONCURRENCE (K)A concurrence signature reflects that the signatory has assured that, with respect to the signatory's area of cognizance,the submittal is appropriate and consistent with TVA Policy, the submittal is complete and accurate, applicablecommitments are approved for implementation and supporting documentation for submittal completeness and accuracyhas been prepared.NAME ORGANIZATION SIGNATURE DATEICAREBJ. Paul Site Licensing ManagerS. Hunnewell Engineering Manager .P. Summers Director Plant SupportB. Wetzel Corp Licensing(L) Licensing (only): /QUALITY REVIEWERTVA 41035Page 1 of 14NPG-SPP-03.10-1 [10-31-20131 Integrated Coi.,1leteness and Accuracy Review L..:,uation BoardMinutes01 /,o5 /iohiDate:Subjectmm/dd/yyyy,T')vt e, ,r% 2 ýIA eo, f- -P,C2 Lb6H,) L1e/J l)e bec.ýCorrespondence Type:NOV Response E] GL Response E] Bulletin Response [] CAL Response 5]Allegation Response El RAI Response [I NOED [] Relief Request 0 Security Event Report 5LAR 0 LER El Licensedclperator ] Required Report 0Other'q Describe: Tot I 'I r", -pp -Board MembersMember Name (print) TitleChairperson -- ; j-'vl Pv1-e,,-Member #2 C/\ ne A essarMember #3 ";~ ;ce- ~L~;ce~Member #4_(if necessary) __________________________MinutesDiscussion of Validation/Verification Performed-., fJ ÷j -do 5----j due i-J e, f\ 1r1e-f,"nlyn(J ý F er 9 e-r-\Yes*j)Ip.Cý n evcA /U dC, , ý"CConclusion Additional Validation/Verification Required:Now'Yesl1Describe Additional Validation (if required):C1. Q LC L A/ CV;./(6 eIcc/y %dr--eciCN~2&JiMinutes Approved:/ Q JICAREB Chairperson/Date}} | | PER 913911 REGULATORY CONSIDERATIONS (B) Oath or Affirmation []YES 0 NO (E) Posting Requirements El YES 0 NO (C) Licensing Verification [ YES El NO (F) FSAR EFFECT []YES [ NO (D) New Commitments [] YES [ NO (G) OGC Consultation El YES [] NO (H) LIC-109 Review E] YES Z N/A (I) Engineering Independent El YES |
| | * NO Technical Review (ITR) |
| | *Engineering (only): / Design Change # NIA INDEPENDENT TECHNICAL REWER (J) Licensing (only): A/5 PEER CHECKER CONCURRENCE (K) |
| | A concurrence signature reflects that the signatory has assured that, with respect to the signatory's area of cognizance, the submittal is appropriate and consistent with TVA Policy, the submittal is complete and accurate, applicable commitments are approved for implementation and supporting documentation for submittal completeness and accuracy has been prepared. |
| | NAME ORGANIZATION SIGNATURE DATE ICAREB J. Paul Site Licensing Manager S. Hunnewell Engineering Manager . |
| | P. Summers Director Plant Support B. Wetzel Corp Licensing (L) Licensing (only): / |
| | QUALITY REVIEWER TVA 41035 Page 1 of 1 4NPG-SPP-03.10-1 [10-31-20131 |
| | |
| | Integrated Coi., 1 leteness and Accuracy Review L..:,uation Board Minutes Date: 01 /,o5 /iohi mm/dd/yyyy Subject ,T')vte, ,r %2 ýI Aeo, f- -P, C2 Lb6 H,) L1e/Jl)ebec.ý Correspondence Type: |
| | NOV Response E] GL Response E] Bulletin Response [] CAL Response 5] |
| | Allegation Response El RAI Response [I NOED [] Relief Request 0 Security Event Report 5 LAR 0 LER El Licensedclperator ] Required Report 0 Other'q Describe: I Tot 'Ir",- pp - |
| | Board Members Member Name (print) Title Chairperson -- ; j-'vl L;ce.*, Pv1-e,,- |
| | Member #2 ne essar C/\ A Member #3 ;ce- |
| | ";~ ~L~;ce~ |
| | Member #4_(if necessary) __________________________ |
| | Minutes Discussion of Validation/Verification Performed |
| | , fJ |
| | -. ÷j *u,-,?o..o do - 5- 00- e,f\ 1r1e |
| | --- j due i-J C*,I*,.de - |
| | - f,"nly n(J ý F er 9 e-r-\ Yes*j) |
| | : p. I Cý n evcA /U , dC, |
| | ý"C Conclusion Additional Validation/Verification Required: Now' Yesl1 Describe Additional Validation (if required): |
| | C1.LC Q L CV;./( A/ 6e Icc/y %dr--eci Minutes Approved: CN~2&Ji / Q J ICAREB Chairperson/Date}} |
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Category:Deficiency Correspondence (per 10CFR50.55e and Part 21)
MONTHYEARML24175A0042024-06-23023 June 2024
Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System
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EN 56958_1 Ametek Solidstate Controls, Inc
ML24023A2802024-01-23023 January 2024
Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump
ML22075A2192021-11-29029 November 2021
10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0133, Rev. 0 - Swing Check Valve, P/N ESl50359
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C&D Technologies, Inc. -10 CFR Part 21 Evaluation Regarding Container Failure in KCR-07 Batteries
ML19317D0932019-10-25025 October 2019
Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10 CFR21-0127, Rev. 0, Emd Fuel Injectors - Seized Plunger and Bushing
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10 CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0123, Rev. 1
ML18075A3552018-03-0606 March 2018
10 CFR Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl 10x8x10 and 6x4x6 Bolted Bonnet Gate Valve
ML17114A0692017-04-19019 April 2017
Part 21 Report - Control Rod Drive Mechanisms Contaminated with Chlorides
ML17081A4532017-03-20020 March 2017
Part 21 - Plastic Jar Dedication Sampling
ML16252A2742016-08-29029 August 2016
Azz/Nli - Part 21 Report - Potential Allen Bradley Timing Relay
ML15223B2662015-08-0707 August 2015
Part 21 Report - Crane Nuclear Pressure Seal Valve with Retaining Rings
ML15201A2872015-07-0808 July 2015
Crane Nuclear, Inc. - Part 21 Interim Report - Notification of Pressure Seal Valve Yoke Material Compliance
ML15134A0162015-05-0101 May 2015
Part 21 Report Regarding Potentially Unqualified Component in Certain Allen Bradley Timing Relays
ML14309A5292014-10-31031 October 2014
Closure of 10 CFR Part 21 Interim Report - Engine Systems, Inc., Emergency Diesel Generator Heat Exchanger CEY564L-HEX
ML14318A1962014-09-0505 September 2014
CFR Part 21 Interim Report - Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX
ML14216A3772014-07-30030 July 2014
Part 21 Report - Incorrect Industrial Irradiator Dose
ML14210A0102014-07-23023 July 2014
Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve
ML14204A7072014-07-23023 July 2014
Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV
ML14189A4172014-07-0707 July 2014
Closure of 10 CFR Part 21 Interim Report - Limitorque Valve Motor - Motor Operator of SMB-0 Valve Actuator
ML14192A0382014-07-0303 July 2014
Part 21 Report Incorrect Industrial Irradiator
ML14079A0272014-03-13013 March 2014
Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve
ML14069A4672014-02-26026 February 2014
Part 21 Report Involving a Potential Manufacturing Defect in Replacement Masterpact Cradles
ML13260A0772013-09-12012 September 2013
10 CFR Part 21 Interim Report - General Electric (GE) Hitachi Nuclear Energy - Sbm Type Manual Switch
ML13246A0872013-08-23023 August 2013
Nuclear Nonconformance Event Number 49302 - 10CFR21 Notification
ML13165A3422013-06-12012 June 2013
60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers
ML13094A1772013-03-18018 March 2013
Notice to the U.S. Nuclear Regulatory Commission of a Possible Deviation or Defect in Nuclear Qualified High Efficiency Particulate Air Filters Manufactured by Aaf
ML13044A0752013-02-0808 February 2013
Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology
ML13008A3212013-01-0404 January 2013
Anti-Rotation Pin Failure in Anchor Darling (Flowserve) Double Disc Gate Valve
ML12347A3082012-12-12012 December 2012
Part 21 60-Day Interim Report Notification: Error in Main Steam Line High Flow Calculational Methodology
ML12319A0122012-09-27027 September 2012
Error in Main Steam Line High Flow Calculational Methodology
ML12158A4472012-06-0606 June 2012
Part 21 60-Day Interim Report Notification - Closufailure of CRD Collet Retainer Tube/Outer Tube Weld
ML12094A3712012-04-0202 April 2012
Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations
ML1127000672011-09-26026 September 2011
GE-Hitachi Part 21 Reportable Condition Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance
ML11115A0392011-04-14014 April 2011
Notice of Deviation Pursuant to 10 CFR 21, NPKC-7-21A(N) Splice Kit with Possible Compromised Jacket Seal
ML1025202192010-09-0303 September 2010
Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance
ML1025201572010-08-16016 August 2010
Initial Exam 2010-301 Final Administrative Documents
ML1018907392010-07-0101 July 2010
Part 21 Report Concerning Failure of Turbine Overspeed Reset Control Valve Diaphragm
ML0907611882009-03-11011 March 2009
Part 21 Notification - Defective Hk and K-Line Circuit Breaker Tension Springs
ML0511602412005-04-14014 April 2005
Thermo Electron Svioc, SV18C and SV28C Series Recorders
ML0506302442005-03-0202 March 2005
Part 21 Report Concerning MCPR Limits and MCPR Monitoring
ML0501902562005-01-14014 January 2005
Non-Emergency Event Report from Framatome Anp, Inc
ML0232901622002-11-18018 November 2002
Final Report, Stability Option III: Possible Successive Confirmation Count Resets - Not Reportable
2024-06-23
[Table view]
Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML23348A3942023-12-14014 December 2023
Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve
ML23335A0722023-12-0101 December 2023
Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump
ML23320A2542023-11-16016 November 2023
Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump
ML23282A0022023-10-0606 October 2023
Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump
ML22208A0042022-06-17017 June 2022
Nutherm International, Inc., USNRC 10CFR Part 21 Notification Reference: Arnold Magnetics Power Supply Part Number PBM-24-106
ML22153A0792022-04-0707 April 2022
10CFR Part 21 Notification for Curtiss-Wright Supplied RCS-Dresser Actuator P/N: SURE-24-10-4
ML21294A0292021-10-0404 October 2021
Flowserve Part 21 Notification for Limitorque Supplied DC Motor
ML20049A0752020-02-11011 February 2020
C&D Technologies, Inc. -10 CFR Part 21 Evaluation Regarding Container Failure in KCR-07 Batteries
ML19317D0932019-10-25025 October 2019
Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10 CFR21-0127, Rev. 0, Emd Fuel Injectors - Seized Plunger and Bushing
ML19002A2042018-12-21021 December 2018
to Engine Systems, Inc., Part 21 Report Re Emd Fuel and Soakback Pumps - Potentially Undertorqued Cover Bolts
ML18341A2472018-12-0606 December 2018
Mirion Technologies - 10 CFR Part 21.21 Report Re Relays Defect
ML18354A7422018-12-0404 December 2018
Engine Systems, Inc., Submittal of 1OCFR21 Reporting of Defects and Non-Compliance - Report No. 1OCFR21-0123, Rev. 0 - Emo Fuel and Soakback Pumps - Potentially Undertorqued Cover Bolts
ML18087A0032018-03-21021 March 2018
Crane Nuclear, Inc. - Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl 10x8x10 and 6x4x6 Bolted Bonnet Gate Valve (Updated)
ML18075A3552018-03-0606 March 2018
10 CFR Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl 10x8x10 and 6x4x6 Bolted Bonnet Gate Valve
ML18079A0142018-03-0606 March 2018
Crane Nuclear, Inc., 10 CFR Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl I0x8x10 and 6x4x6 Bolted Bonnet Gate Valve
ML18003A2602017-12-19019 December 2017
Crane Nuclear, Inc. - 10 CFR Part 21 Notification of Defect on Weak Link Analysis for Chapman Gate Valve Figure L900, Item #18, Drawing CC05307, Revision B
ML17194A8252017-07-11011 July 2017
Part 21 Report Re Wedge Pin Failure in Anchor Darling Motor Operated Double Disc Gate Valves with Threaded Stem to Upper Wedge Connections
ML17179A3782017-06-0707 June 2017
TE Connectivity - Part 21 Transfer of Information TE-023
ML17114A0692017-04-19019 April 2017
Part 21 Report - Control Rod Drive Mechanisms Contaminated with Chlorides
ML17114A0702017-04-13013 April 2017
Part 21 Notification - Identified Fisher 546S Electro-Pneumatic Transducers Standard Mounting Brackets Failed Seismic Testing Standards
ML17081A4532017-03-20020 March 2017
Part 21 - Plastic Jar Dedication Sampling
ML17026A4142017-01-20020 January 2017
C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling
ML16278A4712016-09-22022 September 2016
Notification of 10 CFR Part 21 Condition, Masterpact Breaker Fail to Close
ML16281A2702016-09-22022 September 2016
Part 21 - Initial Notification of Masterpact Breaker Fail to Close
ML16252A2742016-08-29029 August 2016
Azz/Nli - Part 21 Report - Potential Allen Bradley Timing Relay
ML16243A4742016-08-26026 August 2016
Potential Part 21 Unqualified Component in Certain Allen Bradley Timing Relays
ML16238A1862016-08-15015 August 2016
Update - Report of Potential l0CFR Part 21, Allen Bradley Timing Relay Model 700RTC-NRC Event Number 51030, Accession Number ML15134A016
ML16232A6042016-08-15015 August 2016
Potentially Unqualified Component in Certain Allen Bradley Timing Relays
ML16196A0642016-07-10010 July 2016
Part 21 Report - Materials Not Properly Dedicated
ML16188A3742016-06-30030 June 2016
Part 21 - Inadequate Swaging and Adherence of Silicone O-Ring and Silicone PAD Soft Seat Main Disc and Pilot Disc Assemblies
ML16154A2072016-05-26026 May 2016
Part 21, Azz/Nli Nuclear Logistics, Inc., Potentially Unqualified Component in Certain Allen Bradley Timing Relays Model 700RTC
ML16194A1992016-05-25025 May 2016
Azz/Nli - Update - Report of Potential 10CFR Part 21, Allen Bradley Timing Relay Model 700RTC
ML16111A4202016-04-0808 April 2016
Part 21 Report No. P21-04302015, Rev. 1 Regarding Potentially Unqualified Component in Certain Allen Bradley Timing Relays, Per Browns Ferry, Ginna, Millstone, Nine Mile Point, North Anna, Ft. Calhoun, Perry, River Bend, South Texas Project
ML15201A2872015-07-0808 July 2015
Crane Nuclear, Inc. - Part 21 Interim Report - Notification of Pressure Seal Valve Yoke Material Compliance
ML15134A0162015-05-0101 May 2015
Part 21 Report Regarding Potentially Unqualified Component in Certain Allen Bradley Timing Relays
ML15159A5682015-04-30030 April 2015
Report of Potential 10CFR Part 21, Allen Bradley Timing Relay Model 700RTC
ML15099A0422015-04-0202 April 2015
Notification of Part 21 Report - Potentially Defective Pressure & Temperature Switches
ML15099A0432015-04-0202 April 2015
Amendment to Event Number 50299, 10 CFR Part 21 Notification, Potentially Defective Pressure & Temperature Switches
ML14303A2582014-10-27027 October 2014
10 CFR Part 21 Notification of an Error in Powerplex MCPR and LHGR Limit Input for Browns Ferry, Unit 2
ML14274A0522014-09-22022 September 2014
Final Report 10CFR Part 21 Evaluation Regarding Misaligned Separators in LCR-25 Standby Batteries, Revision 1 - Original Letter Did Not Include the List of Affected Utilities
ML14318A1962014-09-0505 September 2014
CFR Part 21 Interim Report - Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX
ML14216A3772014-07-30030 July 2014
Part 21 Report - Incorrect Industrial Irradiator Dose
ML14220A0212014-07-29029 July 2014
Final Report - Closure for Iterim 10CFR Part 21 Report (PMT No. 14-01, Ncr Event No. /Accession No. ML14192A040)
ML14213A0992014-07-24024 July 2014
Notification of Part 21 Report - Potentially Defective Pressure & Temperature Switches
ML14204A7082014-07-23023 July 2014
Enclosure 2, Description of Closure Evaluation, Non-Proprietary Information - Class I (Public)
ML14210A0102014-07-23023 July 2014
Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve
ML14204A7072014-07-23023 July 2014
Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV
ML14189A4172014-07-0707 July 2014
Closure of 10 CFR Part 21 Interim Report - Limitorque Valve Motor - Motor Operator of SMB-0 Valve Actuator
ML14192A0382014-07-0303 July 2014
Part 21 Report Incorrect Industrial Irradiator
ML14192A0402014-07-0303 July 2014
Interim Report - 10CFR Part 21 Evaluation Regarding Potential Deficiencies
2023-12-14
[Table view]
Category:Letter
MONTHYEARIR 05000259/20240032024-11-0404 November 2024
Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003
CNL-24-043, Application for Subsequent Renewed Operating Licenses, Second Safety Supplement2024-11-0101 November 2024
Application for Subsequent Renewed Operating Licenses, Second Safety Supplement
ML24305A1692024-10-31031 October 2024
Site Emergency Plan Implementing Procedure Revision
05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024
Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators
05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024
Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure
ML24299A2632024-10-25025 October 2024
Response to Apparent Violation in NRC Inspection Report 05000260/2024090, EA-24-075
ML24289A1232024-10-24024 October 2024
Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry
CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
ML24308A0042024-10-16016 October 2024
Ahc 24-1578 Environmental Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Subsequent License Renewal Application Limestone County
CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024
Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1
ML24270A2162024-09-27027 September 2024
Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075
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
ML24262A1502024-09-24024 September 2024
Requalification Program Inspection - Browns Ferry Nuclear Plant
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
ML24239A3332024-09-0303 September 2024
Full Audit Plan
IR 05000259/20244042024-09-0303 September 2024
Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter
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
IR 05000259/20244022024-08-0606 August 2024
Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402
ML24219A0272024-08-0606 August 2024
Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
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)
05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024
Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints
05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024
Inoperability of Unit 3 Diesel Generator Due to Relay Failure
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)
05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024
Reactor Scram Due to Generator Step-Up Transformer Failure
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)
ML24071A0292024-06-0505 June 2024
Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter
ML24068A2612024-06-0505 June 2024
SLRA Fluence Methodology Report - Proprietary Determination Letter
IR 05000259/20244032024-05-22022 May 2024
– Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403
05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024
High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation
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
2024-09-03
[Table view] |
Text
It Dz5~cJie4c(j cbrAqm
[ICA Tennessee Valley Authority, Post Office Box 2000. Decatur, Alabama 35609-2000 September 5, 2014 10 CFR 21.21 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296
Subject:
10 CFR Part 21 Interim Report - Engine Systems, Inc. -
Emergency Diesel Generator Heat Exchanger CEY564L-HEX The Tennessee Valley Authority (TVA) recently identified a leak in the weld of the Emergency Equipment Cooling Water outlet piping on the head of the C2 Emergency Diesel Generator (EDG) heat exchanger, CEY564L-HEX. Corrective Action Program documents were written to document the failure of the heat exchanger weld and to perform an engineering evaluation of the condition. TVA's evaluation concluded that this condition has the potential to constitute a reportable condition pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 21, "Reporting of Defects and Noncompliance," and as such, requires additional evaluation.
The TVA must perform additional analysis in order to determine the significance of the weld defect. TVA will submit a final 10 CFR Part 21 report by November 6, 2014. The enclosure to this letter provides information required by 10 CFR Part 21.21 (a)(2) for the interim report of this condition.
There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact J. L. Paul, Nuclear Site Licensing Manager, at (256) 729-2636.
Respectfully S-/E3r
U.S, Nuclear Regulatory Commission Page 2 September 5, 2014
Enclosure:
10 CFR Part 21 Interim Report - Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX cc (w/ Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant
Enclosure Browns Ferry Nuclear Plant, Units 1, 2, and 3 10 CFR Part 21 Interim Report Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX See Enclosed
10 CFR Part 21 Interim Report - Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX Name and Address of the Individual Making the Interim Report Mr. K. J. Poison Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority Post Office Box 2000 Decatur, Alabama 35609-2000 Identification of the facility, the activity, or basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect (under evaluation)
On July 10, 2013, the Tennessee Valley Authority (TVA) identified a leak in the weld of the Emergency Equipment Cooling Water (EECW) outlet piping on the head of the C2 Emergency Diesel Generator (EDG) heat exchanger, CEY564L-HEX.
Identification of the firm constructin-g the facility or supplying the basic component which fails to comply or contains a defect (under evaluation)
Engine Systems, Inc.
175 Freight Rd Rocky Mount, NC 27804 Description of the Deviation or Failure to Comply that is being Evaluated A leak was identified in the weld of the EECW outlet piping on the head of the C2 EDG heat exchanger. The TVA determined the cause of the leak to be a vendor manufactured failed weld in the weld joint between the EECW line connection and the inlet / outlet heat exchanger head.
Evaluation Status The TVA determined the cause of the leak to be a vendor manufactured failed weld in the weld joint between the EECW line connection and the inlet / outlet heat exchanger head. The C2 EDG heat exchanger will undergo additional analysis in order to determine the safety significance of the weld defect. Once the analysis is complete, TVA will complete the 10 CFR Part 21 evaluation.
Date on which Evaluation will be Completed The TVA will submit a final 10 CFR Part 21 report by November 6, 2014.
E-1
,NSTRUCTIONS FOR FORM 41L LICENSING TRANSMITTAL TO NRC
SUMMARY
AND CONCURRENCE SHEET DATE DUE: September 5, 2014 -(A) PREPARER: Mark B. Acker (7533)
SUBJECT:
Interim Part 21 Report - C2 Emergency Diesel Generator Heat Exchanger Weld Defect -
PER 913911 REGULATORY CONSIDERATIONS (B) Oath or Affirmation nl YES 0 NO (E) Posting Requirements Ii YES 0 NO (C) Licensing Verification 0 YES El NO (F) FSAR EFFECT El YES 0 NO (D) New Commitments E] YES Z NO (G) OGC Consultation El YES 0 NO (H) LIC-109 Review El YES 0 N/A (I) Engineering Independent El YES 0 NO Technical Review (ITR)
- Engineering (only): I Design Change # N/A INDEPENDENT TECHNICAL REVWER (J) Licensing (only):
PEER CHECKER CONCURRENCE (K)
A concurrence signature reflects that the signatory has assured that, with respect to the signatory's area of cognizance, the submittal is appropriate and consistent with TVA Policy, the submittal is complete and accurate, applicable commitments are approved for implementation and supporting documentation for submittal completeness and accuracy has been prepared.
NAME ORGANIZATION SIGNATURE DATE ICAREB26 J. Paul Site Licensing Manager V<<.,'I S. Hunnewell Engineering Manager I/
P. Summers Director Plant Support B. Wetzel Corp Licensing 0 (L) Licensing (only): S>--J(k&{ ,L -"'5rO .)
QUALITY IEVIEWER TVA 41035 Page 1 of 1 NPG-SPP-03.10-1 [10-31-2013]
,NSTRUCTIONS FOR FORM 41 LICENSING TRANSMITTAL TO NRC
SUMMARY
AND CONCURRENCE SHEET DATE DUE September 5. 2014 (A) PREPARER Mark B. Acker (7533)
SUBJECT Interim Part 21 Report - C2 Emergency Diesel Generator Heat Exchanger Weld Defect -
PER 913911 REGULATORY CONSIDERATIONS (B) Oath or Affirmation E YES & NO (E) Posting Requirements E YES 0 NO (C) Licensing Verification 09 YES C] NO (F) FSAR EFFECT LI YES 0 NO (D) New Commitments 0 YES Z NO (G) OGC Consultation f- YES 0 NO (H) LIC-109 Review C3 YES [D N/A (I) Engineering Independent C] YES 0 NO Technical Review (ITR)
- Engineering (only) Design Change # N/A INDEPENDENT TECHNICAL REVIWER (j) Licensing (only) -. C/ 74) 6?
PEER CHECKER CONCURRENCE (K)
A concurrence signature reflects that the signatory has assured that. with respect to the signatory's area of cognizance, the submittal is appropriate and consistent with TVA Policy. the submittal is complete and accurate, applicable commttments are approved for implementation and supporting documentation for submittal completeness and accuracy has been prepared NAME ORGANIZATION SIGNATURE DATE ICA REB . 7~a.L-- _____
.1. uinul Site Liccnsingf Nlanag~er S. IlunnewelI Enginecrint! Manager 1'. S.ummers Director Plant Support 11.Wetzel Corp Licenring (L) Licensing (only).
QUALITY REVIEWER TVA 41035 Page 1 of 1 NPG-SPP-03 10-1 110-31-20131
oNSTRUCTIONS FOR FORM 41L LICENSING TRANSMITTAL TO NRC
SUMMARY
AND CONCURRENCE SHEET DATEDUE Setembr 5 204 I(A) PREPARER: Mark B. Acker (7533)
SUBJECT:
Interim Part 21 Report - C2 Emergency Diesel Generator Heat Exchanger Weld Defect -
PER 913911 REGULATORY CONSIDERATIONS (B) Oath or Affirmation []YES 0 NO (E) Posting Requirements El YES 0 NO (C) Licensing Verification [ YES El NO (F) FSAR EFFECT []YES [ NO (D) New Commitments [] YES [ NO (G) OGC Consultation El YES [] NO (H) LIC-109 Review E] YES Z N/A (I) Engineering Independent El YES
- NO Technical Review (ITR)
- Engineering (only): / Design Change # NIA INDEPENDENT TECHNICAL REWER (J) Licensing (only): A/5 PEER CHECKER CONCURRENCE (K)
A concurrence signature reflects that the signatory has assured that, with respect to the signatory's area of cognizance, the submittal is appropriate and consistent with TVA Policy, the submittal is complete and accurate, applicable commitments are approved for implementation and supporting documentation for submittal completeness and accuracy has been prepared.
NAME ORGANIZATION SIGNATURE DATE ICAREB J. Paul Site Licensing Manager S. Hunnewell Engineering Manager .
P. Summers Director Plant Support B. Wetzel Corp Licensing (L) Licensing (only): /
QUALITY REVIEWER TVA 41035 Page 1 of 1 4NPG-SPP-03.10-1 [10-31-20131
Integrated Coi., 1 leteness and Accuracy Review L..:,uation Board Minutes Date: 01 /,o5 /iohi mm/dd/yyyy Subject ,T')vte, ,r %2 ýI Aeo, f- -P, C2 Lb6 H,) L1e/Jl)ebec.ý Correspondence Type:
NOV Response E] GL Response E] Bulletin Response [] CAL Response 5]
Allegation Response El RAI Response [I NOED [] Relief Request 0 Security Event Report 5 LAR 0 LER El Licensedclperator ] Required Report 0 Other'q Describe: I Tot 'Ir",- pp -
Board Members Member Name (print) Title Chairperson -- ; j-'vl L;ce.*, Pv1-e,,-
Member #2 ne essar C/\ A Member #3 ;ce-
";~ ~L~;ce~
Member #4_(if necessary) __________________________
Minutes Discussion of Validation/Verification Performed
, fJ
-. ÷j *u,-,?o..o do - 5- 00- e,f\ 1r1e
--- j due i-J C*,I*,.de -
- f,"nly n(J ý F er 9 e-r-\ Yes*j)
- p. I Cý n evcA /U , dC,
ý"C Conclusion Additional Validation/Verification Required: Now' Yesl1 Describe Additional Validation (if required):
C1.LC Q L CV;./( A/ 6e Icc/y %dr--eci Minutes Approved: CN~2&Ji / Q J ICAREB Chairperson/Date
