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{{Adams
#REDIRECT [[CP-201500685, Response to Request for Additional Information for Relief Request 2A3-1, Unit 2, Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Class 1 & 2.]]
| number = ML15211A240
| issue date = 07/22/2015
| title = Comanche Peak - Response to Request for Additional Information for Relief Request 2A3-1, Unit 2, Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section Xi Examination Requirements for Clas
| author name = Flores R, Madden F W
| author affiliation = Luminant Generation Co, LLC, Luminant Power
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000446
| license number =
| contact person =
| case reference number = CP-201500685, TAC MF5813, TXX-15104
| document type = Inservice/Preservice Inspection and Test Report, Letter, Response to Request for Additional Information (RAI)
| page count = 6
| project = TAC:MF5813
| stage = Response to RAI
}}
 
=Text=
{{#Wiki_filter:Rafael Flores Luminant PowerSenior Vice President P0O Box 1002____& Chief Nuclear Officer 6322 North FM 56RafaeI.Flores@Luminant.com Glen Rose, TX 76043Luminant 258759CP-201500685 Ref. # 10CFR50.55a(z)(1)TXX-15104July 22, 2015U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555
 
==SUBJECT:==
COMANCHE PEAK NUCLEAR POWER PLANTDOCKET NO. 50-446RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FORRELIEF REQUEST 2A3-1 FOR UNIT 2 INSERVICE INSPECTION FOR APPLICATIONOF AN ALTERNATIVE TO THE ASME BOILER AND PRESSURE VESSEL CODESECTION XI EXAMINATION REQUIREMENTS FOR CLASS 1 AND 2 PIPING WELDS(2007 EDITION OF ASME CODE, SECTION XI, 2008 ADDENDATHIRD INTERVAL START DATE: AUGUST 3, 2014THIRD INTERVAL END DATE: AUGUST 2, 2023)
 
==REFERENCES:==
: 1. Letter logged TXX-15032 dated March 4, 2015 from Rafael Flores to the NRCsubmitting Relief Request No. 2A3-1 Regarding Risk Informed Jnservice InspectionProgram for the Class 1 and 2 Piping (Third ISI Interval Start Date: August 3, 2014;Third ISI Interval End Date: August 2, 2023)2. Email dated June 22, 2015 from Baiwant Singal of the NRC to Timothy Hope ofLuminant Power requesting additional information regarding Relief Request 2A3-1(TAC No. MF5813)
 
==Dear Sir or Madam:==
Per Reference 1, Lumninant Generation Company, LLC (Luminant Power) submitted Relief Request 2A3-1for Comanche Peak Unit 2 for the third ten year inservice inspection interval. Per Reference 2, the NRCprovided a request for additional information regarding the subject relief request.Attached is the Luminant Power response to the request for additional information.This communication contains no new licensing basis commitments regarding Comanche Peak Unit 2.
U. S. Nuclear Regulatory CommissionTXX-15 104Page 2 of 207/22/2015Should you have any questions, please contact Mr. Jack Hicks at (254) 897-6725.Sincerely,Luminant Generation Company LLCRafael FloresBY: redW. Ma~dden ,-°- --Director, External AffairsAttachment -Response to Request for Information Regarding Unit 2 Relief Request 2A3-1 for Risk-Informed Inservice Inspection of Piping Weldsc -Marc L. Dapas, Region IVBalwant K. Singal, NIRKResident Inspectors, Comanche PeakRobert Free, TDLRJack Ballard, ANII, Comanche Peak Attachment to TXX- 15104Page 1 of 4COMANCHE PEAK NUCLEAR POWER PLANT UNIT 2RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDINGRELIEF REQUEST 2A3-1 FOR RISK-INFORMED INSERVICE INSPECTION OF PIPING WELDS(THIRD 10-YEAR ISI INTERVAL START DATE: August 3, 2014)TAC NO. MF5813NRC REQUEST 1:Of the welds not selected for future examinations, did the previous examinations identify any serviceinduced degradation? If service induced degradation was identified, please discuss the degradationmechanism. Please discuss the corrective actions taken to mitigate the degradation?LUMINANT POWER RESPONSE TO REQUEST 1:During the Second Interval there were no unacceptable indications identified during the performance ofthe RI-ISI examinations. Therefore, no new service induced degradation was identified and nocorrective actions were required.NRC REQUEST 2:Please identify any augmented inspection programs subsumed in the proposed third 10-year intervalRI-ISI program and discuss the reason(s) for any changes. Examples include: augmented program formanaging thermal fatigue (NRC Bulletin (BL) 88-11, Generic Letter (GL) 89-08, NRC InformationNotice (IN) 93-20, and Materials Reliability Program (MRP)-146), augmented program for addressingstress corrosion cracking (BL 79-17), augmented program to address the requirements of 10 CER50.55a(g)(6)(ii)(E) that requires implementation of ASME Code Case N-722-1 with conditions,augmented program for piping welds in high energy main steam and main Feedwater piping (NRCNUIREG-0800, Standard Review Plan 3.6.2, and augmented program for inspection of feedwater systempiping (NRC BL 79-13).LUMINANT POWER RESPONSE TO REQUEST 2:The PI-ISI process has criteria that specifically evaluate the susceptibility of piping to thermal fatigueissues. Therefore, augmented examination programs such as those presented in NRC Bulletin 88-11,Information Notice 93-20, MRP-146 and Bulletin 79-13 are subsumed by the RI-ISI application. This isthe same criteria that has been implemented and approved since the initial RI-ISI application in 2001.The augmented inspection program for flow accelerated corrosion (FAC) per Generic Letter 89-08 isrelied upon to manage this damage mechanism and remains a separate program which is not affectedor changed by the RI-ISI program. This is the same criteria that has been implemented and approvedsince the initial RI-ISI application in 2001.The augmented inspection program for high energy break exclusion piping is a separate program and isnot affected or changed by this RI-ISI Relief Request.CPNPP will meet the criteria of 10CER50.55a(g)(6)(ii)(E) and therefore implement Code Case N-722-1for the performance of reactor coolant pressure boundary visual inspections.CPNPP will meet the criteria of 10CFR50.55a(g)(6)(ii)(F) and therefore implement Code Case N-770-1for the examination of Class 1 piping and nozzle dissimilar-metal butt welds. The Risk Ranking,Element Selection, and Risk Impact Analysis has been changed to reflect the inspection of PrimaryWater Stress Corrosion Cracking (PWSCC) under Code Case N-770-1 with the applicable weldsremoved from the RI-ISI Element Selection process.
Attach ment to TXX- 15104Page 2 of 4COMANCHE PEAK NUCLEAR POWER PLANT UNIT 2RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDINGRELIEF REQUEST 2A3-1 FOR RISK-INFORMED INSERVICE INSPECTION OF PIPING WELDS(THIRD 10-YEAR ISI INTERVAL START DATE: August 3, 2014)TAC NO. MF5813Portions of the containment spray and residual heat removal systems contain Class 2 piping that is lessthan 0.375 in. thick. ASME Section XI does not require surface or volumetric examinations on this piping,based on the wall thickness. However, in response to NRC SSER-26, CPNPP committed to performingvolumetric examinations on 7.5% of the welds in this "thin wall' piping during each ten year interval. Thispiping was included in the scope of the RI-ISI application, and therefore is addressed by the RI-ISIprogram. Consequently, the RI1-ISI program subsumes this augmented inspection program. This is thesame criteria that has been implemented and approved since the initial RI-ISI application in 2001.There are no other augmented examination programs that interface with the RI-ISI program.NRC REQUEST 3:The NRC staff notes that the licensee did not specify in P.R 2A3-1 whether it will review and update theproposed third 10-year CPNPP, Unit 2, RI-ISI program on a regular basis (e.g., at least on the basis ofthe ASME Code periods, more frequently if dictated by any plant procedure to update the probabilisticrisk assessment (PRA), or as new degradation mechanisms are identified). Please clarify whether thelicensee will implement a monitoring program to review and update the proposed RI-ISI program forthe third 10-year 131 interval in accordance with the guidance in NRC Regulatory Guides (RGs) 1.174and 1.178.LUMINANT POWER RESPONSE TO REQUEST 3:Both the original RI-1SI submittal and the resultant NRC Safety Evaluation call for a periodic reviewand update. The RI-ISI program is a living program requiring feedback of new relevant information toensure the appropriate identification of high safety significant piping locations. As a minimum, the RI-ISI program will be reviewed and adjusted on an ASME period basis. In addition, significant changesmay require more frequent adjustment as directed by NRC Bulletin or Generic Letter requirements, orby industry and plant specific feedback. This is the same criteria that has been implemented andapproved since the initial PI-ISI application in 2001.
Attachment to TXX-15104Page 3 of 4COMANCHE PEAK NUCLEAR POWER PLANT UNIT 2RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDINGRELIEF REQUEST 2A3-1 FOR RISK-INFORMED INSERVICE INSPECTION OF PIPING WELDS(THIRD 10-YEAR ISI INTERVAL START DATE: August 3, 2014)TAC NO. MF5813NRC REQUEST 4:In Section 4.0 of the NRC safety evaluation report of EPRI TR-112657, Revision B-A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure," (ADAMS Accession No. ML013470102), the NRCstaff concluded that a licensee requesting to implement an RI-ISI program pursuant to 10 CFR50.55a(z)(1) may incorporate into its application, by reference, the program described in EPRI TR-112657, Revision B-A, together with appropriate plant specific information, provided that theapplication includes, among other items, a summary of the risk impact of the changes to the ISIprogram.The licensee stated in its application dated March 4, 2015 that a new risk impact analysis wasperformed, and that the revised RI-ISI program continues to represent a risk reduction when comparedto the last deterministic ASME Code, Section XI, inspection program.To demonstrate that the acceptance criteria of EPRI TR-112657, Revision B-A, for change in CDF andLERF per system are met, please provide tabulated values for the system level changes in CDF andLERF (i.e., the changes in CDF and LERF compared between the ASME Code 1SI program and theCPNPP, Unit 2, third 10-year RI-lSI program). For an example, please refer to Tables 3.6.1 and 3.6.2 ofLuminant letter dated February 15, 2001 (ADAMS Accession Number ML010520269) requesting relieffrom the ASME Code, Section XI examination requirements for inservice inspection of Class 1 and 2piping welds for CPNPP, Units 1 and 2.LUMINANT POWER RESPONSE TO REQUEST 4:See the table on the foliowing page for the results of the current risk impact analysis for CPNPP Unit 2.The applicable "CDF Impact" and "LERF Impact" values are those with Probability of Detection (POD)included.
Attachment to TXX-15104Page 4 of 4-_________ ____________ -CPNPP Unit 2 Bounding Estim~ate of Risk Impoact Based on Best E~stimate Failure RatesRsUpeBon FalrPoeta Bet POD Improvement Inspection CDF Impact LERF ImpactRik ppr oud alue otntal BetFactors LocationsSyst -1R 1TEstimate1 _ ____ ______ ______ ____CaRak isk Cat Risk Cat D j Rank Failure Rate S Xl I-S None S XIl I-S Delta w/ POD wlo POD w/ POD w/o PODRCS -2 High 1.98E-03 1.65E-03 TASCS, TT Medium 2.00E-07 0.3 0.9 0.5 4 2 2.38E-10 3.96E-10 -198E-10 3.30E-10RCS 2 High 1.98E-03 165E-03 TASCS Medium 2.00E-07 0.3 0.9 0.5 1 6 5 -2.02E-09 -9.90E-10 -1.68E-09 -8.25E-10RCS 2 Higqh 1.98E-03 165E-03 TT Medium 2.OOE-07 0.3 0.9 0.5 4 0 -4 4.75E-10 7.92E-1D 3.96E-10 6.60E-10TT MediumRCS 2 (2) High (High) 1.98E-03 165E-03 (PWSCC) (Medium) 2.00E-07 0.3 0.9 0.5 1 0 -1 1.19E-10 1.98E-f0 9.90E-11 1.65E-19RCS 4 Medium 1.00E-04 !.00E-05 None Low 1.00E-08 0.5 0.5 0.5 49 30 -19 9.50E-12 9.50E-12 9.50E-13 9.50E-13RCS 4 (2) Medium) 100E-0 !.00E-05 NoneCC Lowium 1.0E-C8 0.5 0.5 0.5 12 0 -12 6.00E-12 6.00E-12 6.00E-13 6.00E-13RCS 5a Medium 1.00E-04 IO00E-05 TASCS Medium 2.00E-07 0.3 0.9 0.5 5 2 6.O0E-12 3.O0E-11 -6.00E-13 3.00E-12RCS 5a Medium 1.00E-04 1.00E-05 TT Medium 2.00E-07 0.3 0.9 0.5 2 6 4 -9.60E-11 -4.00E-11 -9.60E-12 -4.00E-12Medium TT MediumRCS 5a (5a) (Medium) 1.OOE-04 I.00E-05 (PWSCC) (Medium) 2.00E-07 0.3 0.9 0.5 1 0 -1 6.00E-12 1.00E-11 6.00E-13 l00E-12RCS 6a Low 1.OOE-06 1.00E-07 None Low 1.OOE-08 0.5 0.5 0.5 0 0 0 no change no change no change no chan qeRCS 7a Low 1.00E-06 !.00E-07 None Low 1.00E-08 0.5 0.5 0.5 0 0 0 nochange nochange nochange nochangeRCS Total _____________ ____-1.74E-09 4.12E-10 -1.39E-09 3.32E-10CVCS Sa Medium 1.OOE-04 1.00E-05 TT Medium 2.O0E-07 0.3 0.9 0.5 q0 0 0 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00CVCS 6a Low 1.OOE-06 1.00E-07 None Low lOO.0E-08 0.5 0.5 5 0 -5 negligible negligible negl~igible negqligibleCVCS 6b Low 1.00E-06 1.00E-07 TT Medium 2.00E-07 0.3 0.9 0.5 0 0 0 no change no change no change no changqeCVCS 7a Low 1.00E-06 tO00E-07 None Low t.00E-08 0.5 0.5 0.5 0 0 0 no change no changqe no changqe no changqeCVCS Total _________0.OOE+OO O.OOE+O0 O.OOE+O0 O.OOE+00SIS 4 Medium 1.00E-04 tO0E-05 None Low IOOE-08 0.5 0.5 0.5 4 10 6 -3.OOE-12 -3.OOE-12 -3.OOE-!3 -3.O0E-13SIS 6a Low 1.OOE-06 1.00E-07 None Low 1.OOE-08 0.5 0.5 0.5 33 7 -26 1.30E-13 1.30E-13 1.30E-14 !.30E-14SIS 6b Low 1.OOE-06 1.00E-07 IGSCC Medium ZO2.0E-07 0.5 0.5 2 2 0 0.OOE+00 0.O0E+00 0.00E+00 0.OOE+00SIS 7a Low 1.0OE-06 1.00E-07 None Low 1.00E-08 0.5 0.5 0.5 6 0 -6 negqli~gible negligible negligqible negqligibleSIS Total _______________________-2.87E-12 -2.87E-12 -2.87E-13 -2.87E-13RHRS 4 Medium 1.0OE-04 1.00E-O5 None Low 1.O0E-08 0.5 0.5 0.5 17 13 -4 2.OOE-12 2.OOE-12 2.00E-13 2.00E-13RHRS 6a Low 1.OOE-06 !.00E-07 None Low 1.O0E-08 0.5 0.5 0.5 0 0 0 no changqe no changqe no change no changqeRHRS Total ____________2.OOE-12 2.OOE-12 2.OOE-13 2.OOE-13CSS 4 Medium 1.00E-04 1.00E-05 None Low I.00E-08 0.5 0.5 0.5 13 2 -11 5.50E-12 5.5OE-12 5.50E-13 5.50E-13CSS 6a Low 1.00E-06 1.00E-05 None Low 1.00E-08 0.5 0.5 0.5 3 0 -3 negligqible negligible negligible negligibleCSS 7a Low 1.00E-06 t00E-07 None Low !l00E-08 0.5 0.5 0.5 14 0 -14 negligible negligible negligible negligibleCSS Total ___ ____________ ____ __________5.50E-12 5.50E-12 5.50E-13 5.50E-13FWS 6b (4) Medium 1.00E-04 l.00E-05 TFASCS Medium 2.00E-07 0.3 0.9 0.5 3 0 -3 negligible negligible negligible negligibleFWS 7a (4) Low 1.OOE-06 1.00E-07 None(FAC) Low(High) l.00E-08 0.5 0.5 0.5 14 0 -14 negligible negligible negligible negligibleFWS Total ________________0.OOE+OO O.O0E+OO O.00E+00 0.O0E+O0MSS 7a Medium 1.O0E-04 l00E-05 None(FAC) Low(High) 1.00E-08 0.5 0.5 0.5 0 0 0 negligible negligible negligible negligibleMSS Total ____ _______________negligible negligible negligible negligibleAFW 6a (3) Medium 1.00E-04 !l00E-05 None (FAC) Low(High) l00E-08 0.5 0.5 0.5 7 0 -7 negligible negligible negligible negligibleAFW Total _________ ______________negligible negligible negligible negligibleGrand Total ___________ __________-1.74E-09 4.16E-10 -1.39E-09 3.32E-10}}

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