ML15254A545

Peach Bottom, Units 2 and 3 - Response to Draft Request for Additional Information Regarding Proposed Relief Request Associated with the Common Emergency Service Water (ESW) System Piping

ML15254A545
Person / Time
Site:	Peach Bottom
Issue date:	09/11/2015
From:	David Helker Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MF6551, TAC MF6552
Download: ML15254A545 (9)

Text

Exelon Generation September 11, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 200 Exelon Way Kennett Square. 'A 19348 www.exeloncorp.com 10 CFR 50.55a Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278

Subject:

Response to Draft Request for Additional Information Regarding Proposed Relief Request Associated with the Common Emergency Service Water (ESW) System Piping for Peach Bottom Atomic Power Station, Units 2 and 3

References:

1) Letter from D. P. Helker (Exelon Generation Company, LLC) to the U.S. Nuclear Regulatory Commission, "Proposed Relief Request associated with the Common Emergency Service Water (ESW) System Piping," dated July 29, 2015 2) E-mail correspondence from R. Ennis (U.S. Nuclear Regulatory Commission) to S. J. Hanson (Exelon Generation Company, LLC), "Peach Bottom Atomic Power Station -Request for Additional Information Regarding Proposed Relief Request 14R-56 Emergency Service Water Leak Repair Deferral (ML 15223A515)," dated August 6, 2015 3) Letter from D. P. Helker (Exelon Generation Company, LLC) to the U.S. Nuclear Regulatory Commission, "Response to Request for Additional Information Regarding Proposed Relief Request associated with the Common Emergency Service Water (ESW) System Piping for Peach Bottom Atomic Power Station, Units 2 and 3," dated August 13, 2015. 4) E-mail correspondence from R. Ennis (U.S. Nuclear Regulatory Commission) to S. J. Hanson (Exelon Generation Company, LLC), "Peach Bottom Atomic Power Station -Draft Request for Additional Information Regarding Proposed Relief Request 14R-56 Emergency Service Water Leak Repair Deferral (NRC TAC Nos. MF6551 and MF6552)," dated September 8, 2015 U.S. Nuclear Regulatory Commission Response to Request for Additional Information Concerning Relief Request 14R-56 September 11, 2015 Page2 By letter dated July 29, 2015, Exelon Generation Company, LLC (Exelon) submitted a Relief Request to the U.S. Nuclear Regulatory Commission (NRC) for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3 (Reference 1). Specifically, Exelon requested that the NRC authorize relief from Code Case N-513-3, "Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1" of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) and the condition placed on Code Case N-513-3 as listed in Regulatory Guide 1.147, "lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1," Revision 17, dated August 2014. In the Reference 2 e-mail correspondence, the U.S. NRC requested additional information. Reference 3 provided Exelon's response. In the Reference 4 e-mail correspondence, the U.S. NRC requested additional information. Attached is our response. There are no regulatory commitments in this response. If you have any questions concerning this response, please contact Stephanie J. Hanson at 610-765-5143. Respectfully, David P. Helker Manager, Licensing and Regulatory Affairs Exelon Generation Company, LLC

Attachment:

Response to Draft Request for Additional Information Regarding Proposed Relief Request 14R-56 cc: USNRC Region I, Regional Administrator USNRC Senior Resident Inspector, PBAPS USNRC Project Manager, PBAPS R. R. Janati, Pennsylvania Bureau of Radiation Protection S. T. Gray, State of Maryland

Response to Request for Additional Information Concerning Relief Request 14R-56 Docket Nos. 50-277 and 50-278 Planar Flaw Evaluation in ferritic ninine IA W Code Case N-513-3 PBAPS ESW Min Wall "B" ESW {IR 2494904-03} I Definitions: I Flaw depth (lnom. tmin) -Information Only a= 0.047 I Pipe wall thickness ( lnom) t= 0.375 I Maximum assumed circumferential flaw length (dadi): l= 13.500 I Pipe outside diameter: D= 12.75 I R = D-t Mean pipe radius: R= 6.21 I 2 Piping bending moment of inertia: I= 7t[D4-(D-2t)4J I= 247.06 I 64 Flaw half-angle per Figure I, N-513: 0 = 2*R 8= 1.087 I Unit definition for kips: I kip= 1000 lbf I Unit definition for psi: I ksi = 1000 psi I Pinine Loads <Moments Increased bv 25% for Uncertainties): I Maximum operating pressure: OP= 58.00 I POP = -t )2

• OP Maximum operating pressure axial force: Pop= 6662.82 I Axial load on pipe for Normal/Upset condition forces: Pnu= 957.00 I Axial load on pipe for Emergency/Faulted condition forces: Pnf= 1109.00 I Total axial load on pipe, including pressure from piping analysis for normal/upset condition forces: Pn = Pop+Pnu Pn= 7619.82 I Total axial load on pipe, including pressure from piping analysis for emergency/faulted condition forces: Pr= Pop+Pnr Pf= 7771.82 I Applied bending moment on the pipe from piping analysis Mn= 2206.25 for normal/upset condition (SRSS(MA, MB, MC) for WTOl+SEISOB) I Aoolied bending moment on the pipe from piping analysis Mf= 4328.02 for emergency/faulted condition (SRSS(MA, MB, MC) for WTO I +SEISSS) I Pipe thermal expansion stress from piping analysis: Pe= 0.000 I I Adjusted thickness per CC N-513-3, § 3.2(d) tadi = 0.328 I in in in in in in"4 rad psi lbs lbs lbs lbs lbs ft-lbf ft-lbf ksi in Enclosure 1 Page 1 of 4 Response to Request for Additional Information Concerning Relief Request 14R-56 Docket Nos. 50-277 and 50-278 Circumferential Flaw Evaluation Usinl! N-513 Pioinl! Material Prooerties Ref. ASME B31.1): Young's Modulus: E= 27850 ksi Poisson's Ratio: µ= 0.30 E'= (FJ(I-µ2) E'= 30604.40 ksi Material Prooerties for Flaws oer H-4000: From ASME XI C-8322 J1c = Allowable Fracture Toughness, Kie: K1c = Kie= (CJ1c

• E') I (1000 lbf/k.ip))0*5 N-513 Annendix I Circumferential Flaw eouations: Accurate between 5 and 20. Conservative over 20. R/t= Am= -2.02917 + I.67763*(R/t) -0.07987*(Rlt/ + O.OOJ 76*(R/t)3 Am= Bm = 7.09987 -4.42394*(R/t) + 0.21036*(R/t)2 -0.00463*(R/t)3 Bm= Cm= 7.79661 + 5.16676*(R/t) -0.24577*(R/t)2 + 0.00541 *(R/t)3 Cm= Fm= 1.0 + Am*(0ht{5 + Bm*(0ht)2'5 + Cm*(0hr)3*5 Fm= Ab= -3.26543 + I.52784*(R/t) -0.072698*(R/t)2 + 0.0016011 *(R/t)3 Ab= Bb = l 1.36322 -3.91412*(R/t) + 0.18619*(R/t/-0.004099*(R!t}3 Bb= Cb= -3.18609 + 3.84763*(R/t)-O.l8304*(R/t)2 + 0.00403*(R/t)3 Cb= Fb = 1.0 + Ab*(0ht/5 + Bb*(0ht)25 + Cb*(0hr)3-5 Fb= 45 37.l 11 18.936 13.05 -32.68 54.24 2.68 10.47 -23.82 31.40 2.22 in*lbf/in2 ksi*in°*5 Acceptable Enclosure 1 Page 2 of 4 Response to Request for Additional Information Concerning Relief Request 14R-56 Docket Nos. 50-277 and 50-278 Annlied Stress Intensitv Factor KI for Circumferential Flaw: N-513 Appendix I requires that the flaw depth in the C-7300 stress intensity equations be changed to the flaw half-length, c: Maximum assumed circumferential flaw length: l= 13.500 Flaw half-length, c = 1/2: c= 6.75 Note: Units are converted automatically. NormaVUnset Condition <ref. C-4311): Kim=( 2.1*Pn }(Jr*c)0.5 *Fm Kim= 19.804 2*Jl'*R*t ( 2.3

• Mn J ( )o.s K lb = i + . Ji. c . Fb Jl'*R *t K1b= 15.646 Kr= Krm+Krb Kr= 35.450 Therefore, Kr< Klc: Acceptable Emer2encv/Faulted Condition <ref. C-4311 ): K = *Jl'*c *F ( 1.8 P1 J ( ) Im 2 . :Jl'

• R . t m Krm= 13.466 ( 1.6 M 1 ) ( )°' 21.351 K lb = 2 + Pe . Jr . c . Fb Krb= Jr* R *t K1= K1m+K1b Kr= 34.817 Therefore, K1 < Klc: Acceptable in in ksi-in°5 ksi-in°*5 ksi-in°.s ksi-in°5 ksi-in°*5 ksi-in°5 Enclosure 1 Page 3 of 4 Response to Request for Additional Information Concerning Relief Request 14R-56 Docket Nos. 50-277 and 50-278 Axial Throu!!h-walll Flaw Evaluation Usin!! N-513 Stress Intensitv Factor KI for an axial flaw subiect to the boundin!! condition <ref. C-4311): Axial flaw length: l= 8.000 in Flaw half-length, c = 1/2: c= 4 in Maximum operating pressure: OP= 58 psi Safety Factor for normal/upset conditions from C-2622: SF= 2.7 N-513 Appendix I assigned flaw shape parameter for a through-wall flaw: Q= 1.00 /... = c/(R *t)0*5 /...= 2.802 Therefore, O<'A.<5: Acceptable Note: Units are converted automatically F = 1.0 + 0.072449*/... + 0.64856*/...2 -0.2327*/...3 + 0.038154*/... 4 -0.0023487*/...5 F= 3.122 K = SF. OP. R . 7t. c . F ( r I t Q Ki= 32.823 k .. 0.5 SI-In Therefore, K1 < Kie: Acceptable END OF ASME CODE CASE N-513-3 EVALUATION Enclosure 1 Page 4 of 4