NG-09-0663, Time Limited Aging Analysis Evaluations for the Duane Arnold License Renewal Project

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Time Limited Aging Analysis Evaluations for the Duane Arnold License Renewal Project
ML093000503
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 03/21/2008
From: Evon K, Tang S
Structural Integrity Associates
To:
Duane Arnold, Office of Nuclear Reactor Regulation
References
DAEC-20Q-338, FOIA/PA-2010-0209, K1160464, NG-09-0663
Download: ML093000503 (30)
v • d • e


Text

StructuralIntegrityAssociates, Inc. File No.: DAEC-20Q-338 CALCULATION PACKAGE Project No.: DAEC-20Q PROJECT NAME:

Time Limited Aging Analysis Evaluations for the Duane Arnold License Renewal Project CONTRACT NO.:

Ki 16046 CLIENT: PLANT:

FPL Energy Duane Arnold, LLC Duane Arnold Energy Center (DAEC)

CALCULATION TITLE:

RPV Circumferential and Axial Weld Examination Relief NON-PROPRIETARY, REDACTED VERSION Document Affected Project Manager Preparer(s) &

Revision Pages Revision Description Approval Checker(s)

Signature & Date Signatures & Date 0 1 - 15, Initial Issue. G. L. Stevens Keith R. Evon Appendix:

Al- A2 /4 d *<)z~ -JZ In 3/21/2008 3/21/2008 Computer Files S. S. Tang 3/21/2008 Page 1 of 15 F0306-OIRO

1 StructuralIntegrityAssociates, Inc.

Table of Contents 1.0 O B JEC TIV E ................................................................................................................................. 3 2.0 M E T HO D O L O GY ....................................................................................................................... 3 3.0 REACTOR VESSEL AXIAL AND CIRCUMFERENTIAL WELD CONFIGURATIONS ...... 3 4.0 BELTLINE AXIAL SHELL WELD INSPECTION ACCESIBILITY ................................. 3 5.0 REACTOR VESSEL FLUENCE ................................................................ 4 6.0 REACTOR VESSEL DIMENSIONS AND WELD CHEMISTRY .................... 4 7.0 LOADING CONDITIONS AND OTHER INPUTS ............................................................. 4 8.0 A N A L Y SE S ................................................................................................................................. 7 9.0 RESU LTS OF AN ALY SIS .................................................................................................... 8 10.0 CO N C L U SION S .......................................................................................................................... 8 11.0 RE FE REN C ES ............................................................................................................................. 9 APPENDIX A: LISTING OF COMPUTER INPUT AND OUTPUT FILES ............................... Al List of Tables Table 1: Axial Inspection Coverage Results [6, Table NDE-ROO1] ........................................................ 11 Table 2: Peak Neutron Fluence for Energy > 1.0 MeV for DAEC RPV Weld and Shell Locations at the Inner Surface [5] ................................................................................................................... 11 Table 3: Maximum > 1.0 MeV Neutron Fluence in DAEC RPV Axial and Circumferential Welds

[5 ] ................................................................................................................................................ 12 Table 4: Weld Chemistries and ART Values for 54 EFPY [7] ........................................................... 13 Table 5: Probability of Failure Due to LTOP Event Per 60 Years ..................................................... 14 Table 6: Probability of Failure Due to LTOP Event Per Year ........................................................... 14 List of Figures Figure 1: DAEC RPV Shell Weld Locations and Identifications [4] .................................................. 15 File No.: DAEC-20Q-338 Page 2 of 15 Revision: 0 F0306-O1RO

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1.0 OBJECTIVE The purpose of this calculation is to justify the elimination of the reactor pressure vessel (RPV) circumferential weld examinations in the vessel beltline region to the end of the extended period of operation (60 years or 54 EFPY) for the Duane Arnold Energy Center (DAEC). This evaluation is based on the methodology presented in Reference [1]. This evaluation includes the estimate of the probability of failure due to a limiting event (i.e., low temperature over-pressurization, or LTOP) for the case of 90% axial weld inspection of the RPV axial welds in the RPV beltline region.

2.0 METHODOLOGY The evaluation was performed using the same methodology used in Reference [1]. A Monte Carlo simulation was performed to determine the beltline circumferential and axial welds failure probability using a project specific version, VIPERXP [2], of the program VIPER Version 1.2 developed by Structural Integrity Associates [3]. The software, VIPER, was developed as part of the program contained in Reference [1] for the BWR RPV beltline shell weld inspection recommendations. The project specific version of VIPER was verified in Reference [2]. The code verified for use is identical to the code used in BWRVIP-05 [1]. The only reason for the different executable is to allow use of the program under the Windows XP operating system.

The detailed description of the methodology is documented in Reference [1].

3.0 REACTOR VESSEL AXIAL AND CIRCUMFERENTIAL WELD CONFIGURATIONS The DAEC RPV weld configuration including the beltline region is shown in Figure 1 [4]. There is one circumferential weld, DE (VCB-A2), in the beltline region. Four axial welds, (El (VLB-A2), E2 (VLB-A1), DI (VLA-A1), and D2 (VLA-A2)), have at least a portion of their length in the beltline region. The azimuth location for each of these four axial welds is also shown in Figure 1. The length of each axial weld is approximately 146.125 inches [13].

All other axial and circumferential welds are located outside of the beltline region. Only the portions of welds within the beltline region are subjected to significant neutron fluence from the reactor core.

Neutron fluence on the welds outside the beltline regions is considered insignificant. These areas outside the beltline region contribute insignificant risk to the RPV integrity and are therefore not included in the evaluation.

There is only one circumferential shell weld in the beltline region of the DAEC RPV, which is located between the lower intermediate shell and lower shell, at an elevation of 238.625 inches [4].

4.0 BELTLINE AXIAL SHELL WELD INSPECTION ACCESIBILITY The past inspection coverage results for the DAEC RPV are provided in References [6] and [13].

The results summarized in Table 1 include OD and ID examination percentages.

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5.0 REACTOR VESSEL FLUENCE The maximum fluence at the end of 60 years or 54 effective full power years (EFPY) of operation is obtained from Table 2-1, Table 7-1, and Table 7-2 of Reference [5], and is shown in Tables 2 and 3.

In the beltline region, the fluence distribution varies as a function of vessel azimuth and elevation due to the fuel bundle configuration. The maximum 54 EFPY fluence is 7.5 lxlO' 8 n/cm 2 in Shell Ring 2 (50 Azimuth), as shown in Table 2. The maximum 54 EFPY fluence in the circumferential weld DE (VCB-A2) is 5.85x1018 n/cm 2 . The maximum 54 EFPY fluence in the beltline axial welds is 6.29x10 18 n/cm 2 per Table 7-1 of Reference [5]. The maximum fluence from Shell Ring 2 is used for the beltline axial welds for conservatism. Note that it is significantly conservative to assume the peak fluence for all portions of the welds that fall in the beltline region. Actual fluence profiles typically show significant variation from this peak value both axially and circumferentially in the beltline region.

The 54 EFPY peak ID fluence of 7.5 x10O18 n/cm 2 is as shown in References [5] and [7] and also shown in Tables 2 and 4.

6.0 REACTOR VESSEL DIMENSIONS AND WELD CHEMISTRY The relevant DAEC RPV dimensions are as follows:

Shell Inside Radius (base metal) 92.69" [8, Page 42], [12, Sheet 84 of SII]

Shell Wall Thickness 4.469" [8, Page 42], [12, Sheet 84 of SIl]

Clad Thickness 3/16" [12, Page S21-1 and Sheet 84 of SI]

Shell Mean Radius (Including Cladding) 94.83" [((92.69"-3/16")*2+4.469"+3/16")/2]

The weld chemistry and other material properties of the DAEC RPV were obtained from Reference [7], and are shown in Table 4.

7.0 LOADING CONDITIONS AND OTHER INPUTS Other loading conditions and input for this analysis are:

Vessel Temperature Operating 5330 F [9, Region B, EPU conditions]

Event (LTOP) 88' F [10, Page 21]

Vessel Pressure Operating 1025 psig [9, Region B, EPU conditions]

Event (LTOP) 1,150 psig [10, Page 21]

Crack Geometry: Axial Elliptical Crack with an aspect ratio a/l = 0.1 360' Circumferential Crack File No.: DAEC-20Q-338 Page 4 of 15 Revision: 0 F0306-01 RO

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Flaw Density 30 flaws/mr3 (1.8 flaws/total length of beltline axial welds) 30 flaws/mr3 (3.67 flaws/360° beltline circumferential welds)

Assuming a double V weld, the area of the weld profile is calculated as:

Area = Cx2xt 2

= 12.51868 inches where: t = vessel thickness including cladding

= 4.469" + 3/16"

= 4.6565" c = base of triangle shown below t

= TAN (30') x -

2 The volume is therefore the Area times the length of the weld. The length of an axial weld is 146.125" [13]. The length of a circumferential weld is the circumference (based on the mean radius of 94.83" specified in Section 6.0).

The two weld volumes are therefore:

Vaxial = length x Area x number of welds

- 146.125 inches x 12.51868 inches2 x 2

= 3658.6 circumference x area Vcirc = circumference x Area

= 2 r r x Area 2

= 2 r x 94.83 inches x 12.51868 inches 3

- 7459 inches where: r mean radius from Section 6.0

= 94.83 inches And, the number of flaws is then calculated as volume x flaw density. The conversion from inches 3 to meter 3 is 1.6387064 x 10-.

3

  1. of Axial flaws = 3658.6 inches 3 x 1.6387064 x 10-5 x 30 flaws/mi

= 1.8 flaws 3

  1. of circumferential flaws = 7459 inches 3 x 30 flaws/mr

= 3.67 flaws File No.: DAEC-20Q-338 Page 5 of 15 Revision: 0 F0306-OIRO

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t t/2 t

C Information regarding Flaw Size Distribution and Clad Stress Mean and Standard Deviation is based on proprietary information from BWRVIP-05.

The fracture toughness is represented as follows [14, page 30]:

K= 36.2 + 49.4exp(0.0104(T-RTndt)) T-RTndt _<50'F (1) 55.1 + 28exp(0.0214(T-RTndt)) T-RTndt > 50'F where: KIc = fracture toughness for crack initiation ksi uin T = metal temperature at postulated crack tip (OF)

RTndt = reference temperature of nil ductility transition for unirradiated material.

Time to stress corrosion initiation and growth is determined with proprietary method. See BWRVIP-05.

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The applied loading includes an axial pressure stress of 10.69 ksi and a hoop stress of 21.39 ksi, both of which are due to an operating pressure of 1,025 psi. Both values are calculated using thin-wall cylinder pressure stress equations, using the outer radius of the vessel. Residual stress [1] is expressed as a 3rd polynomial as follow:

Residual stress is determined by proprietary method. See BWRVIP-05.

8.0 ANALYSES From the inspection coverage in Table 1, the anticipated overall percentage of the weld length for the beltline axial welds inspected during future outages is calculated to be:

% overall inspected = 90.0% (lower bound used)

Based on the average inspection coverage, the following cases were analyzed for the beltline axial and circumferential welds:

  • A baseline case of 90% (which equates to "essentially 100%") inspection coverage for the beltline axial welds, with fluence corresponding to 54 EFPY.
  • A baseline case of 90% ("essentially 100%") inspection coverage for the beltline circumferential weld, with fluence corresponding 54 EFPY.
  • 0% inspection coverage for the beltline circumferential weld, with fluence at 54 EFPY.

The analyses were performed using the COMBINED inspection probability of detection (PoD) curves in VIPER. The "COMBINED" inspection PoD applies for an inspection using a combination of different inspection techniques.

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The probability of occurrence for an LTOP event is 1 x 10-3 / year [10].

The analyses were performed using VIPERXP developed by Structural Integrity [2, 3].

9.0 RESULTS OF ANALYSIS Table 5 presents the PoF results for 60 years (54 EFPY) for the RPV beltline axial welds and the beltline circumferential weld, including the consideration of the LTOP occurrence probability of 1xl0-3 per year. The PoF for the beltline circumferential weld due to an LTOP event is 1.5x10-9 at 60 years (54 EFPY) and 2.5x10l" per year (see Table 6). The 1.5x10"9 value is less than the value of 1.78x10-5 for the CB&I plant in Reference [10, Table 2.6-5]. The 1.78x10-5 value reported in Reference [10, Table 2.6-5] is for 64 EFPY. The equivalent value to have a one to one comparison with the value determined in this calculation would be for 54 EFPY. Using the value of 2.0xl 0-7

[10, Table 2.6-4] for 32 EFPY and interpolating to determine the 54 EFPY value yields a result of 1.23x10-5. The 1.5x10-9 value is less than the interpolated value of 1.23x10-5 for the CB&I plant determined from Reference [10, Tables 2.6-4 and 2.6-5]. The difference between the two inspection coverage cases (0% and 90%) at the circumferential weld is 5.0xl 0-11 probability of failure event per year. This difference is less than the lxl0-6 per year requirement as specified in Regulatory Guide 1.174 [11].

The probability of failure event for the beltline axial welds due to an LTOP event is 2.24x 10-7 at 60 years (54 EFPY) and 3.74x 10- 9 per year (see Table 6) for 90% inspection.

10.0 CONCLUSION

S It is shown that the probability of failure for both 0% and 90% inspection coverage for the DAEC beltline circumferential weld remains essentially the same. These results justify the elimination of the RPV circumferential weld examination in the vessel beltline region to the end of the extended period of operation (60 years or 54 EFPY), since the probability of failure for both 0% and 90%

inspection coverage is approximately the same. The probability of failure for the circumferential welds is below that calculated in Reference [10], further justifying the elimination of the RPV circumferential weld examination in the vessel beltline region to the end of the extended period of operation (60 years of 54 EFPY). The DAEC inspection coverage on axial welds satisfies ASME Code requirements. The probability of failure per reactor year for the axial welds shown in Table 6 is well below the probability of 5x 10-6 quoted in Reference [15].

3 The 3.74x 10 9 probability for axial weld failure in Table 6 includes an LTOP frequency of 1x10- per year.

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11.0 REFERENCES

1. EPRI Report No. TR-105697, "BWR Reactor Pressure Vessel Shell Weld Inspection Recommendations (BWRVIP-05)," September 1995, EPRI PROPRIETARY, SI File No.

BWRVIP-01-205P.

2. Structural Integrity Associates Calculation No. DAEC-20Q-350, Revision 0, "Verification of VIPER Version 1.2 program for Microsoft Operation System Windows XP, a project specific version of VIPER Version 1.2," 10/26/2002.
3. VIPER Version 1.2, Structural Integrity Associates Inc. 1/5/98.
4. Duane Arnold Energy Center, IES Utilities, Inc., Drawings:
a. Drawing No. VS-01-41, Revision 1, "Vessel Shell Ring Layout," December 1994, SI File No. DAEC-20Q-224.
b. Drawing No. VS-01-01A, Revision 2, "Reactor Vessel Welds," December 1997, SI File No. DAEC-20Q-224.
5. "Non-Proprietary Version of Duane Arnold Energy Center Reactor Pressure Vessel Fluence Evaluation at 32 EFPY and 54 EFPY," TransWare Enterprises Report No. FPL-FLU-00 I -R-004, Revision 0, January 2008, SI File No. DAEC-20Q-243.
6. "Technical Letter Report on Third 10-Year Interval Inservice Inspection Requests For Relief For IES Utilities, Inc. Duane Arnold Energy Center Docket Number: 50-331," SI File No.

DAEC-20Q-239.

7. Structural Integrity Associates Calculation No. DAEC-20Q-324, Revision 1, "ARTNDT and ART Evaluation."
8. GE Report No. GE-NE-A22-00100-08-0 l-R2, Revision 2, "Pressure-Temperature Curves for Duane Arnold Energy Center, (Non-Proprietary Version)," August 2003, SI File No. DAEC-20Q-201.
9. APED-A41-003, Revision 2, 11/7/2005, GE Drawing No. 729E762, "Reactor Thermal Cycles," SI File No. DAEC-20Q-203.
10. Safety Evaluation Report, "Final Safety Evaluation of the BWR Vessel and Internals Project BWRVIP-05 Report (TAC No. M93925)," Office of Nuclear Reactor Regulation, July, 1998.

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11. United States Nuclear Regulatory Agency, Regulatory Guide 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant Specific Changes to the Licensing Basis."
12. Attachment D to APED-B 11-232, Revision 3, "Stress Report, 183" BWR Vessel, Duane Arnold Energy Center, Iowa Electric Light and Power Co. CBIN Contract No. 68-2967, GE Purchase Order #205-Hl289," VPF #2655-330-1, 8/28/72, SI File No. DAEC-20Q-207P (Note.- Although this reference has a proprietaryfile number associatedwith it, this attachment is non-proprietary).
13. FPL Energy Duane Arnold, LLC Document Number NG-08-0078, "Transmittal of Comments and List of Documents Regarding DAEC-20Q-338," SI File No. DAEC-20Q-200.
14. NUREG/CR-4486, "VISA-II - A Computer Code for Predicting the Probability of Reactor Pressure Vessel Failure."
15. Supplement to Final Safety Evaluation, "Supplement to Final Safety Evaluation of the BWR Vessel and Internals Project BWRVIP-05 Report (TAC No. MA3395)," United States Nuclear Regulatory Commission, March 7, 2000, S1 File No. BWRVIP-01-205P.

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Table 1: Axial Inspection Coverage Results [6, Table NDE-RO01]

2007 RFO ID 2005 RFO ID 1996 RFO14 OD Weld examination Percent examination Percent examination Percent Identification Coverage [13] Coverage [13] Coverage

[6, Table NDE-R0011 El (VLB-A2) No Exam 90.4 95.8 E2 (VLB-AI) No Exam 90.8 95.4 DI (VLA-A1) 90.8 No Exam 96.6 D2 (VLA-A2) 91.5 No Exam 96.7 Table 2: Peak Neutron Fluence for Energy > 1.0 MeV for DAEC RPV Weld and Shell Locations at the Inner Surface [5]

32 EFPY 54 EFPY Weld/Nozzle/Shell Location Elevation Peak Fluence Elevation Peak Fluence

[cm (in)] (n/crn) [cm (in)] (n/cm 2)

Peak Weld - Weld El/E2 753.43 735.65 6.29E+18 (500 azimuth) (296.63) (289.63)

Peak Nozzle - Nozzle 1 N16A 883.92 883.92 2.89E+18 (400 azimuth) (348.00) (348.00)

Peak Shell (40.6076

- Shell 2 736.44767.1E8 (40 azimuth for 32 EFPY; (293.94) 4.27E+18 (289.94) 7.51E+18 50 azimuth for 54 EFPY)

1) Value corresponds to peak value around vessel cutout for nozzle, elevation is nozzle centerline.

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Table 3: Maximum > 1.0 MeV Neutron Fluence in DAEC RPV Axial and Circumferential Welds [5]

Shell 32 EFPY Fluence (n/cm 2 ) 54 EFPY Fluence (nlcn9)

Location Weld Azimuth (Degrees) OT at Weld OT at Weld D1 54 2.62E+18 4.90E+18 Shell Ring 1 D2 234 2.62E+18 4.90E+18 El 310 3.50E+18 6.29E+18 Shell Ring 2 E2 130 3.50E+18 6.29E+18 F1 67.5 4.55E+16 8.81E+16 Shell Ring 3 F2 247.5 4.55E+16 8.81E+16 Shell Weld Elevation [cm (in)] 32 EFPY Fluence (n/cm 2) 54 EFPY Fluence (nlcm 2)

Location OT at Weld OT at Weld Shell 1-2 DE 606.1075 (238.625) 3.28E+1 8 5.85E+18 Shell 2-3 EF 977.265 (384.75) 4.83E+16 9.31 E+ 16 File No.: DAEC-20Q-338 Page 12 of 15 Revision: 0 F0306-OIRO

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Table 4: Weld Chemistries and ART Values for 54 EFPY [7]

C6439-2 0.090 0.510 58.00 45.02 17.00 0.00 119.0 40 CI 1-19 B0402-1 40 0.130 0.470 87.10 67.61 17.00 0.00 141.6 0.1 Shell Ring #2 1-20 B0436-2 10 0.150 0.640 111.00 93.78 17.00 0.00 137.8 D1,D2 432Z4521 Lot B020A27A -50 0.010 0.980 20.00 14.57 7.29 0.00 -20.9 D1 ,D2 432Z0471 Lot B003A27A -50 0.030 0.910 41.00 29.87 14.94 0.00 9.7 Lower-Intermediate ElE2 432Z4521 Lot B020A27A -50 0.010 0.980 20.00 15.92 7.96 0.00 -18.2 E1,E2 432Z0471 Lot B003A27A -50 0.030 0.910 41.00 32.64 16.32 0.00 15.3 Girth DE 09L853 Lot L017A27A -50 0.030 0.880 41.00 31.83 15.91 0.00 13.7 DE 1 ng Lot K004A27A -50 0.030 41.00 31.83 15.91 0.00 13.7 0

Z 1-18 4.469 1.117 5.85E+18 0.765 4.47E+18 0.7762 1-19 4.469 1.117 5.85E+18 0.765 4.47E+18 0.7762 Shell Ring #2 1-20 4.469 1.117 7.51E+18 0.765 5.74E+18 0.8448 1-21 4.469 1.117 7.51E+18 0.765 5.74E+18 0.8448 Lower D1,D2 4.469 1.117 4.90E+18 0.765 3.75E+18 0.7286 D1,D2 4.469 1.117 4.90E+18 0.765 3.75E+18 0.7286 Lower-Intermediate EL E 1,E2 4.469 1.117 6.29E+18 0.765 4.81E+18 0.7960 E1,E2 4.469 1.117 6.29E+18 0.765 4.81E+18 0.7960 Girth DE 4.469 1.117 5.85E+18 0.765 4.47E+18 0.7762 DE 4.469 1.117 5.85E+18 0.765 4.47E+18 0.7762 DE 4.469 1.117 5.85E+18 0.765 4.47E+18 0.7762 Nozzle N16 4.469 1.117 2.89E+18 0.765 2.21E+18 0.5936 Nozzle N2 4.469 1.117 6.82E+17 0.765 5.22E+17 0.2995 (a) Material in the surveillance program with adjusted CF in accordance with Reference [6].

(b) Estimated copper in accordance with Reference [4].

(c) Best-estimate nickel from all available data in Reference [6].

(d) CF values do not include the ratio procedures adjustments in RVID [5]. These adjustments are not required by RG1.99, R2 [1].

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Table 5: Probability of Failure Due to LTOP Event Per 60 Years PoF per 60 years PoF per 60 years (54 EFPY) for (54 EFPY) for Circumferential Weld Number of Axial Welds Simulations

.90% 0% 90%

Peak 10 Million Fluence at 2.24x10_7 1.5xl0 9 1.8xl0.9 60 years (54 EFPY)

Note: The results include a probability of LTOP Event =1 x 10- /year, [10]. Also, note that for the circumferential weld at peak fluence only, PoF per 60 years for 90% inspection is greater than PoF at 0%. This is not unexpected, as it falls within the uncertainties in the probabilistic fracture mechanics evaluation.

Table 6: Probability of Failure Due to LTOP Event Per Year PoF per year for Circumferential PoF per year for Axial Welds Wl Weld Number of Simulations 90% 0% 90%

Peak 10 Million Fluence at 3.74x10-9 2.5xl0.1 3.0x10 11 60 years (54 EFPY)

Difference between the two inspection Only one case was run so there is no 5.0xl0."

coverage cases comparison to report.

3 T- -r..... - I-.....L . -- rn r ....-- 1 .l- .... r--------------------... .- 1 IN ote: Ine results include a probaobiity o LI.UF tEvent = I x 10 /year LiUJ. Also, note mat ior me circumferential weld at peak fluence only, PoF per 60 years for 90% inspection is greater than PoF at 0%. This is not unexpected, as it falls within the uncertainties in the probabilistic fracture mechanics evaluation.

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HC -82 TOP HEAt DOLLA* PLATE 180 160 140 120 100 80 60 40 20 0 340 320 300 280 260 240 220 200 1l0 OAF N38 N3A (MBB-01) IMHA-01) 1 30 CHSD"0D M-OV NX (VIE-Ol EI(VC-Dl)

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______VZ8-I4) ISHEELL NO.4 N11. NLIB N413(J NQ dIAt) N40dV1--D FF40 OCA-01 @, -A (CSID°0 (FFFB-IF4 ) N) I!O=)

0 9 384A _VCS-23) SHELL KU0. 3 (V-E-Oi (VIF-hl-l 00EF 0 0

  • ?. NC NA 0 IWH0 * .4' 6FN* PATCHES El13 - E3EAMINED 238_ flCS-AZ SHELL NO.2 M20 F20 N129 2A 124 1O2T N2D WIE cRRD-O iJ RRO-Ol) iRRB-0TI) IRRA-Ol) (CRH1-Oil (55-Oil 15SF-iL) IRAE-DIl

@ @ @ lEN-IC) @ @

21 505-1) D (0 APO-O OUTSIDE VIEW OF THE FM' SHOWING SCHEMATIC ARRANGOEMNT OF VESSELPLATESANDWELDS Figure 1: DAEC RPV Shell Weld Locations and Identifications [4]

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APPENDIX A:

LISTING OF COMPUTER INPUT AND OUTPUT FILES Note: The files includedin the attachedlisting are providedin the computerfiles associatedwith this calculation.

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Filename Description Peak Fluence Case Axlp90fv.inp Axial Welds with Normal Peak Fluence at 54 EFPY with 90% Inspection Input File.

CirpOfv.inp Circumferential Weld with Normal Peak Fluence at 54 EFPY with 0% Inspection Input File.

Cirp90fv.inp Circumferential Weld with Normal Peak Fluence at 54 EFPY with 90% Inspection Input File.

Axlp90fv.out Axial Welds with Normal Peak Fluence at 54 EFPY with 90% Inspection Output File.

Cirp0fv.out Circumferential Weld with Normal Peak Fluence at 54 EFPY with 0% Inspection Output File.

Cirp90fv.out Circumferential Weld with Normal Peak Fluence at 54 EFPY with 90% Inspection Output File.

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Enclosure 3 to NG-09-0663 Change to LRA Table 3.2.2-2 Regarding Stainless Steel Bolting NRC Request In a telephone conference call on October 2, 2009, the NRC questioned whether the High Pressure Coolant Injection (HPCI) System contained stainless steel bolts subject to aging management review. Two vent valves, V23-0078 and V23-0079, HPCI suction line inboard and outboard vent valves, have been identified as having stainless steel bolting.

DAEC Response For completeness, stainless steel bolting is being added to LRA Table 3.2.2-2, as follows.

In LRA Table 3.2.2-2, Summary of Aging Management Review Results High Pressure Coolant Injection System, on page 3.2-41, the following new line item is added:

Component Intended Material Environment Aging Effect Aging NUREG- Table Notes Type Function Requiring Management 1801 3.X.1 Management Program Volume 2 item line Item Fasteners, Pressure Stainless Air - indoor Loss of Bolting F, bolts, boundary steel uncontrolled preload Integrity 207 washers, (external) Program nuts Page 1 of 1

Enclosure 4 to NG-09-0663 Duane Arnold Energy Center License Renewal Application Updated LRA Section 18.4, Table A-I, Duane Arnold License Renewal Commitments TABLE A-1 DUANE ARNOLD LICENSE RENEWAL COMMITMENTS 1 Item System, Component or Commitment 2 Section Schedule No. Program Buried Piping and Tanks Implement Buried Piping and Tank Program. 18.1.7 Prior to the Inspection Program period of extended

[Revised in DAEC letter NG-09-0764 in response to New Program operation Commitments RAI]

2. BWR Vessel Internals Perform an EVT-1 inspection of 5% of the top guide locations. 18.1.14 Within six Program years of entering the period of extended operation
3. BWR Vessel Internals Perform an EVT-1 inspection of an additional 5% of the top guide 18.1.14 Within 12 Program locations. years of entering the period of extended operation
4. Electrical Cables and Implement an Electrical Cables and Connections Program and 18.1.17 Prior to the Connections Program complete the first inspection prior to the period of extended period of operation. extended operation

[Revised in DAEC letter NG-09-0764 in response to New Program Commitments RAI]

Page 1 of 12

Enclosure 4 to NG-09-0663 Duane Arnold Energy Center License Renewal Application Updated LRA Section 18.4, Table A-I, Duane Arnold License Renewal Commitments TABLE A-1 DUANE ARNOLD LICENSE RENEWAL COMMITMENTS 1 Item System, Component or Commitment2 Section Schedule No. Program

5. Electrical Cables and Implement an Electrical Cables and Connections Used in 18.1.18 Prior to the Connections Used in Instrumentation Circuits Program and complete the first inspection period of Instrumentation Circuits prior to the period of extended operation. extended Program [Revised in DAEC letter NG-09-0764 in response to New Program operation Commitments RAI]
6. Electrical Connections Implement an Electrical Connections Program and complete the 18.1.19 Prior to the Program one time inspection prior to the period of extended operation. period of extended

[Revised in DAEC letter NG-09-0764 in response to New Program operation Commitments RAI]

7. Electrical Penetration Implement an Electrical Penetration Assemblies Program. 18.1.20 Prior to the Assemblies Program period of

[Revised in DAEC letter NG-09-0764 in response to new Program extended Commitments RAI] operation

8. External Surfaces Revise the inspection program to address inspector qualifications, 18.1.21 Prior to the Monitoring Program types of components, degradation mechanisms, aging effects, period of acceptance criteria, and inspection frequency. extended operation
9. Fire Protection Program Revise program to include criteria for visual inspection of fire 18.1.22 Prior to the barriers, walls, ceilings, and floors to examine for signs of age period of related degradation. extended operation Page 2 of 12

Enclosure 4 to NG-09-0663 Duane Arnold Energy Center License Renewal Application Updated LRA Section 18.4, Table A-I, Duane Arnold License Renewal Commitments TABLE A-1 DUANE ARNOLD LICENSE RENEWAL COMMITMENTS 1 Item System, Component or Commitment 2 Section Schedule No. Program

10. Fire Protection Program Enhance procedures to inspect the entire diesel driven fire pump 18.1.22 Prior to the fuel supply line for age related degradation. period of extended operation
11. Fire Water System Implement maintenance activities to perform volumetric 18.1.23 Prior to the Program examinations for pipe wall thinning of fire protection piping period of periodically during the period of extended operation. extended

[Revised in DAEC letter NG-09-0764 in response to New Program operation Commitments RAI]

12. Fire Water System Enhance procedures to include NFPA 25 criteria for sprinklers 18.1.23 Prior to the Program regarding replacing or testing. period of extended operation
13. Fire Water System Enhance procedures to perform visual inspection of fire hydrants 18.1.23 Prior to the Program annually. period of extended operation
14. Fuel Oil Chemistry Revise the program to require particulate testing of fuel oil 18.1.25 Prior to the Program samples from the diesel fire pump day tank. period of extended operation Page 3 of 12

Enclosure 4 to NG-09-0663 Duane Arnold Energy Center License Renewal Application Updated LRA Section 18.4, Table A-I, Duane Arnold License Renewal Commitments TABLE A-1 DUANE ARNOLD LICENSE RENEWAL COMMITMENTS 1 Item System, Component or Commitment 2 Section Schedule No. Program

15. Fuel Oil Chemistry Enhance procedures to require sampling and testing of new fuel 18.1.25 Prior to the Program oil delivered to the diesel fire pump day tank; and to require that period of purchase orders and sampling procedures for diesel fuel extended delivered to and stored in the diesel fire pump day tank prohibit operation the delivery and use of biodiesel fuel.

[Revised in letter NG-09-0764 in response to RAI B.3.25-1]

16. Fuel Oil Chemistry Enhance procedures to perform periodic (10 year) draining, 18.1.25 Prior to the Program cleaning and visual inspection of the diesel fuel oil day tanks, period of diesel fire pump day tank, and diesel driven air start air extended compressor fuel oil tanks. operation

[Revised in letter NG-09-0764 in response to RAI B.3.25-4]

17. Fuel Oil Chemistry Implement procedures to require bottom thickness testing of the 18.1.25 Prior to the Program Standby Diesel Generator Day Tanks and the Diesel Fire Pump period of Day Tank. extended operation

[Revised in DAEC letter NG-09-0764 in response to New Program Commitments RAI]

18. Fuse Holders Program Implement a Fuse Holders Program and complete the first test 18.1.26 Prior to the prior to the period of extended operation. period of extended operation

[Revised in DAEC letter NG-09-0764 in response to RAI B.3.26-1 RAI]

and New Program Commitments Page 4 of 12

Enclosure 4 to NG-09-0663 Duane Arnold Energy Center License Renewal Application Updated LRA Section 18.4, Table A-I, Duane Arnold License Renewal Commitments TABLE A-1 DUANE ARNOLD LICENSE RENEWAL COMMITMENTS 1 Item System, Component or Commitment 2 Section Schedule No. Program

19. Inaccessible Medium Implement an Inaccessible Medium Voltage Cable Program and 18.1.27 Prior to the Voltage Cable Program complete the first inspection or test prior to the period of extended period of operation. extended

[Revised in DAEC letter NG-09-0764 in response to New Program operation Commitments RAI]

20. Inspection of Internal Implement an Inspection of Internal Surfaces in Miscellaneous 18.1.28 Prior to the Surfaces in Miscellaneous Piping and Ducting Components Program. period of Piping and Ducting Components extended Program [Revised in DAEC letter NG-09-0764 in response to New Program operation Commitments RAI]
21. Inspection of Overhead Enhance procedures to monitor for corrosion and wear of the 18.1.29 Prior to the Heavy Load and Light supporting steel and rails. period of Load (Related to extended Refueling) Handling operation Systems Program
22. Inspection of Overhead Enhance procedures to record usage of the reactor building and 18.1.29 Prior to the Heavy Load and Light turbine building cranes. period of Load (Related to extended Refueling) Handling operation Systems Program Page 5 of 12

Enclosure 4 to NG-09-0663 Duane Arnold Energy Center License Renewal Application Updated LRA Section 18.4, Table A-I, Duane Arnold License Renewal Commitments TABLE A-1 DUANE ARNOLD LICENSE RENEWAL COMMITMENTS 1 Item System, Component or Commitment 2 Section Schedule No. Program

23. Lubricating Oil Analysis Enhance procedures to include diesel fire pump. 18.1.30 Prior to the Program period of extended operation
24. Metal Enclosed Bus Implement a Metal Enclosed Bus Program and complete the first 18.1.31 Prior to the Program inspection prior to the period of extended operation. extended

[Revised in DAEC letter NG-09-0764 in response to New Program operation Commitments RAI]

25. One-Time Inspection Implement a One-Time Inspection Program and complete the 18.1.32 Prior to the Program one-time inspections prior to the period of extended operation. period of extended

[Revised in DAEC letter NG-09-0764 in response to New Program operation Commitments RAI]

26. Reactor Vessel Implement a procedure to evaluate the BWRVIP ISP data as it 18.1.35 Prior to the Surveillance Program becomes available, period of extended operation

[Revised in DAEC letter NG-09-0764 in response to New Program Commitments RAI]

Page 6 of 12

Enclosure 4 to NG-09-0663 Duane Arnold Energy Center License Renewal Application Updated LRA Section 18.4, Table A-I, Duane Arnold License Renewal Commitments TABLE A-1 DUANE ARNOLD LICENSE RENEWAL COMMITMENTS 1 Item System, Component or Commitment 2 Section Schedule No. Program

27. Reactor Vessel Revise the Reactor Vessel Surveillance Program to implement 18.1.35 Prior to the Surveillance Program the recommendations of BWRVIP-1 16 BWR Vessel and Internals period of BWRVIP-74-A BWR PRV Project Integrated Surveillance Program Implementation for extended License Renewal. operation Inspection and Flaw Evaluation Guidelines for License Renewal
28. Reactor Vessel Implement BWRVIP-116 with the conditions documented in 18.1.35 Prior to the Surveillance Program Sections 3 and 4 of the NRC Staffs SE dated March 1, 2006 period of for BWRVIP-1 16, including the following: extended operation 0 NRC approval will be obtained for any change in the withdrawal schedules of the DAEC Reactor Vessel surveillance capsules.

0 If a standby capsule is removed from the DAEC Reactor Vessel without the intent to test it, the capsule will be stored in a manner which maintains it in a condition which would permit its future use, including during the period of extended operation, if necessary.

[Revised in DAEC letter NG-09-0663 in response to RAI. B.3.35-1]

Page 7 of 12

Enclosure 4 to NG-09-0663 Duane Arnold Energy Center License Renewal Application Updated LRA Section 18.4, Table A-I, Duane Arnold License Renewal Commitments TABLE A-1 DUANE ARNOLD LICENSE RENEWAL COMMITMENTS 1 Item System, Component or Commitment 2 Section Schedule No. Program

29. Selective Leaching of Implement and complete a program to include one-time visual 18.1.36 Prior to the Materials Program inspection and hardness measurement of selected components period of susceptible to selective leaching. extended operation

[Revised in DAEC letter NG-09-0764 in response to New Program Commitments RAI]

30. Structures Monitoring Enhance procedures to include structures and structural 18.1.37 Prior to the Program components not currently in Maintenance Rule Program. period of extended operation
31. Structures Monitoring Enhance procedures to include periodic sampling of groundwater 18.1.37 Prior to the Program for pH, chloride and sulfate concentration on a 10 year periodicity. period of extended operation
32. Structures Monitoring Enhance procedures to include a elastomer inspection to prevent 18.1.37 Prior to the Program leakage through containment penetration. period of extended operation
33. Structures Monitoring Enhance procedures to include a requirement to contact the 18.1.37 Prior to the Program proper personnel to allow opportunistic inspection of the buried period of concrete foundation. extended operation Page 8 of 12

Enclosure 4 to NG-09-0663 Duane Arnold Energy Center License Renewal Application Updated LRA Section 18.4, Table A-I, Duane Arnold License Renewal Commitments TABLE A-1 DUANE ARNOLD LICENSE RENEWAL COMMITMENTS 1 Item System, Component or Commitment 2 Section Schedule No. Program

34. Structures Monitoring Enhance procedures to include opportunistic inspections of the 18.1.37 Prior to the Program buried concrete foundation on a 10 year periodicity. period of extended operation
35. Metal Fatigue of Reactor Enhance procedures to incorporate the requirements of 18.2.2 Prior to the Vessel Coolant Pressure NUREG/CR-6260 locations into the implementing procedures. period of Boundary Program extended operation
36. Thermal Aging and Implement a Thermal Aging and Neutron Irradiation Embrittlement 18.1.38 Prior to the Neutron Irradiation of Cast Austenitic Stainless Steel (CASS) Program. period of Embrittlement of Cast . extended Austenitic Stainless Steel [Revised in DAEC letter NG-09-0764 in response to New Program operation Auseniic tailes Stel Commitment RAI]oprtn (CASS) Program
37. BWR Vessel Internals Inspect a sample of the rim hold-down bolts by VT-3 until an 18.1.14 Prior to the Program expanded technical basis for not inspecting is approved by the period of NRC. extended operation
38. Reactor Vessel Submit a relief request to address the frequency requirements of 18.3.1.4 Prior to the Circumferential Weld TLAA the inservice inspection of the RPV circumferential welds. period of (BWRVI P-05) extended operation Page 9 of 12

Enclosure 4 to NG-09-0663 Duane Arnold Energy Center License Renewal Application Updated LRA Section 18.4, Table A-I, Duane Arnold License Renewal Commitments TABLE A-1 DUANE ARNOLD LICENSE RENEWAL COMMITMENTS 1 Item System, Component or Commitment 2 Section Schedule No. Program

39. Quality Assurance Expand the scope of its 10 CFR Part 50, Appendix B Quality UFSAR Prior to the Program (Corrective Assurance program to include non-safety-related structures and 17.1.2 period of Action, Confirmation components subject to an AMR for license renewal. extended Process, Administrative operation Controls)
40. Operating Experience Perform an operating experience review of extended power Prior to the uprate and its impact on aging management programs for period of systems, structures, and components (SSCs) before entering the extended period of extended operation. operation
41. Bolting Integrity Program Revise the implementing procedures for the ASME Section XI 18.1.6 Prior to the Inservice Inspection Subsections IWB, IWC, and IWD Program; period of ASME Section Xl Inservice Inspection, Subsection IWF Program; extended External Surfaces Monitoring Program; Structural Monitoring operation Program; and Buried Piping and Tanks Program such that they specifically address the inspection of fasteners (bolting, washers, nuts, etc.) for signs of leakage, corrosion/loss of material, cracking, and loss of preload/loss of prestress, as applicable.

[Added in letter NG-09-0764 in response to RAI B.3.6-02]

Page 10 of 12

Enclosure 4 to NG-09-0663 Duane Arnold Energy Center License Renewal Application Updated LRA Section 18.4, Table A-I, Duane Arnold License Renewal Commitments TABLE A-1 DUANE ARNOLD LICENSE RENEWAL COMMITMENTS 1 Item System, Component or Commitment 2 Section Schedule No. Program

42. BWR Penetrations The implementing document for the BWR Penetrations Program 18.1.10 Prior to the Program will be revised to specify that guidance in BWRVIP-14, -59 and - period of 60 is to be considered in the'evaluation of crack growth in extended stainless steel, nickel alloys and low-alloy steels, respectively, operation when flaws are identified and evaluation required.

[Added in letter NG-09-0764 in response to RAI B.3.10-5]

43. Fire Protection Program DAEC Fire Barrier Penetration Seal Inspection Surveillance shall 18.1.22 Prior to the be enhanced to require at least 10 percent of each type of seal to period of be inspected each refueling cycle, extended

[Added in letter NG-09-0764 in response to RAI B.3.22-1] operation

44. Fire Protection Program The DAEC Cardox System annual operability test shall be 18.1.22 Prior to the enhanced to include an inspection for corrosion and mechanical period of damage. extended

[Added in letter NG-09-0764 in response to RAI B.3.22-1] operation

45. ASME Class 1 Small-bore Implement an ASME Code Class 1 Small-bore Piping Inspection 18.1.40 Prior to the Piping Inspection Program Program. period of

[Added in letter NG-09-0764 in response to RAI B.3.3-2] extended operation Page 11 of 12

Enclosure 4 to NG-09-0663 Duane Arnold Energy Center License Renewal Application Updated LRA Section 18.4, Table A-I, Duane Arnold License Renewal Commitments TABLE A-1 DUANE ARNOLD LICENSE RENEWAL COMMITMENTS 1 Item System, Component or Commitment 2 Section Schedule No. Program

46. BWR Vessel Internals The BWR Vessel Internals Program will incorporate the crack 18.1.14 Prior to the Program growth rate evaluations specified in the BWRVIP-100-A report. period of Plant-specific inspection intervals will be developed for DAEC extended core shroud welds that are exposed to a neutron fluence value operation equal to or greater than 1 X 1021 n/cm 2 (E > 1 MeV), as needed.

[Added in letter NG-09-0663 in response to RAI B.3.14-5]

47. Reactor Internals DAEC will submit an analysis for loss of preload in core plate 18.3.1.7 Two years hold-down bolts due to stress relaxation to the NRC for Staff prior to review. The analysis will use projected neutron fluence values for entering the the end of the period of extended operation. The analysis will be period of submitted 2 years prior to entering the period of extended extended operation. operation

[Added in letter NG-09-0663 in response to RAI 4.2.7-1]

1 2Table In the is updated to reflect DAEC correspondence through 10/23/2009 table, the term "implement" means that the program is described in an approved procedure or other approved formal document; the test, inspection or monitoring procedure has been developed and approved; and the first test, inspection or monitoring activity has been scheduled.

Page 12 of 12

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