Text

Relief Request Reactor Pressure Vessel Stud HNP-ISI-RR-05-02
	ML18309A272
Person / Time
Site:	Hatch
Issue date:	11/05/2018
From:	Gayheart C; Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NL-18-1336, RR-HNP-ISI-RR-05-02
	Download: ML18309A272 (47)
	v • d • e

A Southern Nuclear Cheryl A. Gayheart Regulatory Aflairs Director 3535 Colonnade Parkway Birmingham, AL 35243 205 992 5316 tel 205 992 7795 lax NOV 0 5 2018 cag.tyh~a @ south .:mco.com Docket No.: 50-366 NL-18-1336 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant- Unit 2 Relief Request Reactor Pressure Vessel Stud HNP-ISI-RR-05-02 Ladies and Gentlemen:

Pursuant to 10 CFR 50.55a(g)(5)(iii), Southern Nuclear Operating Company (SNC) hereby requests Nuclear Regulatory Commission (NRC) approval of proposed Relief Request HNP-ISI-RR-05-02. This Relief Request will allow Hatch Nuclear Plant (HNP) Unit 2 to continue operation with a flaw indication on one reactor pressure vessel (RPV) stud. provides proposed Relief Request HNP-ISI-RR-05-02. Enclosure 2 provides the Dominion Engineering, Inc. (DEl) evaluation report supporting continued operation.

This letter contains no NRC commitments. If you have any questions, please contact Jamie Coleman at 205.992.6611.

Respectfully submitted, CAG/RMJ

Enclosures:

1. Proposed Relief Request HNP-ISI-RR-05-02

2. Dominion Engineering, Inc. (DEl) Evaluation Cc: Regional Administrator, Region II NRR Project Manager- Hatch Senior Resident Inspector- Hatch RTYPE: CHA02.004

Edwin I. Hatch Nuclear Plant - Unit 2 Relief Request Reactor Pressure Vessel Stud HNP-ISI-RR-05-02 Enclosure 1 Proposed Relief Request HNP-ISI-RR-05-02 to NL-18-1336 Proposed Relief Request HNP-ISI-RR-05-02

1. ASME Code Component(s) Affected Code Class: ASME Section XI Code Class 1 Component Numbers: Not Applicable Code

References:

ASME Section XI, 2007 Edition through 2008 Addenda, IWB-3515.2 Examination Category: 8-G-1 Pressure Retaining Bolting Greater Than 2 in. (50.8 mm) in Examination Area:

Diameter Item Number(s): 86.20

2. Requested Date for Approval Approval is requested prior to the completion of the Unit 2 refueling outage, which begins February 4, 2019.

3. Applicable ASME Code Requirements ASME Section XI, 2007 Edition through 2008 Addenda, IWA-3515.2(c) Allowable flaws for Volumetric Examination of Studs and Bolts The 2007 Edition through 2008 addenda of ASME Section XI, IWB-3515.2(c) states: "Any flaw detected by volumetric examination shall be investigated by a surface examination. If confirmed to be a surface flaw, the standards of IWB-3515.1 shall apply. If not a surface flaw, the standards of IWB-3515.2(a) and (b) shall apply.

4. Reason for Request

A flaw indication was found on a Reactor Pressure Vessel (RPV) Stud during a code required volumetric examination during the spring 2017 refueling outage at the Edwin I.

Hatch Nuclear Plant Unit 2 (hereinafter referred to as HNP2). The examination was completed in accordance with Table IWB-2500-1, examination category 8-G-1, and met the examination volume requirements of Figure IWB-2500-12. During the lnservice Inspection (lSI) of the HNP2 RPV Studs {#1 through #56), a circumferential flaw indication was identified in the RPV stud at location #33. The indication is located at a distance of 41.7 inches from the top of RPV Stud. This correlates to just below or at the surface of the reactor vessel flange. The indication is approximately one inch {1") in length. Qualified Personnel and Procedures (to the requirements of 10 CFR 50 Appendix VIII) were utilized to perform the ultrasonic examination using a oobeam angle (scanned from the top of the stud) to identify any/all abnormalities. Currently, there are no Appendix VIII Qualified Techniques available to size the indication in the RPV Stud.

In accordance with IWB-3515.2(c), flaws detected by volumetric examination shall be investigated by a surface examination. Due to the location of the flaw indication at or slightly below the reactor flange, removal of RPV Stud #33 is necessary to perform an ASME Section V, Mandatory Appendix 6 (Liquid Penetrant) or Mandatory Appendix 7 (Magnetic Particle) Surface Examination.

E1-1 to NL-18-1336 Proposed Relief Request HNP-ISI-RR-05-02 After discovery, various attempts were made to remove the stud prior to flooding the reactor cavity for fuel movement and after draindown for vessel reassembly in 2R24. Two different methodologies (Basic Removal and Advanced Removal) were pursued to remove the stud.

The first attempt to remove the RPV Stud utilized the "Basic Removal" Technique. This technique includes chasing the stud hole, applying an approved penetrant directly to the stud (includes soak time), installing a STAR adapter to the stud and attempting removal with an impact tool. The "Advanced Removal (Full STAR Tooling)" Technique was also utilized.

This technique includes installing an adapter plate, pumping an approved penetrant down the elongation hole and back up the threads, using a vibrator to agitate the stud (attached to the STAR Adaptor) prior to utilizing an impact tool to remove the stud. Both of these attempts were unsuccessful due to schedule limitations, preparation and planning inadequacies, and attempting to work with the reactor vessel head in place.

In the upcoming HNP2 outage (2R25), additional attempts will be made to remove the stud using the methods discussed above with enhancements to the tools, penetrant, and planning. A mockup and practice removal sessions will be utilized to identify best practices and processes to be implemented during the outage. Additionally, the site has scheduled adequate time for removal attempts with planned time after reactor vessel disassembly, to ensure that the head is not an obstruction (i.e. the RPV head is removed from the vessel),

and there is contingency for additional time during reassembly. If these attempts are unsuccessful, the stud would remain in place for the remainder of the current lSI Interval.

5. Proposed Relief Request and Basis for Use Proposed Relief Request Pursuant to 10 CFR 50.55a(g)(5)(iii), a relief request is requested on the basis that compliance to the specified requirements in the Code is impractical based on not being able to remove RPV stud #33. In the event stud removal is successful, this relief request will not be required.

Southern Nuclear Operating Company (SNC) requests relief from the surface examination requirement of IWB-3515.2(c) in the event that RPV Stud #33 cannot be removed for a code compliant surface examination. Attempts are scheduled and planned to remove RPV Stud #33 during refueling outage 2R25, using enhanced tooling and improved techniques. For Stud #33, ultrasonic examination of the stud will be conducted once per 10-year lSI Interval per Table IWB-2500-1, Category B-G-1, Item B6.20 and Figure 2500-12. To ensure that the flaw does not propagate into the surrounding flange, ultrasonic examination of the threads in the flange will be conducted per Table IWB-2500-1, Category B-G-1, Item B6.40, and Figure 2500-12, except the frequency of ultrasonic examination of the threads in the flange will be once per Inspection Period of the current 10-year lSI Interval in lieu of the code required frequency of once per Interval. Additionally, VT-1 examination of the flange will be conducted concurrently with the aforementioned ultrasonic examination (Item B6.40) of the flange once per Inspection Period for the current 10-year lSI Interval. VT-1 examination includes 1 inch annular surface of flange surrounding RPV stud #33.

Basis for Use An evaluation has been performed demonstrating that all applicable ASME Code allowable stresses (e.g., stud membrane and membrane plus bending stress, bearing stress, thread E1-2 to NL-18-1336 Proposed Relief Request HNP-ISI-RR-05-02 shear stress) are met with a single stud analytically assumed out of service, including subsequent operation with the expanded elongation tolerances previously developed for HNP2. The analysis considers the effects of both a single stud left de-tensioned and a stud that fails in service. This evaluation demonstrates that the structural and leakage integrity of the RPV Head Joint will be maintained if Stud #33 is not able to be removed to verify the stud structural integrity by a surface examination. Ultrasonic examinations will be performed in accordance with the requirements of Table IWB-2500-1, Category B-G-1, Items 86.20 and 86.40, except the frequency for ultrasonic examination for Item 86.40 (threads in the flange) will be conducted once per Inspection Period in lieu of once per Interval for the current 10-year lSI Interval. Additionally, VT -1 examination of the flange will be conducted concurrently with the aforementioned ultrasonic examination (86.40) of the flange once per Inspection Period for the current 10-year lSI Interval. VT-1 examination includes 1 inch annular surface of flange surrounding RPV stud #33. These will ensure that the flaw in the stud is monitored and that no flaw propagation into the surrounding flange occurs. Also a Class 1 System Leakage Test conducted before start up from each refueling outage, per Table IWB-2500-1 Category 8-P, will verify the integrity of the RPV Head Joint. The system leakage test pressure for Class 1 Systems shall correspond to rated PRV pressure (at least 1,045 psig) and be attained at a rate in accordance with the approved Pressure I Temperature Limit Curves and approved procedures. If the test pressure results in a temperature greater than 200°F, the pressure may be reduced. After the test conditions have been attained, the VT-2 Examination will be performed. During plant operation, the bleed off line between the double o-ring seal is monitored by a pressure switch with an annunciator in the control room. This allows for continued monitoring of the RPV Head Flange integrity.

Based on the above discussion, the requirement to remove RPV Stud #33 to perform the required surface examination (Liquid Penetrant or Magnetic Particle) represents an unusual difficulty. However, the inability to remove the stud in question does not adversely affect the design requirements of the RPV nor impose a decrease in the level of quality and safety of the HNP Unit 2 RPV.

6. Duration of Proposed Relief Request This proposed relief request is requested for the current lSI Interval, currently scheduled to end on 12/31/2025, if attempts to remove Stud #33 are unsuccessful in 2R25.

7. Precedents Edwin I. Hatch Nuclear Plant Letter, dated 2/17/17, to USNRC; Docket Nos. 50-366, "Relief Request Reactor Pressure Vessel Stud Inspection" and the associated NRC SER ML17205A345, dated 8/10/17.

E1-3

Edwin I. Hatch Nuclear Plant- Unit 2 Relief Request Reactor Pressure Vessel Stud HNP-ISI-RR-05-02 Enclosure 2 Dominion Engineering, Inc. (DEl) Evaluation

~

CALCULATION Dominion fnvineerin~

Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page 1 of 41 RECORD OF REVISIONS Prepared by Checked by Reviewed by Approved by Rev. Description Date Date Date Date 0 Original Issue S.c~J~~ f.C*'?r -r.c.~ 1. .f.~SJ

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J .E. Broussard T.C. Ligon T.C. Ligon D.J. Gross Principal Enltineer Engineer Engineer Principal Engineer The last revision number to reflect any changes for each section of the calculation is shown in the Table of Contents. The last revision numbers to reflect any changes for tables and figures are shown in the List of Tables and the List of Figures. Changes made in the latest revision, except for Rev. 0 and revisions which change the calculation in its entirety, are indicated by a double line in the right hand margin as shown here.

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Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page 2 of 41 TABLE OF CONTENTS Last Mod.

Section Page Rev.

1 PURPOSE ..................................................................................................................................... 5 0 2

SUMMARY

OF RESULTS ......................................................... ........................................................ 5 0 3 INPUT REQUIREMENTS .................................................................................................................. 5 0 4 ASSUMPTIONS ....................... ........................................................................................... ............ 6 0 5 ANALYSIS ....................... ...................................................... ...... .... ........................ ... ................... 7 0 5.1 Stud Primary Stress with One Stud Out of Service ......................................................... 7 0 5.1.1 Average Stud Force ............................................................ ............................. 8 0 5.1.2 Calculation of Stud Force Distribution .............................................................. 8 0 5.1.3 Primary Stress Comparison ........................................................................... 10 0 5.2 Analysis of Closure Flange with Stud Out of Service .................................................... 10 0 5.2.1 Evaluation Methodology ................................................................................. 10 0 5.2.2 Reactor Vessel Closure Flange Model ........................................................... 11 0 5.2.2.1 Model Geometry ......................................................................... 11 0 5.2.2.2 Model Boundary Conditions ....................................................... 12 0 5.2.3 Analysis Cases ............................................................................................... 12 0 5.2.4 Results Discussion ......................................................................................... 12 0 5.2.4.1 RPV Closure Stresses ................................................................ 13 0 5.2.4.2 RPV Stud Stresses ..................................................................... 13 0 5.2.4.3 RPV Closure Flange Separation .................. , ............................ 13 0 5.2.4.4 Fatigue ........................................................................ .. ............. 13 0 12100 Sunrise Valley Drive, Suite 220

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Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page 3 of 41 Last Mod.

Section Page Rev.

5.2.4.5 Emergency and Faulted Conditions ............................................ 14 0 5.2.5 ANSYS Input Listings ..................................................................................... 14 0 5.3 Quality Assurance Software Controls ........................................................................... 14 0 6 REFERENCES ............................................................................................................................. 15 0 A FINITE ELEMENT ANALYSIS INPUT LISTINGS .................*................................................................ 23 0 A.1 File: _HATCH2.runs ...................................................................................................... 23 0 A.2 File: _MACROS.HATCH2 ............................................................................................. 29 0 B SOFlWARE USAGE RECORDS ...................................................................................................... 41 0 CERTIFICATION The original Edwin I. Hatch Nuclear Plant Unit 2 Reactor Vessel Design Report and previous amendments, as identified in Section 6 of this report, are supplemented by this amendment. The original Design Report and previous amendments, in conjunction with this amendment, reaffirm the structural integrity of the components in accordance with the 1968 Edition of Section III of the ASME Boiler and Pressure Vessel Code, with Addenda through Summer 1970. All requirements of applicable Code revisions are satisfied. This evaluation was performed under Purchase Order number SNG10151695.

Z (~ zv,1-E. Broussard, III, PE. Date irginia Certificate No. 032963 12100 Sunrise Valley Drive, Suite 220

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Dominion [n~ineerin~, Inc

Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page 4 of 41 LIST OF TABLES Last Mod.

Table No. Rev.

Table 1. FEA Model Inputs 0 Table 2. Calculation of Primary Stresses in Reactor Vessel Studs, One Stud Out of Service 0 Table 3. Stress Increase Due to Stud Out of Service 0 LIST OF FIGURES Last Mod.

Figure No. Rev.

Figure 1. Reactor Vessel Head Stud Geometry, One Stud Out of Service 0 Figure 2. Hatch Unit 2 RPV Closure Flange FEA Model Overall View [1] 0 Figure 3. FEA Model Node Numbering and Section Cut Line Locations [1] 0 12100 Sunrise Valley Drive, Suite 220

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Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.:

-- 0- Page 5 of 41 1 PURPOSE Dominion Engineering, Inc. (DEI) originally provided optimized tensioning and detensioning procedures for Plant Hatch in January 20I5 [I], along with design basis evaluations for expanded elongation tolerances. The purpose of this calculation is to provide an update to these evaluations that consider the effect of a single stud out of service. This analysis considers the stresses resulting from two conditions which bound the effects of a stud out of service: (I) operating with one stud left untensioned, and (2) the unlikely condition of a stud that is tensioned then fails in service.

2

SUMMARY

OF RESULTS The average stresses in the studs due to primary load conditions with one stud out of service were calculated using the methodology outlined in Section 5.I. As summarized in this section, all studs continue to meet ASME Code requirements for primary loads with one stud out of service.

The FEA model which was used to develop the current stud tensioning evaluations in DEI Report R-3937-00-0I [I] was used to perform an analysis ofthe closure flange with one stud out of service, as summarized in Section 5.2. The analysis results are summarized in Table 3. As demonstrated by the results in Table 3, operation of the Hatch Unit 2 RPV with one stud out of service does not result in any component of the RPV closure flange to exceed the design basis ASME Code allowables.

3 INPUT REQUIREMENTS The following inputs are required to calculate the average stresses in the studs due to primary load conditions with one stud out of service:

I. The RPV design pressure is 1,250 psi a and the design temperature is 575°F [I, Table 3-I].

2. The RPV inner a-ring radius is III.O inches [I, Table 3-3].

3. The RPV stud circle radius is 117.3I3 inches [I, Table 3-3].

4. The number of studs in the Hatch Unit 2 RPV is 56 [ 1, Table 3-I].

5. The stud shank OD is 6.0 inches, the stud shank ID is I.O inches, and the stud shank cross section area is 27.489 in 2 [I, Table 3-I].

6. The Sm allowable at design temperature*for the RPV studs is 36.3 ksi [I, Table 3-3].

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Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.:

- -- 0 Page 6 of 41 The following inputs are required for the FEA analysis of tensioning effects related to one stud out of service:

7. Reactor vessel head and closure flange dimensions. The geometry of the model developed for this analysis is identical to the one used in the Reference [I]. The model parameters used in this FEA model are detailed in Table 1.

8. Reactor vessel head and closure flange low alloy steel material properties. The material properties of the model developed for this analysis are identical to those used in Reference [1].

9. ASME Code design basis summary. The design basis conditions for the RPV closure flange components updated to include the analyses performed in the 2015 tensioning optimization stress report are summarized in Table 2-1 of Reference [ 1]. This table includes the updated stress values as well as the appropriate ASME Code comparison and allowable stress value.

I 0. Primary stress design basis values. The conditions evaluated in the 2015 tensioning optimization stress report do not impact primary conditions, and therefore they were not included. Using the original closure flange design basis report [2] (referenced in the 2015 analysis), the following limiting primary stress values are obtained:

a. Closure head I head flange general membrane stress: 22.5 ksi compared to an allowable stress of 26.7 ksi (Sm) [2, p. A -16]

b. Vessel closure shell I flange general membrane stress: 23.8 ksi compared to an allowable stress of 26.7 ksi (Sm) [2, p. A-16]

c. Closure head I head flange local membrane + bending stress: 28.1 ksi compared to an allowable stress of 40.05 ksi (1.5Sm) [2, p. A-23]

d. Vessel closure shell I flange local membrane+ bending stress: 28.2 ksi compared to an allowable stress of 40.05 ksi (1.5Sm) [2, p. A-29]

4 ASSUMPTIONS The following assumptions are used to calculate the average stresses in the studs due to primary load conditions with one stud out of service:

1. The reactor vessel and head are rigid. This is consistent with the usual treatment of primary loads which only considers net forces and moments and not localization of stress from geometry and compliance effects. A consequence of this assumption is that the distribution of stud forces varies linearly with the distance from the neutral axis.

2. The reactor vessel and head exert no contact forces on each other (i.e., the compression forces on the mating surfaces are neglected). These secondary forces serve to mitigate the redistribution of loads when studs fail, so this assumption conservatively maximizes the calculated maximum stud stress value.

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Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: - - 0- Page 7 of 41

3. As a simplifying assumption, each stud is individually treated as a point force . That is, each stud contributes no bending stiffness to the cross section as a whole.

4. The design pressure is assumed to act out to the radius of the inner o-ring of the vessel.

The following assumptions are used for the FEA analysis of tensioning effects related to one stud out of service. These assumptions are consistent with analyses described in Reference [ 1].

5. All vessel elements were assigned material properties appropriate for low carbon steel at ambient temperature: E = 27.9E6 psi and v = 0.3. All stud elements were assigned material properties appropriate for low alloy steel at ambient temperature: E = 29.9E6 psi and v = 0.3. The differences caused by differential thermal expansion of the stud and vessel are negligible and are not considered.

6. The modulus of elasticity in the stud hole regions of the upper and lower flanges were de-rated by the ratio shown in Table 1 to account for the removed material in the stud holes.

7. The contact between the nut and the washer is assumed to occur at a single point location. This is considered a reasonable assumption since the nut and washer mate at a spherical surface, and therefore come into contact all at once.

8. Beam elements that are stiff in bending are used to impose flange rotation on the ends of the studs. Despite the presence of spherical washers between the nut and the upper flange, friction acts to "glue" the nut to the flange once the stud is preloaded. At full pressure load, a modest amount of friction (Jl < 0.1) has been demonstrated to be sufficient to transmit the bending stresses which arise from this boundary condition. Thus, the infinite friction assumption is concluded to be more realistic than the assumption of zero friction at the spherical washer.

9. The interface between the head and vessel flanges was simulated by a row of line elements connecting the head and vessel flanges. The location of these interface elements was selected to act at a "reaction radius" empirically determined from the correlation between the model predictions and the actual stud elongation data using the existing tensioning procedure.

10. All studs are assumed to be initially uniformly tensioned to the target stud elongation of 0.0397 inch, equivalent to a stud stress of 37.146 ksi [I , Table 3-1].

5 ANALYSIS

5. 1 Stud Primary Stress with One Stud Out of Service The effect of a stud being out of service on the primary stress in the remaining studs is greater than simply increasing the design basis primary stress by the ratio of original to remaining studs. The change in restraint conditions caused by the inactive stud will tend to create a larger primary load in the studs adjacent to the inactive stud.

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Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page 8 of 41 We treat the studs as a single cross section loaded in bending by the pressure on the reactor head.

Assuming one stud is out of service, and that the resulting force distribution in the studs is a linear function of the distance from the neutral axis of the stud cross section, we enforce the static equilibrium equations on the studs. Note that the linear distribution assumption is a consequence of Assumption I. An Excel spreadsheet is used to facilitate solution of the equations which are developed.

5.1.1 Average Stud Force Ignoring for a moment that the 55 remaining studs are not uniformly distributed around the RPV closure, we can compute the average force in the studs according to the following equation. Assuming that the design pressure (in psig) acts out to the location of the inner o-ring radius (characterized by radius R;), we have:

_ PA P(nR/) (1235 psig){1Z'xlll.0 2 in 2 )

F=-" = = =869.2 kipS [5-1]

55 55 55 This value will be used in computing the actual force (and, from there, stress) distribution among the studs in a later section. For comparative purposes, we note that when all studs are intact and tensioned, the corresponding average force is (55/56)*869.2 = 853.6 kips.

5.1.2 Calculation of Stud Force Distribution Because the out of service stud is located symmetrically about the x-axis, the neutral axis of bending for the remaining studs (considered as a whole) must be oriented parallel to they-axis in Figure I. The offset (Hrom the center of pressure is still an unknown at this point, however. The solution for ois achieved by writing the static equilibrium equations for the reactor head LFz = LF,-PAh = 0

[5-2]

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Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page 9 of 41 where Fz = net force in the direction parallel to the stud lengths M,, = net moment about the neutral axis x; = x-coordinate of each stud per the axes in Figure I 8 = parallel offset of the neutral axis from they-axis as shown in Figure I A 11 = area of the reactor head on which the pressure force acts The coordinates Xi can be written in terms of the bolt-circle radius (R 0 ) and Oi as defined in Figure I.

e XI = Ro cos 01' where 01 = 5~ 9 ) X 27T [5-3]

At this point, we assume per Section 4 that the stud force varies linearly with its distance from the neutral axis. The mathematical form of the force distribution in the studs consequently may be expressed as follows, wherefis a constant F 1

= F + J(x 1

- 8) [5-4]

Substituting Eq. [5-4] into the first ofEqs.[5-2] and taking advantage ofthe fact that I'F = PA, yields L (F + f (XI - 8))- PA, =0 ~ L f (XI - 8) = 0 ~

[5-5]

8 = LX = ~ Icos0 1

55 1 1 I I where Eq. [5-3] has been used for Xj. Since 8is now known, we can substitute Eq. [5-4] into the second of Eqs. [5-2], resulting in the following 12100 Sunrise Valley Drive, Suite 220

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Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.:

-- 0- Page 10 of 41 L( F + f(x,- c5)}(x,- c5)- PA,(-8) =0 ~

I

[5-6]

The values forfand c5can be substituted directly back into Eq. [5-4], producing the force distribution for all studs. The final results appear in Table 2. Note that the highest stud force occurs at Stud Location Nos. 2 and 56, as might be expected since these are adjacent to the untensioned stud (No. I).

5.1.3 Primary Stress Comparison The distributed primary stud forces are divided by the stud stress area of 27.489 in 2 (Input 5) to calculate the primary stud stresses. The maximum primary stud stress is calculated in Table 2 to be 32.8 ksi, which is less than the Sm allowable of 36.3 ksi; therefore, this condition is satisfied.

5.2 Analysis of Closure Flange with Stud Out of Service 5.2.1 Evaluation Methodology The effect of one stud out of service on the ASME Code comparison stresses in the reactor vessel closure flange components is evaluated using the same model used in the 2015 tensioning optimization stress report. The approach used to evaluate these conditions is to: (I) determine the stresses in the studs and vessel for the intact case and for the case of a single stud out of service under preload plus design pressure conditions, (2) determine the increase in the stresses when going from the intact to single stud out of service condition, (3) add the calculated increase in stress to the stress given in the design report which includes the effect of plant design transients, and (4) determine if the calculated single stud out of service condition stresses still meet ASME Code requirements.

12100 Sunrise Valley Drive, Suite 220

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Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.:

-- 0- Page 11 of 41 5.2.2 Reactor Vessel Closure Flange Model The simulation was performed using the finite element analysis model described in Appendix A of Reference [I]. The modeling methods are summarized in this section; greater detail on the specifics of the model is described in Reference [I].

5.2.2.1 Model Geometry The vessel shell, head and flange regions were modeled using SOLID45 (30 structural solid) elements with each row of elements corresponding to one stud pitch. Studs were modeled using BEAM4 (30 beam) elements which resist tensile loads and bending moments. A three dimensional model of the Hatch RPV closure flange was simulated as shown in Figure 2. The model considers half the circumference of the closure flange, with symmetry boundary conditions at the circumferential edges.

The 3-D BEAM4 elements used for the studs and tie bars require three real properties: area, moment of inertia, and thickness (used to calculate section modulus). The stud element real properties used in the analysis are reported in Reference [I]. Tie bar properties were selected so that the area is I 00 times smaller than the area of the studs, and the moment of inertia is I 00 times greater than that of the studs.

This has the effect of making the tie bars rigid in bending (as they are being used, the elements have no shear deflection), so that the rotation of the flanges is imposed on the ends of the studs without affecting the stiffness of the adjacent solid elements.

The interface between the head and vessel flanges was simulated by a row of LINKS (30 spar) elements connecting the head and vessel flanges. The location of these interface elements was selected to act at a "reaction radius" empirically determined from the correlation between the model predictions and the actual stud elongation data using the existing tensioning procedure.

The case of an untensioned stud is simulated by deleting the beam element representing that stud and adjusting the initial strains on the studs adjacent to the untensioned stud to produce the specified preload. If the spar elements simulating the vessel to head contact have axial tensile stresses in the pressurized condition, these elements are deleted and the coupled circumferential and radial constraints at these nodes are removed to simulate the fact that there is no longer a frictional restraining force at this location.

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Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.:

-- 0- Page 12 of 41 5.2.2.2 Model Boundary Conditions The nodes at the bottom of the vessel shell were all fixed in the vertical and circumferential directions and allowed to move freely in the radial direction. Additionally, out of plane rotations (ROTX and ROTZ) were restrained on the nodes associated with the tie bar elements. The rotation of the flange was tied to the bending of the stud by coupling the rotational degree of freedom between the node at top of the stud beam element and the center node of the "tie bar" elements at the top of the flange.

As noted previously, symmetry boundary conditions were applied at the circumferential edges of the model. In addition, the stud and tie bar beam elements located at each end of the model (i.e., in the first and last planes) are assigned half of the area and moment of inertia as the rest of the studs because they lie on a plane of symmetry. Similarly, the LINKS elements representing flange contact located at each end of the model are given half the area ofthe rest of the flange contact elements.

5.2.3 Analysis Cases Six cases are evaluated as follows:

Case AI represents the preload condition with all studs intact

Case A2 represents the operating condition with the vessel at design pressure and with intact studs

Case 81 represents the case of one stud untensioned and with all other studs pre loaded to the specified initial stress

Case 82 same as Case 8 1 with the vessel at design pressure

Case Cl represents the case of all studs pre loaded to the specified initial strain with one stud assumed to fail in service

Case C2 same as Case C 1 except the vessel is at design pressure 5.2.4 Results Discussion The results of the finite element analyses are summarized in Table 3. The increases in stress caused by the inactive stud are summarized, and the stresses are compared to the appropriate ASME Code allowables. As noted in Input 9, the ASME Code comparisons and allowables are taken from Table 2-1 of Reference [ 1]. The following evaluations are considered:

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- - 0- Page 13 of 41 5.2.4.1 RPV Closure Stresses As shown in Table 3, the stud out of service has little to no impact on the stresses associated with General Primary Membrane Stress Intensity, Primary Local Membrane plus Bending Stress Intensity, and Maximum Stress Intensity Range. Each of these stress values remain below the appropriate ASME Code allowable stresses.

5.2.4.2 RPV Stud Stresses As shown in Table 3, the stud out of service has a modest immpact on the stresses associated with the stud Maximum Membrane and Maximum Membrane plus Bending stress. Each of these stress values remain below the appropriate ASME Code allowable stresses.

5.2.4.3 RPV Closure Flange Separation As shown in Table 3, the stud out of service causes an additional flange separation at the a-ring of 0.0078 inch. This increase does not impact an ASME Code allowable. The flange separation is less than the a-ring minimum springback ofO.OIO inch cited in Table 3-2 of Reference [1).

5.2.4.4 Fatigue Per Table 3, the stud out of service increases the maximum stress at: (I) the head flange/shell by 0.24 ksi, (2) the vessel flange/shell by 0.47 ksi and (3) the stud by 0.97 ksi; each of these increases are approximately I% of the previous design basis stress. According to Table 2-1 of Reference [I], the fatigue usage values in these components are as follows: (I) the head is 0.178 (2) the vessel is 0.679, and (3) the stud is 0.846. These fatigue usage values were calculated for the full service life of the component.

The impact of the I% increase in stress for a single cycle of operation on these components is negligible. Referring to the fatigue curves in the design basis Code [7], Figures N-415A (vessel and head material) and N-416 (bolting material), it may be demonstrated for higher values of alternating stress that the number of allowable cycles is inversely proportional to the square of the increase in stress. Therefore, even if the components were operated for their full service life with the increase in stress resulting from one stud out of service, the increase in fatigue usage would be the square of the increase in stress, or 1.01 2 = 2%. The resulting values would remain below the Code allowable of 1.0.

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Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: - - 0- Page 14 of 41 5.2.4.5 Emergency and Faulted Conditions Review of the design basis conditions evaluated in the original plant design basis report [2]

demonstrates that, for the RPV closure flange components, meeting the ASME Code requirements for normal and upset conditions described in previous sections of this calculation bounds the requirements for emergency and faulted conditions. This is demonstrated on pages A-ll through A-30 of Reference [2] as follows :

The emergency condition evaluated in Reference [2] is a vessel overpressure event. The evaluated pressure is I ,350 psia, or a factor of I .08 greater than the normal condition design pressure, but the stress allowables for emergency conditions are I .2 times the normal condition allowables.

The faulted condition evaluated in Reference [2] is a pipe rupture event. The evaluated pressure is I ,000 psia, which is lower than the normal condition design pressure.

5.2.5 ANSYS Input Listings The RPV closure flange stud tensioning analysis described in this section is performed using the ANSYS input listing files _HATCH2.runs, _MACROS.HATCH2, and MACROS.DEI. The

_HATCH2.runs input listing defines parameters that are used by _MACROS.HATCH2 and MACROS.DEI to generate the geometry and run the stud out of service analysis cases. The input listings _HATCH2.runs and _MACROS.HATCH2 are provided in Appendix A.

MACROS.DEI is a proprietary input listing developed outside ofthe scope of this work. It is retained as an electronic file on a data disk [6] along with other software usage QA records required by the DEI QA program [4]. The contents of this data disk are listed in Appendix B. This data disk is retained with the project file for this task (Task 3944) and is available for on-site review by Southern Nuclear personnel.

5.3 Quality Assurance Software Controls The RPV closure flange stud tensioning analysis described in this calculation was performed on the "ANSYS-A" Dell Precision R7910 workstation, using Windows Server 2012 R2 Standard 64-bit operating system and ANSYS Version 15.0 which was verified on February 6, 2017, as documented in Reference [3]. This software is maintained in accordance with the provisions for control of software described in Dominion Engineering, Inc.'s (DEI's) quality assurance (QA) program for safety-related 12100 Sunrise Valley Drive, Suite 220

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Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page 15 of 41 nuclear work [4]. 1 In addition to QA controls associated with the procurement and use of the ANSYS software (e.g., maintenance of the ANSYS Inc. as an approved supplier of the software based on formal auditing and surveillance; formal periodic verification of ANSYS software installation), QA controls associated with all ANSYS batch input listings are also carried out by DEI. These include independent checks of a batch input listing each time it is used; review of all ANSYS Class 3 error reports and QA notices to assess their potential impact on a batch input listing; and independent confirmatory analyses 2 to ensure that the project-specific application of the analysis is appropriate. The review of ANSYS error reports and QA notices as well as the project-specific check calculations are documented formally in a QA memo to project file (5].

The stud primary stress calculations performed in Table 2 were generated using Microsoft Excel 2010 on a Dell Latitude E7440 with an Intel Core i7 processor and running Microsoft Windows 7. The one-time-use Microsoft Excel spreadsheet "Hatch 2 Stud Primary Stress Calc vO.xlsx" was prepared, checked, and reviewed in accordance with DEI's nuclear QA program manual [4] and is archived on the data disk associated with this calculation (6].

6 REFERENCES

1. DEI Report R-3937-00-1, Rev. 0, "Reactor Vessel Tensioning Optimization Stress Report -

Hatch Nuclear Plant Unit 2," January 2015.

2. "Analytical Report for Hatch No.2 Reactor Vessel for Georgia Power Company," Combustion Engineering Report No. CENC-1232, April 1975.

3. Dominion Engineering, Inc. Software Test Report No. STR-9898-00-19, "ANSYS 15.0 Re-Verification Software Test Report." Revision 0, February 2017.

4. Dominion Engineering, Inc. Quality Assurance Manual for Safety-Related Nuclear Work, DEI-002. Revision 18, November 2010.

5. Dominion Engineering, Inc. Memorandum M-3944-00-01, Revision 0, "ANSYS Confirmatory Analysis and Review of Error Reports I QA Notices for C-3944-00-0 1, Rev. 0." February 2017.

6. Dominion Engineering, Inc. Data Disk D-3944-00-01, Revision 0, dated February 2017.

1 DEI's quality assurance program for safety-related work (DEI-002) commits to applicable requirements of 10 CFR 21, Appendix 8 of I 0 CFR sq, and ASME/ ANSI NQA-1. This QA program is independently audited periodically by both NUPIC (the Nuclear Procurement Issues Committee) and NIAC (the Nuclear Industry Assessment Committee).

2 Confirmatory analyses for a given project may include comparison of model-computed stresses to theoretical closed-form solutions and other checks on model results.

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7. ASME Boiler and Pressure Vessel Code, Section III - Rules for Construction ofNuclear Vessels, 1968 Edition with Addenda through Summer 1970.

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Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page 17 of 41 Table 1. FEA Model Inputs Parameter Units Hatch Unit 2 Stud and Vessel Parameters

- Number of Studs --- 56

- Stud Shank OD in 6.000

- Design Stud Stress Area in Shank in"2 27.489

- Calculated Stud Moment of Inertia in"4 63.568

- Membrane Stress, Preload Only ksi 35.58

-Corresponding Elongation in 0.038

- Design Pressure psia 1,250

- Stud Effective Length in 31.937 Tensioning Parameters

- Max Tensioner Pressure (new) psi n/a

- Optimized Sequence Final Pressure (new) psi 7,100

- Resuhing Stud Stress ksi 37.15

- Tensioner Coeffteient, Kt psvin 5.232 Bohing Dimensions

- Stud Circle Radius in 117.313

- Stud Hole Diameter in 6.750

- Spherical Washer Radius of Curvature in 27.000

- Modulus Ratio in Hole Region --- 0.60 Vessel Flange Dimensions

- Flange IR in 109.690

- Inner 0-ring Mean Radius in 111.000

- Reaction Radius in 113.250

- Seating Surface Outer Radius in 113.750

- Flange OR in 122.625

- Z dim to ID Transition in -18.000

- Z dim to OD transition in -14.500 Vessel Shell Dimensions

- Shell IR in 110.720

- Shell thickness in 5.875

- Z dim to Bottom of Transition in -21.090 Head Flange Dimensions

- Flange IR in 109.250

- Flange OR in 122.625

- Flange Top Fillet Radius in 2.750

- Z dim to Top of Flange in 24.375

- Z dim to Recess (inner) in 0.375

- Z dim to Recess (outer) in 0.375 Head Shell Dimensions

- Shell IR in 109.500

- Shell thickness in 3.188

- Z dim to Head Coord. Sys. in -7.250 12100 Sunrise Valley Drive, Suite 220

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Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-0 1 Revision No.: 0 Page 18 of 41 Table 2. Calculation of Primary Stresses in Reactor Vessel Studs, One Stud Out of Service Design Pressure, P. ps1g 1,235 Boh Circle Radius, Ro 117,313ot Inner o-ring Radius, Ri II 1.000 Average fOrce, Fbar 869.2 kips Studs Our ofSenice I Neu!ral axis oi!Set, d 2. 133 m.

Stud Stress Area, A 27.489 Coefliciem f -274 .6 psi/in Nll11ber ofStuds 56 Stud theta cos(theta) cos" 2 (theta) Fi Stress (deg) (kip) (ksi)

I -180 IBllensioned Wltensioned Wltensioned llltensioned 2 -174 -0.9937 099 901 8 32 80 3 -167 -0.9749 095 901 2 32 78 4 -161 -0 9439 0 89 900.2 32 75 5 -154 -0,9010 0 81 898 8 32 70 6 -148 -0.8467 0.72 897.0 32.63 7 -141 -0.7818 0.61 894,9 32 56 8 -135 -0 7071 0 50 892.5 32.47 9 -129 -0.6235 0 39 889.8 32.37 10 -122 -0 5320 0.28 886.9 32.26 II -116 -0 4339 0. 19 883.7 32 15 12 -109 -0.3303 0 II 880.4 32.03 13 -103 -0.2225 0.05 876.9 31,90 14 -96 -0 ll20 0 01 8734 31.77 15 -90 0.0000 0.00 869,7 31.64 16 -84 0. 1120 0 01 866 I 31 51 17 -77 0.2225 0.05 862 6 31.38 18 -71 0.3303 0 II 859 I 31 25 19 -64 0.4339 0.19 855 .8 31.13 20 -58 0.5320 0.28 852 6 31 02 21 -51 0.6235 0 39 849 7 30.91 22 -45 0.7071 0.50 847,0 30.81 23 -39 0.7818 0.61 844 ,6 30,72 24 -32 0.8467 0,72 842 5 30.65 25 -26 0 9010 0.81 840 7 30.58 26 -19 0.9439 0.89 839.3 30.53 27 -13 0,9749 0.95 838 3 30.50 28 -6 0.9937 0_99 837.7 30.48 29 0 I 0000 I 00 837.5 30.47 30 6 0.9937 0.99 837 7 30.48 31 13 0.9749 0.95 838 3 30.50 32 19 0.9439 0.89 839.3 30.53 33 26 09010 0 81 840.7 30.58 34 32 0 8467 0.72 842 5 30.65 35 39 0.7818 0.61 844.6 30.72 36 45 0.7071 0.50 847 0 30.81 37 51 06235 0 39 849.7 30 .91 38 58 0,5320 0.28 852.6 31.02 39 64 0.4339 0. 19 855.8 31.13 40 71 0.3303 0. 11 859. 1 31.25 41 77 0.2225 0.05 862.6 31.38 42 84 0. 1120 0 01 866 I 31.51 43 90 0.0000 0.00 869,7 31.64 44 96 -0. 1120 0.01 873.4 31.77 45 103 -0.2225 0.05 876.9 31.90 46 109 -0.3303 0. 11 880.4 32.03 47 116 -0 4339 0. 19 883.7 32. 15 48 122 -0.5320 0.28 886.9 32.26 49 129 -0.6235 0.39 889.8 32.37 50 135 -0.7071 0.50 892.5 32.47 51 141 -0.7818 0 61 894.9 32.56 52 148 -0.8467 0.72 897.0 32 .63 53 154 -0.9010 0.81 898.8 32.70 54 161 -0.9439 0 89 900.2 32.75 55 167 -0.9749 0.95 901.2 32 .78 56 174 -0.9937 0.99 901.8 32 .80 12100 Sunrise Valley Drive, Suite 220

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Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page 19 of 41 Table 3. Stress Increase Due to Stud Out of Service Shell Stresses (ksi) (2) Stud Stresses (ksij Flange Stud Load Gen. Membrane Local Memb.+Bend. MaximwnSI Max Memb+ Separation Load Condition Condition Case Head Vessel Head Vessel Head Vessel Membrane Bending (10"-3 in)

Preload Only Nonnal AI 0,07 0.28 23.82 18.11 24.60 18.48 37.10 81.56 14.7 Pre load 0 nly I Untensioned Bl 0.09 0.28 23.83 18.10 24.61 18.49 37.10 81.59 14.7 Preload Only I Failed Cl 0.09 0.28 23.82 18.11 24.60 18.48 40.06 81.58 14.7 Preload+Pressure Nonnal A2 22.13 23.49 36.93 34.17 37.02 33.94 34.91 97.92 21.2 Preload+Pressure I Untensioned 82 22.13 23.49 37.12 34.52 37.21 34.31 37.34 97.98 m Preload+Pressure I Failed C2 22.13 23.49 37.17 34.63 37.26 34.41 39.30 98.89 26.6 Max. Increase from A2 (Cases B2 & C2) 0.00 0.00 0.24 0.46 0.24 0.47 4.40 0.97 7.8 Limiting Vessel Report Value (I) 22.50 23.80 28.10 28.20 64.00 47.40 45.30 95.40 --

New Maximwn Value 22.50 23.80 28.34 28.66 64.24 47.87 49.70 96.37 -

Code Stress Limit Sm = Sm = 1.5 Sm = 1.5 Sm = 3.0 Sm = 3.0 Sm = 2Sm = 2.7 Sm =

26.7 26.7 40.1 40.1 80.1 80.1 73.5 99.2 (I) Value taken from R-3937-00-01 Rev 0 [I] or from Rererence [2] as listed in Input 10.

(2) Local Membrane + Bending and Maximwn Sl taken at cut lines 2, 3, 4, 5, 6, and 7. General Membrane Sl taken at cut lines I and 8. (See Figure 3).

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Blackened Stud is Out of Service 8

Neutral Axis Figure 1. Reactor Vessel Head Stud Geometry, One Stud Out of Service 12100 Sunrise Valley Drive, Suite 220

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/

28 , 000 ' s Nodal Plane

--2000 ' s Nodal Plane

~"1000 ' s Nodal Plane l ' s Nodal Plane Figure 2. Hatch Unit 2 RPV Closure Flange FEA Model Overall View [1]

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Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page 22 of 41 269

-~++.----4

-~+tt----3

-~+tt---- 2 11 / "15 1/ "5 Figure 3. FEA Model Node Numbering and Section Cut Line Locations [1]

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Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 23 Page -==-- of 41 A FINITE ELEMENT ANALYSIS INPUT LISTINGS A.1 File: _HATCH2.runs

/BATCH,LIST

/COM,

/COM, *************************************************************** *******************

/COM, Hatch Unit 2 Stud Out of Servi ce Evaluation

/COM, *************************************************************** *******************

/COM,

/INP,_MACROS,HATCH2

/INP,_MACROS,DEI

/COM,

/COM, **********************************************************************************

/COM, PRE-RUN SETUP

/COM, **********************************************************************************

/COM,

/FILNAM, Tens-1

/SHOW,plots,grph

/TYPE,1,4

/PREP?

/TITLE, Hatch2 Reactor Vessel Tensioning

/COM, Define run parameters NT = 56 ! Total number of studs in model NV = 56 ! Total number of studs in real vessel NPMAX = 56*3 ! Max number of studs any sequence TENSMX = 7 ! Max number of Tens-* routines XS = 37146 ! Final stud stress target for old tensioner XP = 7100 ! Corresponding tensioner pressure Pmax = 8500 ! Tensioner pressure cap X1 = 0.9994 ! Empirical correction factor (init guess)

X2 = 0.9854 ! Empirical correction factor (init guess)

Kt = XS*X1/XP ! Relate tensioner pressure to stud stress RLMAX = NT+1 ! Number of data items in RLIST (from ENDPOST macro)

DIM,TENSAR,ARRAY,TENSMX,3

/COM,

DIM,MPBTMPI,ARRAY,5

DIM,MPBTMPC,ARRAY,5

DIM,MPBTMPO,ARRAY,5

DIM,TOTTMPI,ARRAY,5

DIM,TOTTMPO,ARRAY,5

/COM,

/COM, *** TOGGLE TENSIONING ROUTINES ***

/COM,

/COM, To set tensioning routine I (Tens-!) to RUN, toggle TENSAR(I,1)=1

/COM To set tensioning routine I (Tens-!) to OFF, toggle TENSAR(I,1)=0

/COM, TENSAR(I,2) is number of cyclic symmetry slices (=1 for full model) for Tens-!

/COM, TENSAR(I,3) is number of passes thru OPTLOOP for Tens-! (max of 7)

/COM, TENSAR(1, 1) =1 STENSAR(1,2)=1 STENSAR(1,3)=1 RUNMORF = 1 ! RUNMORF=1 to run out of service stud cases

/COM,

DIM,PLIST,ARRAY,NPMAX,4

DIM,RLIST,ARRAY,NT,RLMAX

DIM,RSAVE10,ARRAY,NV/2+1,RLMAX,6

/COM,

/COM, *************************************************************** *******************

/COM, GEOMETRY FIGURES

/COM, **********************************************************************************

/COM,

/COM, Make 1/2 model to lay down 'Appendix A' plots NT = NV/2+1 ! Total number of studs in model

/COM, Clear the boundary conditions and re-do the geometry.

/PREP?

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24 of _....:....:.._

41

USE,GEOM,O ! Create geometry

/TITLE, Hatch2 Reactor Vessel Tensioning

/VIEW,1,1,1,1 ESEL,S,TYPE,,1 NSLE

/COLOR,NUM,BLAC,1

/TRIAD,OFF

/DIST ,1,1. 5*HFOR

/FOCUS,1,-HFOR/4,-65,-HFOR/2.1 EPLO ESEL,S,ELEM,,41,290 ESEL,A,ELEM,,1041,1290 NSLE

/PNUM,MAT,1

/NUM,1

/AUTO EPLO ESEL, S, TYPE, ,1 ESEL,R,ELEM,,1,1000 NSEL,S,NODE,,1,1000

/VIEW EPLO

DO,I,1,11

/COLOR,NUM,WHIT,I

ENDDO

/NUM

/PNUM,ELEM,1 ESEL,S,ELEM,,502,506 ESEL,A,ELEM,,1502,1506

REPEAT,4,, ,,1000,1000 NSLE NSEL,U,NODE,,361,4361,1000

/VIEW,1,1,1,1

/AUTO EPLO

/VIEW,1,-1,1,5

/NUM,2 ESEL, S, ELEM, , 501 NSLE EPLO

/USER

/DIST,1,5.75 ESEL,S,TYPE,,1 ESEL, A, ELEM, , 501 NSLE EPLO ALLSEL

/AUTO

/COLOR,DEFA

/NUM FINISH

/COM,

/COM, *************************************************************** *******************

/COM, TENSIONING ROUTINE 1: INITIALIZE MODEL

/COM, *************************************************************** *******************

/COM,

/PREP7 NT = 10 ! Total number of studs in model

USE,GEOMCLUP

USE,GEOM,O ! Create geometry FINISH

/COM,

/COM, Do initial sets at final pressure to solve for X1 and X2

/COM, Tension all studs except in one set and then retension stud 10 PP = NT ! Number of studs in each set NP = 2 ! Number of sets in this sequence n = 1 ! Number of sets to achieve one-pass tens.

USE,ZEROIT

DO,I,1,NT PLIST(I ,1) = I ! Load PLIST column 1 with stud numbers PLIST(I,2) = XP ! Load PLIST column 2 with ref. tens. press.

ENDDO 12100 Sunrise Valley Drive, Suite 220

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-=-

DO,I,NT+1,NT*2 PLIST(I,1) = 10 ! Load PLIST column 1 with stud numbers PLIST(I,2) - XP ! Load PLIST column 2 with ref. tens. press.

PLIST(I,4) = 1.0 ! Load PLIST column 4 with retens. flag

ENDDO

IF,TENSAR(1,1),GT,O.S,THEN

USE,GOSOLV, 'Hatch2', 'Tens - 1' ,1 ! Solve model X1 = X1*XS/RLIST(10,3) ! X1 is ref. stress/ av. stud stress - single stud X2 = X1*XS/RLIST(1,3) ! X2 is ref. stress/ av. stud stress - all studs Kt = XS*X1/XP ! Relate tensioner pressure to stud stress

ENDIF

/COM,

/COM, ********** * ********** *************************************************************

/COM, TENSIONING ROUTINE 10: RUN MISSING OR FAI LED STUD CASES

/COM, ***************************** *****************************************************

/COM,

/FILNAM,Tens-10

/COM, Change over to a half model for missing stud runs

/PREP7

USE,GEOMCLUP NT = NV/2+1 ! Total number of studs in model

USE,GEOM,O ! Create geometry FINISH Kt = XS*X2/XP ! Relate tensioner pressure to stud stress

/COM, Tension all studs in one pass PP = NT ! Number of studs in each pass NP = 1 ! Number of passes n = 1 ! Number of passes to achieve one- pass tens.

USE,ZEROIT

DO,I,1,PP PLIST(I, 1) = I ! Load PLIST column 1 with stud numbers PLI ST(I, 2) = XP ! Load PLIST column 2 with ref. tens. press.

ENDDO

USE,GOSOLV,'Hatch2', 'Tens-10' ,1 ! Solve model - Case A1 SAVE, ,A1

DO,I,1,NT

DO,J,1,RLMAX RSAVE10(I,J,1) = RLIST(I,J)

ENDDO

ENDDO

USE,ZEROIT I=1

USE,PSOLV, 'Hatch2', 'A2' ,2.0,1235 ! Solve model

Case A2 SAVE, ,A2

DO,I,1,NT

DO,J,1,RLMAX RSAVE10(I,J,2) = RLIST(I,J)

ENDDO

ENDDO

USE,ZEROIT I=1

/COM, BEGIN SOLUTION PHASE

/SOLU ANTYPE,STATIC,REST SFDELE,ALL,ALL EKILL,502

/TITLE, Hatch2 Reactor Vessel - Case C1 - Preload Only TIME, 3.0 SOLVE FINISH

/POSTl SET,, ,3.0

USE, POSTER

USE,ENDPOST FINISH SAVE, ,C1

DO,I,1,NT

DO,J,1,RLMAX RSAVE10(I,J,S) = RLIST(I,J)

ENDDO

ENDDO

USE,ZEROIT 12100 Sunrise Valley Drive, Suite 220

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USE,PSOLV, 'Hatch2', 'C2',4.0,1235 ! Solve model -Case C2 SAVE, ,C2

DO,I,l,NT

DO,J,l,RLMAX RSAVE10(I,J,6) = RLIST(I,J)

ENDDO

ENDDO

/COM, Check for flange contact links which came out of compression LCHG = 0

DO,I,l,NT

IF,RLIST(I,lO),GT,O,THEN LCHG = 1.0

/PREP7 EKILL,I*l000-499 ! EKILL 501 El. in row CPDELE,I CPDELE,100+I FINISH

ENDIF

ENDDO

IF,LCHG,EQ,l.O,THEN

USE,ZEROIT I=l

USE,PSOLV, 'Hatch2' ,'C2',5.0,1235 ! Re-Solve model - Case C2 SAVE, ,C2A

DO,I,l,NT

DO,J,l,RLMAX RSAVE10(I,J,6) = RLIST(I,J)

ENDDO

ENDDO

ENDIF

/COM, Clear the boundary conditions and re-do the geom.

/PREP7 SFDELE,ALL,ALL CPDELE,ALL,ALL EDELE,ALL NDELE,ALL

USE,GEOM,O ! Create geometry FINISH

/FILN,Tens-108

/COM, Tension all studs in one pass except stud 1 PP = NT-1 ! Number of studs in each pass NP = 1 ! Number of passes TT = 1 ! Number of passes to achieve one-pass tens.

USE,ZEROIT

DO,I,l,PP PLIST(I,l) = I+l ! Load PLIST column 1 with stud numbers PLIST(I, 2) = XP ! Load PLIST column 2 with ref. tens. press.

ENDDO

USE,GOSOLV, 'Hatch2' ,'Tens- lOB' ,1 ! Solve model - Case Bl SAVE, ,81

DO,I,l,NT

DO,J,l,RLMAX RSAVE10(I,J,3) = RLIST(I,J)

ENDDO

ENDDO

USE,ZEROIT I=l

USE,PSOLV, 'Hatch2', '82',2.0,1235 ! Solve model -Case 82 SAVE, ,82

DO,I,l,NT

DO,J,l,RLMAX RSAVE10(I,J,4) - RLIST(I,J)

ENDDO

ENDDO

/COM, Check for flange contact links which came out of compression LCHG = 0

DO,I,l,NT

IF,RLIST(I,lO),GT,O,THEN LCHG = 1.0

/PREP7 EKILL,I*l000-499 ! EKILL 501 El. in row CPDELE,I CPDELE,l00+I 12100 Sunrise Valley Drive, Suite 220

Reston, VA 20191

PH 703.657.7300

FX 703.657.7301

Dominion fn~ineerin~, Inc

Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: Page _.=..:..._

27 of 41 FINISH

ENDIF

ENDDO

IF,LCHG,EQ,1.0,THEN

USE,ZEROIT 1=1

USE,PSOLV, 'Hatch2', '82' ,3.0,1235 ! Re-Solve model - Case 82 SAVE, ,82A

DO,I,1,NT

DO,J,1,RLMAX RSAVE10(1,J,4)

RLIST(I,J)

ENDDO

ENDDO

ENDIF

/COM, Check again for flange contact links which came out of compression LCHG = 0

D0,1,1,NT

IF,RLIST(I,10),GT,O,THEN LCHG = 1.0

/PREP7 EKILL,I*1000-499 ! EKILL 501 El. in row CPDELE,I CPDELE,100+1 FINISH

ENDIF

"'ENDDO

IF,LCHG,EQ,1.0,THEN

USE,ZEROIT 1=1

USE,PSOLV, 'Hatch2', '82' ,4.0,1235 ! Re-Solve model - Case 82 SAVE, ,828

D0,1,1,NT

DO,J,1,RLMAX RSAVE10(I,J,4) = RLIST(I,J)

ENDDO

END DO

"'ENDIF FINISH

/COM, Clear the pressure boundary conditions

/PREP7 SFDELE,ALL,ALL FINISH

USE,ZEROIT

ENDIF

/COM,

/TITLE, Hatch2 Reactor Vessel Tensioning FINISH SAVE

/COM,

/COM, *************************************************************** *******************

/COM, PRINT RESULTS

/COM, **********************************************************************************

/COM,

/COM, Print contents of PSAVE and RSAVE arrays

/OUT,RESULTS,OUT

/NOPR

IF,RUNMORF,EQ,1,THEN

USE,PRINTENS,'PSAVE10', 'RSAVE10' ,6, 'Stud 005',0

ENDIF

/OUT

/GOPR FINISH

/COM,

/COM, **********************************************************************************

/COM, RUN COMPLETE

/COM, **********************************************************************************

/COM,

/FILN,Tens-0 PARSAV,ALL

/COM, Do some file cleanup

/SYS, del CMMAKER

/SYS, del ENDPOST

/SYS, del GEOM 12100 Sunrise Valley Drive, Suite 220

Reston, VA 20191

PH 703.657.7300

FX 703.657.7301

Dominion fn~ineerin~. Inc.

Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page 28 of 41

/SYS, del GEOMCLUP

/SYS, del GODETEN

/SYS, del GOSOLV

/SYS, del OPTLOOP

/SYS, del POSTER

/SYS, del POSTERZ

/SYS, del POSTER3

/SYS, de 1 PRI NTOLR

/SYS, del PRINTENS

/SYS, del PSOLV

/SYS, del READSI

/SYS, del ZEROIT

/SYS, del NPL

/SYS, del linrept

/SYS, del *.dbs

/SYS, del *.stat

/SYS, del *.osav

/SYS, del *.PCS

/SYS, del *. PVTS

/SYS, del *.BCS

/SYS, del *.full

/SYS, del file.log

/SYS, del Tens-1. *

/SYS, del Tens-lO.e???

/EXIT 12100 Sunrise Valley Drive, Suite 220

Reston, VA 20191

PH 703.657.7300

FX 703.657.7301

Dominion [n~ineerin~, Inc.

Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 29 of Page -==-- 41 A.2 File: _MACROS.HATCH2

/COM, --------------- MACROS.HATCH2, Revision 1, Created February 2017 ----------------

/COM, *************************************************************** *******************

/COM,

/COM, *************************************************************** *******************

/COM, CREATE GEOMETRY MACRO

/COM, --------------------------------------------------------------- -------------------

/COM,

CREATE,GEOM

/COM, ------------------------------------------------------------------

/COM, GEOMETRY AND RUN PARAMETERS

/COM, --------------- ------ ----------------------------------------- - ---

/COM, Loads and Material Properties Esteel = 27.9E6 ! Young's modulus (psi)

Ds = 6.000 ! Stud shank diameter (in)

As = 27.489 ! Stud area (inA2)

Is = 63. S68 ! Stud mom. of I (inA4)

Ls = 31.937 ! Stud effective length (in)

Estud = 29.9E6 ! Tune Estud or Ls to get right effective L

/COM,

/COM, Bolting Dimensions SCR = 117.313 ! Stud Circle Radius (in)

NOs = 6. 7SO ! Stud Hole diameter (in)

SWRC = 27.00 ! Spherical Washer Rad. of Curvature (in)

Ehole = 0.60*Esteel ! Derate in stud hole regions

/COM,

/COM, Vessel Flange Dimensions VFIR = 109.690 ! Vessel flange inner radius (in)

! CBIR = 0.000 ! Core Barrel groove inner radius (in)

IORR = 111.00 ! Inner 0-Ring radius (in)

SSOR = 113.7S ! Seating Surface outer radius (in)

RR = 113.2S ! >>> TUNE REACTION RADIUS <<<

VFOR = 122.62S ! Vessel flange outer radius (in)

! ZVFS = 0.000 ! Z dimension to vessel flange surface (in)

! ZBCB =--0.000 ! Z dimension to bottom of Core Barrel groove ZVIT =-18.00 ! Z dim to vessel inside trans. (120's row)

ZVOT =-14. SO ! Z dim to vessel outside trans. (130's row)

/COM,

/COM, Vessel Shell Dimensions VSIR = 110.72 ! Vessel shell inside radius VSTH = S.87S ! Vessel shell thickness ZVTR =-21.090 ! Z dimension to bottom of vessel transition

/COM,

/COM, Head Flange Dimensions HFIR = 109.2S ! Head flange inner radius HFOR = 122.62S ! Head flange outer radius HFFR = 2 .7SO ! Head flange top fillet radius ZTHF = 24.37S ! Z dimension to top of head flange ZHFRI = 0.37S ! Z dimension to head flange recess - inner ZHFRO = 0.375 ! Z dimension to head flange recess - outer

! /COM,

! /COM, Head Shell Flange Transition

! RTCS = 0.000 ! Radial dimension to Transition Coordinate System

! ZTCS = 0.000 ! Z dimension to Transition Coordinate System

! IRTR = 0.000 ! Inner radius of transition area

! ZUIC = 0.000 ! Vertical rise of OD Transition

/COM,

/COM, Head Shell Dimensions HSIR = 109. so ! Head shell inner radius HSTH = 3.188 ! Head shell thickness ZHCS = -7.2SO ! Z dimension to Head Coordinate System AHT = 19.0 ! Approximate start of head shell region

/COM,

/COM, At = As/100 ! Arbitrarily small tie bar area (inA2)

It = Is*100 ! Arbitrarily large tie bar mom. Of i (inA4) 12100 Sunrise Valley Drive, Suite 220

Reston, VA 20191

PH 703.657.7300

FX 703.657.7301

Dominion fn~ineerin~, Inc.

Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.:

- - Page ----=-30=--- of 41 Dt = Ds*lOO ! Arbitrarily large tie bar diameter (in)

RLTH = 0.005 ! Reaction link thickness (in Z direction)

Ar = As*lOO*(RLTH/Ls) ! Reaction link area tuned for stiffness

! 100 times greater than stud (inA2)

/COM,

/COM, ------------------------------------------------------------------

/COM, MATERIAL PROPERTIES

/COM, ------------------------------------------------------------------

/COM, Set types, mats, and reals

/COM, Element types ET,l,SOLID45 Solids - vessel (no associated real props)

ET,2,LINK8 Links - for reaction (REALS: AREA,ISTRN)

ET,3,BEAM4 Beams - studs (A,IZZ,IYY,TKZ,TKY,THETA,ISTRN)

/COM,

/COM, Material properties

/COM, Material 1 for GENERAL USE MP,EX,1,Esteel MP ,NUXY, 1,0. 30

/COM,

/COM, Material 2 for STUD ELEMENTS MP,EX,2,Estud MP,NUXY,2,0.30

/COM,

/COM, Material 3 for STUD HOLES MP,EX,3,Ehole MP,NUXY,3,0.30

/COM,

/COM, REAL PROPERTIES

/COM, R,1,0 Real 1: Dummy real for solid elements R,2,Ar Real 2: Reaction links R,3,Ar/2 Real 3: Cutting plane reaction links R,4,At,It,lt,Dt,Dt,O Real 4: Tie bars R,5,At/2,1t/2,1t/2,Dt,Dt,O Real 5: Cutting plane tie bars R,11,As,ls,Is,Ds,Ds,O Real 11:Stud elements

REPEAT,NT,1 Assign different reals to each stud

/COM,

/COM, ------------------ -- - ---------------------------------------------

/COM, NODE DEFINITION

/COM, ------------------- -- ---------------------------------------------

/COM,

AFUN,DEG

/COM, Establish coordinate systems LOCAL,20,0,0,0 ! Cartesian on lower mating surface LOCAL,21,1,0,0,0,0,-90,0 ! Cylindrical on lower mating surface (z up)

! LOCAL,22,1,RTCS,ZTCS ! Cylindrical system 1 for head curvature LOCAL,23,1,0,ZHCS ! Cylindrical system 2 for head curvature LOCAL,24,2,0,ZHCS ! Spherical system for head stresses

/COM,

/COM, Define keypoints on theta = 0 plane CSYS,20 BOTZ=-100+ZVTR N,l,VSIR,BOTZ ! SHELL I. R. AT BOTTOM OF MODEL N,5,VSIR+VSTH,BOTZ ! SHELL O.R. AT BOTTOM OF MODEL N,81,VSIR,BOTZ+100 ! SHELL I. R. AT BOTTOM OF FLANGE N,85,VSIR+VSTH,BOTZ+100 ! SHELL O.R. AT BOTTOM OF FLANGE

/COM,

/COM, DEFINE FEATURES ON MATING SURFACE N,161,VFIR,O ! Flange inner surface N,162,(VFIR+IORR)/2,0 ! "Core barrel groove inner surface" N,163,10RR,O ! Inner a-ring radius N,164,RR,O ! Reaction radius N,165,SSOR,O ! Outer limit of seating surface N,166,SCR-NDs/2,0 ! Bolt hole inner edge N,167,SCR,O ! Bolt circle N,168,SCR+NDs/2,0 ! Bolt hole outer edge N,169,VFOR,O ! Flange outer surface flwdth = HFOR-HFIR ! Flange width - head flwdtv = VFOR-VFIR ! Flange width - vessel iormo = RR-IORR ! Inner a-ring moment arm

/COM,

/COM, COPY FEATURES THROUGH VESSEL FLANGE 12100 Sunrise Valley Drive, Suite 220

Reston, VA 20191

PH 703.657.7300

FX 703.657.7301

Dominion fn~ineerin~, Inc.

Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: - - Page 31 of 41 NGEN,2,-10,161,169,1,0,(ZTHF-Ls)/2 ! Copy mating surf. thru lower flange (150's)

NGEN,2,-20,161,169,1,0,ZTHF-Ls ! Copy mating surf. thru lower flange (140's)

NGEN,2,-50,161,169,1,0,ZVOT ! Make 110's row for O.D. feature FILL,151,156,,, ,2,-10 ! Even out 150's and 140's row FILL, 111,117 FILL, 116,118 NGEN,2,-20,111,117,1,0,(ZVIT-ZVOT) ! Make 90's row for I.D. feature NMODIF,97,NX(85)

FILL,91,97 NGEN,2,10,91,97,1,0,-(ZVIT-ZVOT)/2 ! Make 100's row for transition FILL,111,141,2,121,10,9,1

/COM,

/COM, FILL IN REST OF NODES IN VESSEL FLANGE FILL,1,5 FILL,81,85 FILL,1,81,7,,,5,1,0.4 ! FILL IN VESSEL SHELL NODES

/COM,

/COM, ARRANGE HEAD FLANGE SURFACE NODES CSYS,20 NGEN,2,40,161,169,1,0,RLTH ! COPY LOWER MATING SURF. TO UPPER FLANGE N,201,HFIR,RLTH ! HEAD FLANGE INNER SURFACE FILL, 201,203 NGEN,2,10,201,209,1,0,ZHFRI-RLTH ! COPY UP THROUGH UPPER FLANGE NGEN,6,10,211,219,1,0,((ZTHF-ZHFRI)/5)! COPY FIVE ROWS UP THROUGH UPPER FLANGE FILL,221,226,,, ,5,10 ! ALIGN 220'S ROW

/COM,

/COM, MOVE HEAD SHELL IR NODES CSYS,23 NMODIF, 231, HSIR

REPEAT,4,10 FILL,231,234,, ,,4,10

/COM,

/COM, DEFINE NODES IN FREE HEAD CSYS,23 N,361,HSIR,90 ! TOP OF HEAD (INNER SURFACE)

N,364,HSIR+HSTH,90 ! TOP OF HEAD (OUTER SURFACE)

N,271,HSIR,AHT ! LOCATE I.R. AT TOP OF FILLET RADIUS N,274,HSIR+HSTH,AHT ! LOCATE O.R. AT TOP OF FILLET RADIUS FILL,271,361,8,,,, ,2.5 ! FILL IN HEAD INNER RADIUS FILL,274,364,8,,,, ,2.5 ! FILL IN HEAD OUTER RADIUS FILL,251,254,, ,,12,10 ! FILL IN INTERIOR HEAD NODES

/COM,

/COM, SWEEP OUT AROUND 360 DEGREES CSYS, 21 NGEN,NT+1,1000,ALL,,,0,360/NV,O ! MAKE FULL SWEEP OF MODEL NROTAT,ALL ! BRING CS'S INTO ACTIVE CS

/COM,

/COM, ------------------------------------------------------------------

/COM, ELEMENT DEFINITION

/COM, ------------------------------------------------------------------

/COM,

/COM, --=-~=-=-~~------

/COM, MAKE SOLID ELEMENTS TYPE,1 MAT,1 REAL,1 EN,1,1,2,12,11,1001,1002,1012,1011 ENGEN,1,4,1,1,1,1 ! SWEEP ACROSS BOTTOM ROW ENGEN,10,8,10,1,4,1 ! SWEEP UP TO BOTTOM OF FLANGE SHPP,OFF ! TEMPORARILY TURN OFF SHAPE WARNINGS EN,81,81,82,92,91,1081,1082,1092,1091 EN,82,82,93,92,92,1082,1093,1092,1092 EN,83,82,83,94,93,1082,1083,1094,1093 ENGEN,1,2,1,83 EN,85,84,96,95,95,1084,1096,1095,1095 EN,86,84,85,97,96,1084,1085,1097,1096 EN,91,91,92,102,101,1091,1092,1102,1101 ENGEN,1,6,1,91 ! make 91 - 96 ENGEN,10,2,10,91,96,1 ! make 101 - 106 ENGEN,10,2,10,101 ! MAKE 111 ENGEN,1,8,1,111,111,1 ! SWEEP RIGHT TO MAKE 112 - 118 ENGEN,10,5,10,111,118

/COM, 12100 Sunrise Valley Drive, Suite 220

Reston, VA 20191

PH 703.657.7300

FX 703.657.7301

Dominion [n~ineerin~, Inc

Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page 32 of 41 EN,201,201,202,212,211,1201,1202,1212,1211 ! MAKE 201 ENGEN,1,4,1,201,201,1 ! SWEEP RIGHT TO MAKE 202 TO 204 ENGEN,10,2,10,201,201,1 ! SWEEP UP TO MAKE 211 ENGEN,1,8,1,211,211,1 ! SWEET RIGHT TO MAKE 212 TO 218 ENGEN,10,5,10,211,218,1 ! SWEEP UP TO TOP OF FLANGE ENGEN,10,10,10,251,253,1 ! SWEEP THROUGH SHELL EN,351,351,1351,1361,361,352,1352,1362,362 ! MAKE 351 ENGEN,1,3,1,351,351,1 ! FIX UP LAST ROW

/COM,

/COM, ASSIGN BOLT HOLE REGION ESEL,S,ELEM,,146,500,10 ! SELECT INNER SIDE OF BOLT HOLE ESEL,A,ELEM,,147,500,10 ! SELECT OUTER SIDE OF BOLT HOLE EMODIF,ALL,MAT,3 ! ASSIGN BOLT HOLE DIFFERENT MATERIAL ESEL,ALL ENGEN,1000,NT,1000,ALL ! COPY AROUND CIRCLE

/COM,

/COM, -----------------------------

/COM, MAKE LINE ELEMENTS FOR STUD TYPE,2 REAL,2 EN,501,164,204 ! REACTION FORCE LINK TYPE,3 REAL,ll MAT,2 EN,502,147,267,361 ! STUD

/COM,

/COM, --~~~~~~~~~~~---

/COM, MAKE LINE ELEMENTS FOR TIE BARS REAL,4 MAT,1 EN,503,146,147,207 EN,504,147,148,207 EN,505,266,267,207 EN,506,267,268,207 ! TIE BARS EN,507,162,163,204 EN,508,163,164,204 EN,509,164,165,204 EN,510,202,203,164 EN,511,203,204,164 EN,512,204,205,164 ! REACTION SURFACE ENGEN,1000,NT,1000,501,512,1 ! COPY REST OF WAY THROUGH

/COM,

/COM, ---------------------------

/COM, ASSIGN INDIVIDUAL REAL PROPERTIES TO EACH STUD

/COM, STUD REAL IS STUD NO. + 10

DO,I,1,NT ESEL,S,ELEM,,I*1000-498 EMODIF,ALL,REAL,I+10

ENDDO ESEL,ALL

/COM,

/COM, -----------------------------

/COM, DO SOME NODAL CLEANUP NSLE,U NDELE,ALL ! DELETE UNUSED NODES NSEL,ALL NUMMRG,NODE,0.001 ! MERGE OVERLAPPING NODES

/COM,

/COM, --------------------------------------------------------------- ---

/COM, APPLY BOUNDARY CONDITIONS

/COM, --------------------------------------------------------------- ---

/COM, CSYS,21

/COM, ----------------~---------

/COM, COUPLE UPPER AND LOWER FLANGE AT REACTION RADIUS CP,1,UX,164,204 ! COUPLE IN X AXIS CPSGEN,NT,1000,1,1,1 ! SWEEP UX SET AROUND CIRCLE CP,101,UY,164,204 ! COUPLE IN Y AXIS CPSGEN,NT,1000,101,101,1 ! SWEEP UY SET AROUND CIRCLE

/COM, APPLY DISPLACEMENT BOUNDARY CONDITIONS NSEL,S,LOC,Z,BOTZ ! SELECT BOTTOM OF MODEL D,ALL,UY ! APPLY ZERO VERT DISP 12100 Sunrise Valley Drive, Suite 220

Reston, VA 20191

PH 703.657.7300

FX 703.657.7301

Dominion [n~ineerin~, Inc.

Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: - --- 0 Page 33 of 41 D,ALL,UZ ! APPLY ZERO VERT DISP NSEL,ALL ESEL, S, REAL, , 4 ! SELECT TIE BAR ELEMENTS NSLE ! SELECT TIE BAR NODES NSEL,U,NODE,,207,99207,1000 ! DESELECT CENTER NSEL,U,NODE,,361 ! DESELECT TOP OF FLANGE D,ALL,ROTX,O,O,,,ROTZ ! HOLD ROTATIONS ON TIE BARS ESEL,ALL NSEL,ALL

/COM,

/COM, ~~~~~~~~~=-~~~~

/COM, APPLY PRYING FORCES DUE TO CORE BARREL SPRING AND CORE SUPPORT LOAD

IF,Fspr+Fcsl,GT,1.0,THEN

DO,I,1,NT F,131+(1 -1)*1000,FZ, - (Fspr+Fcsl)/2 F,132+(1

1)*1000,FZ, - (Fspr+Fcsl)/2 F,201+(1 -1)*1000,FZ,+Fspr/2 F,202+(1-1)*1000,FZ,+Fspr/2

ENDDO

ENDIF

/COM,

/COM, - - - - - - - - - - - - - -

/COM, PUT SPECIAL BOUNDARY CONDITIONS ON VESSEL FOR PARTIAL MODELS

IF,NT,LT,NV,THEN

IF,ARG1,LT,0.5,THEN ! USE MIRROR SYMMETRY B.C.s

/COM, DELETE EXTRA ELEMENTS AND NODES BEYOND LAST STUD EDELE,(NT-1)*1000+1,(NT-1)*1000+499

/COM, DO SOME NODAL CLEANUP NSLE,U NDELE,ALL NSEL,ALL

/COM, CHANGE REALS ON CUTTING PLANES ESEL,S,ELEM, ,501 ESEL,A,ELEM, ,501+(NT-1)*1000 EMODIF,ALL,REAL,3 ESEL,S,ELEM, ,503,512 ESEL,A,ELEM, ,503+(NT-1)*1000,512+(NT-1)*1000 EMODIF,ALL,REAL,5 ESEL,ALL NSEL,S,NODE, ,1,1000 NSEL,A,NODE, ,1+(NT-1)*1000,NT*1000 NSEL,U,NODE, ,204,99204,1000 D,ALL,UY NSEL,ALL

IF,Fspr+Fcsl,GT,1.0,THEN F,131,FZ,-(Fspr+Fcsl)/4 F,132,FZ,-(Fspr+Fcsl)/4 F,201,FZ,+Fspr/4 F,202,FZ,+Fspr/4 F,131+(NT-1)*1000,FZ,-(Fspr+Fcsl)/4 F,132+(NT-1)*1000,FZ,-(Fspr+Fcsl)/4 F,201+(NT-1)*1000,FZ,+Fspr/4 F,202+(NT-1)*1000,FZ,+Fspr/4

ENDIF

ELSE ! USE CYCLIC SYMMETRY B.C.s

/COM, GET RID OF EXCESS ELEMENTS EDELE,(NT-1)*1000+1,(NT-1)*1000+350

/COM, SWING LAST PLANE AROUND TO 0 DEGREES NSEL,S,NODE, ,NT*1000+1,(NT+1)*1000 CSYS, 21 NMODIF,ALL, ,0 NSEL,A,NODE, ,1,1000 NSEL,U,NODE, ,164,204,40 NROTATE,ALL CPINTF,ALL,0.001 NSEL,S,NODE, ,NT*1000+1,(NT+1)*1000 NMODIF,ALL,,NT*360/NV NSEL,ALL NROTATE,ALL

/COM, BRING BACK LAST PLANE OF ELS.

ENGEN,(NT-1)*1000,2,(NT-1)*1000,1,350,1 ! COPY AROUND CIRCLE

/COM, FIX UP COUPLES ON EDGE PLANES CP,1, ,NT*1000+164,NT*1000+204 CP,101,,NT*1000+164,NT*1000+204 12100 Sunrise Valley Drive, Suite 220

Reston, VA 20191

PH 703.657.7300

FX 703.657.7301

Dominion [n~ineerin~, Inc.

Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page ---=--'-----

34 of --'-'-----

41 CP,1501,UZ,164,NT*1000+164 CP,1502,UZ,204,NT*1000+204

ENDIF

ENDIF

/COM, Define a few components for later use

USE,CMMAKER,201,500, 'NHEAD', 'EHEAD'

USE,CMMAKER,1,200,'NVESSEL', 'EVESSEL'

USE,CMMAKER,221,500, 'NHEADR', 'EHEADR'

/COM, Define pressure surfaces for PSOLV macro NSEL,S,NODE,,1,99999,10

/COM, Select additional nodes which form crevice between flanges out to the

/COM, inner a-ring NSEL,A,NODE,,161,99999,1000 NSEL,A,NODE,,162,99999,1000 NSEL,A,NODE,,163,99999,1DOO NSEL,A,NODE,,201,99999,1000 NSEL,A,NODE, ,202,99999,1000 NSEL,A,NODE, ,203,99999,1000 CM, PSURF, NODE NSEL,ALL SHPP CHECK

END

/COM,

/COM, --------------------- -------------------------------------------------------------

/COM, END GEOMETRY MACRO

/COM, ********************* *************************************************************

/COM,

/COM, ********************* *************************************************************

/COM, CREATE CMMAKER MACRO

/COM, --------------------- -------------------------------------------------------------

/COM,

CREATE, CMMAKER NSEL,NONE ESEL,NONE

DO,I,O,(NT-1)*100D,10DO NSEL,A,NODE,,ARG1+I,ARG2+I

IF,I,EQ,(NT-1)*1000,THEN

IF,NT,LT,NV,EXIT

END IF ESEL,A,ELEM,,ARG1+I,ARG2+I

ENDDO CM,ARG3,NODE CM,ARG4,ELEM NSEL,ALL ESEL,ALL

END

/COM,

/COM, --------------------- -------------------------------------------------------------

/COM, END CMMAKER MACRO

/COM, ********************* *************************************************************

/COM,

/COM. **********************************************************************************

/COM, CREATE GEOMCLUP MACRO

/COM, --------------------- -------------------------------------------------------------

/COM,

CREATE,GEOMCLUP CPDELE,ALL,ALL CMDELE,NHEAD CMDELE,EHEAD CMDELE,NVESSEL CMDELE,EVESSEL CMDELE,NHEADR CMDELE,EHEADR 12100 Sunrise Valley Drive, Suite 220

Reston, VA 20191

PH 703.657.7300

FX 703.657.7301

Dominion [n~ineerin~, Inc.

Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: - - 35 of _ 41 Page _ ....=....:;....___ __:_;....__ _

EDELE,ALL NDELE,ALL

END

/COM,

/COM, --------------------- -- - -- -- ----- -- -----------------------------------------------

/COM, END CMMAKER MACRO

/COM, ********************* ************** ***********************************************

/COM, ********************* ****** ******** ***********************************************

/COM,

/COM, ********************* *************************************************************

/COM, CREATE ENDPOST MACRO

/COM, --------------------- -- - -- - - - - ------- ---------------------------------------------

/COM, RLIST columns as foll ows:

/COM, RLIST(J,1) =Flange Displ. last pass

/COM, RLIST(J,2) = Stud Initial Elongation Real Constant

/COM, RLIST(J,3) = Stud Final Membrane Stress

/COM, RLIST(J,4) = Stud Max. Membrane+Bending Stress

/COM, RLIST(J,S) =Maximum Membrane Stress during any pass

/COM, RLIST(J,6) = Pass Number at which Max. Membrane Stress Occurs

/COM,

/COM, RLIST(J, 7) = Angular Rotation of Upper Flange (radians)

/COM, RLIST(J ,8) = Angular Rotation of Lower Flange (radians)

/COM, RLIST(J,9) = Inner 0-ring separation

/COM,

/COM, RLIST(J,10) = Force on Contact Link Element

/COM, RLIST(J,11) =Global X Shear Force on Coupled Set

/COM, RLIST(J,12) =Global Y Shear Force on Coupled Set

/COM,

/COM, RLIST(J,13) = Mu Required to Prevent Flange Mating Surf. Slide

/COM, RLIST(J,14) = Mu Required to Prevent Flange Stud Washer Slide

/COM,

/COM, Cut Plane Stress Intensities:

/COM, Line 1 -Vessel Far Field Cut Plane (RLIST(J,15) to RLIST(J,19))

/COM, RLIST(J,15) = Linearized 51 at Inner Surface

/COM, RLIST(J,16) = Linearized 51 at Center of Surface (Membrane 51)

/COM, RLIST(J,17) = Linearized 51 at Outer Surface

/COM, RLIST(J,18) =Total 51 at Inner Surface

/COM, RLIST(J,19) =Total 51 at Outer Surface

/COM,

/COM, Line 2 - Vessel Local Cut Plane - Lower (RLI ST (J, 20) to RLIST(J, 24))

/COM, Line 3 - Vessel Local Cut Plane - Middle (RLIST(J, 25) to RLIST(J, 29))

/COM, Line 4 - Vessel Local Cut Plane - Upper (RLIST(J, 30) to RLIST(J, 34))

/COM, Line 5 - Head Local Cut Plane - Lower (RLIST(J, 35) to RLIST(J,39))

/COM, Line 6 - Head Local Cut Plane - Middle (RLIST(J, 40) to RLIST(J,44))

/COM, Line 7 - Head Local Cut Plane - Upper (RLIST(J, 45) to RLIST(J,49))

/COM, Line 8 - Head Far Field Cut Plane (RLIST(J, SO) to RLIST(J,S4))

/COM,

CREATE,ENDPOST

/COM, Finish by loading results in RLIST

DO,J,1,NT ENUMB = J*1000-498 ! El. no. of subject element

GET,RLIST(J,3),ELEM,ENUMB,ETAB,MEMBSTRS ! El. membrane stress

GET,DUMBOT,ELEM,ENUMB,ETAB,MAXM+BI ! El. membrane+bend stress (I)

GET,DUMTOP,ELEM,ENUMB,ETAB,MAXM+BJ ! El. membrane+bend stress (J)

RLIST(J,4) = DUMBOT > DUMTOP

/COM, RSYS, 21 NNUM1 = (J-1)*1000+131 ! Node 131 NNUM2 = (J-1)*1000+139 ! Node 139 NNUM3 = (J-1)*1000+211 ! Node 211 NNUM4 = (J-1)*1000+219 ! Node 219 RLIST(J,7) = (UZ(NNUM4)-UZ(NNUM3))/flwdth ! Upper Flange Rotation (radians)

RLIST(J,8) = (UZ(NNUM2)-UZ(NNUM1))/flwdtv ! Lower Flange Rotation (radians)

NNUM1 = (J-1)*1000+164 NNUM2 = (J-1)*1000+204 RLIST(J,9) = UZ(NNUM2)-UZ(NNUM1)+iormo*(RLIST(J,8)-RLIST(J,7))

/COM, ENUMB = (J-1)*1000+501 ! El. no. 501

GET,RLIST(J,10),ELEM,ENUMB,ETAB,FORCE ! El. Force CMSEL,S,EHEAD NSEL,S,NODE,,(J-1)*1000+204 12100 Sunrise Valley Drive, Suite 220

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Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page 36 _ of _ 41 FSUM ESEL,ALL NSEL,ALL

GET, RLI ST (J , 11) , FSUM, , ITEM, FX ! Global X-Shear Force

GET,RLIST(J,12),FSUM,,ITEM,FZ ! Global Z-Shear Force

! RLIST(J,13) is resultant shear divided by link membrane force

IF,RLIST(J,10),LT, - 1.0,THEN RLIST(J,13) = -SQRT(RLIST(J,11)""2+RLIST(J,12)**2)/RLIST(J,10)

ELSE RLIST(J,13) = -1 ! Trap divide by zero

ENDIF SLIPCNST = 2*Is/(Ds*SWRC*As) ! Constants in washer slip calc

IF,RLIST(J,3),GT,1.0,THEN RLIST(J,14) = SLIPCNST*(RLIST(J,4)-RLIST(J,3))/RLIST(J,3)

ELSE RLIST(J,14) * - 1 ! Trap divide by zero

ENDIF

/COM,

/COM, Cut Lines:

USE,READSI,11,15,21,15,J ! Cut 1: Nodes 11 to 15 in CSYS 21

USE,READSI,61,65,21,20,J ! Cut 2: Nodes 61 to 65 in CSYS 21

USE,READSI,71,75,21,25,J ! Cut 3: Nodes 71 to 75 in CSYS 21

USE,READSI,81,85,21,30,J ! Cut 4: Nodes 81 to 85 in CSYS 21

USE,READSI,261,264,24,35,J ! Cut 5: Nodes 261 to 261 in CSYS 24

USE,READSI,271,274,24,40,J ! Cut 6: Nodes 271 to 274 in CSYS 24

USE,READSI,281,284,24,45,J ! Cut 7: Nodes 281 to 284 in CSYS 24

USE,READSI,351,354,24,50,J ! Cut 8: Nodes 351 to 354 in CSYS 24

ENDDO

END

/COM, ----------------------------------------------------------------------------------

/COM, END ENDPOST MACRO

/COM, **********************************************************************************

/COM,

/COM, **********************************************************************************

/COM, CREATE PRINTENS MACRO

/COM, ------------------ --- ------------------------------------------ -------------------

/COM,

/COM, PRINTENS arguments as follows:

/COM, ARG1 = PSAVE Text

/COM, ARG2 = RSAVE Text

/COM, ARG3 = Loop Ending No.

/COM, ARG4 =Free Text Field (e.g., 'Existing')

/COM, ARG5 = Sequence Print Flag (1 = Print Sequence)

/COM,

CREATE,PRINTENS

DO,K,1,ARG3

VWRITE,K

('-----',/,'Tensioning Sequence Iteration ',F2.D)

VWRITE, ARG4

('-----',/,A,' Procedure Results-')

VWRITE (2/,'Stud Stress Summary',/)

VSCFUN,MAXCOL1,MAX, %ARG2%(1, 3,K)

VSCFUN,MINCOL1,MIN, %ARG2%(1, 3,K)

VSCFUN,AVECOL1,MEAN,%ARG2%(1, 3,K)

VSCFUN,MAXCOL2,MAX, %ARG2%(1, 4,K)

VSCFUN,MINCOL2,MIN, %ARG2%(1, 4,K)

VSCFUN,AVECOL2,MEAN,%ARG2%(1, 4,K)

VSCFUN,MAXCOL3,MAX, %ARG2%(1, 5,K)

VSCFUN,MINCOL3,MIN, %ARG2%(1, 5,K)

VSCFUN,AVECOL3,MEAN,%ARG2%(1, 5,K)

VSCFUN,MAXCOL4,MAX, %ARG2%(1,14,K)

VSCFUN,MINCOL4,MIN, %ARG2%(1,14,K)

VSCFUN,AVECOL4,MEAN,%ARG2%(1,14,K)

/COM, MEMBRANE MEMB+BEND MAX. MEM. REQUIRED

/COM, STRESS STRESS STRESS WASHER MU 12100 Sunrise Valley Drive, Suite 220

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Title:

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37 of _....:....:.,_

41

VWRITE, 'MAXIMUM' ,MAXC0Ll,MAXCOL2,MAXCOL3,MAXCOL4 (A7,3X,3(F9.0,3X),3X,F7.4)

VWRITE, 'MINIMUM',MINCOL1,MINCOL2,MINCOL3,MINCOL4 (A7,3X,3(F9.0,3X),3X,F7.4)

VWRITE, 'AVERAGE',AVECOLl,AVECOL2,AVECOL3,AVECOL4 (A7,3X,3(F9.0,3X),3X,F7.4)

VWRITE (2/, 'Head and Head Flange Cut Planes Stress Summary',/)

VSCFUN,AVECOLl,MEAN,%ARG2%(1,51,K)

VWRITE,AVECOLl

('General Membrane Stress Intensity ', F6.0)

VSCFUN,MAXCOL1,MAX,%ARG2%(1,36,K)

VSCFUN,MAXCOL2,MAX,%ARG2%(1,41,K)

VSCFUN,MAXCOL3,MAX,%ARG2%(1,46,K)

MAXCOL4 = MAXCOLl > MAXCOL2 > MAXCOL3

VWRITE, MAXCOL4

('Maximum Local Membrane Stress Intensity ', F6.0)

VSCFUN,MAXCOL1,MAX,%ARG2%(1,35,K)

VSCFUN,MAXCOL2,MAX,%ARG2%(1,40,K)

VSCFUN,MAXCOL3,MAX,%ARG2%(1,45,K)

MAXCOL4 = MAXCOLl > MAXCOL2 > MAXCOL3

VSCFUN,MINCOL1,MAX,%ARG2%(1,37,K)

VSCFUN,MINCOL2,MAX,%ARG2%(1,42,K)

VSCFUN,MINCOL3,MAX,%ARG2%(1,47,K)

MINCOL4 = MINCOLl > MINCOL2 > MINCOL3

VWRITE,MAXCOL4 > MINCOL4

('Maximum Local Mem + Bend Stress Intensity ', F6.0)

VSCFUN,MAXCOL1,MAX,%ARG2%(1,38,K)

VSCFUN,MAXCOL2,MAX,%ARG2%(1,43,K)

VSCFUN,MAXCOL3,MAX,%ARG2%(1,48,K)

MAXCOL4 - MAXCOLl > MAXCOL2 > MAXCOL3

VSCFUN,MINC0Ll,MAX,%ARG2%(1,39,K)

VSCFUN,MINCOL2,MAX,%ARG2%(1,44,K)

VSCFUN,MINCOL3,MAX,%ARG2%(1,49,K)

MINCOL4 = MINCOLl > MINCOL2 > MINCOL3

VWRITE,MAXCOL4 > MINCOL4

('Maximum Local Stress Intensity ', F6.0)

VWRITE (2/,'Vessel and Vessel Flange Cut Planes Stress Summary',/)

VSCFUN,AVECOL1,MEAN,%ARG2%(1,16,K)

VWRITE,AVECOLl

('General Membrane Stress Intensity ', F6.0)

VSCFUN,MAXCOLl,MAX,%ARG2%(1,2l,K)

VSCFUN,MAXCOL2,MAX,%ARG2%(1,26,K)

VSCFUN,MAXCOL3,MAX,%ARG2%(1,31,K)

MAXCOL4 = MAXCOLl > MAXCOL2 > MAXCOL3

VWRITE, MAXCOL4

('Maximum Local Membrane Stress Intensity ', F6.0)

VSCFUN,MAXCOL1,MAX,%ARG2%(1,20,K)

VSCFUN,MAXCOL2,MAX,%ARG2%(1,25,K)

VSCFUN,MAXCOL3,MAX,%ARG2%(1,30,K)

MAXCOL4 = MAXCOLl > MAXCOL2 > MAXCOL3

VSCFUN,MINCOL1,MAX,%ARG2%(1,22,K)

VSCFUN,MINCOL2,MAX,%ARG2%(1,27,K)

VSCFUN,MINCOL3,MAX,%ARG2%(1,32,K)

MINCOL4 = MINCOLl > MINCOL2 > MINCOL3

VWRITE,MAXCOL4 > MINCOL4

('Maximum Local Mem + Bend Stress Intensity ', F6.0)

VSCFUN,MAXCOL1,MAX,%ARG2%(1,23,K)

VSCFUN,MAXCOL2,MAX,%ARG2%(1,28,K)

VSCFUN,MAXCOL3,MAX,%ARG2%(1,33,K)

MAXCOL4 = MAXCOLl > MAXCOL2 > MAXCOL3

VSCFUN,MINCOL1,MAX,%ARG2%(1,24,K)

VSCFUN,MINCOL2,MAX,%ARG2%(1,29,K) 12100 Sunrise Valley Drive, Suite 220

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Title:

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VSCFUN,MINCOL3,MAX,%ARG2%(1,34,K)

MINCOL4 = MINCOLl > MINCOL2 > MINCOL3

VWRITE,MAXCOL4 > MINCOL4

('Maximum Local Stress Intensity ',F6.0)

VSCFUN,MAXC0Ll,MAX,%ARG2%(1,9,K)

VWRITE, MAXCOLl (2/,'Maximum Inner 0-Ring Separation is ',F7.5,' inches.')

VSCFUN,MAXCOLl,MAX,%ARG2%(1,13,K)

VWRITE, MAXCOLl

('Required Mating Surface Mu to Prevent Slip is ',F7.5,'. ')

IF,ARGS,EQ,l,THEN

VWRITE, ARG4

('---- - ',/,A,' Procedure - Sequence Listing',/)

/COM, SET NO. STUD NO. PRESSURE RETEN. FLAG

VWRITE,SEQU,%ARG1%(1,1,K),%ARG1%(1,2,K),%ARG1%(1,4,K)

(4(F9. 0, 3X))

ENDIF

VWRITE, ARG4

('-----',/,A,' Procedure Results- Stud Stresses',/)

/COM, MEMBRANE MEMB+BEND MAX. MEM. ACHIEVED REQUIRED

/COM,STUD # STRESS STRESS STRESS @ SET NO. WASHER MU

VWRITE,SEQU,%ARG2%(1,3,K),%ARG2%(1,4,K),%ARG2%(1,5,K),%ARG2%(1,6,K),%ARG2%(1,14,K)

(F5.0,5X,4(F9.0,3X),2X,F7.4)

VWRITE, ARG4

('-----',/,A,' Procedure Results- Flange Contact Forces',/)

/COM, GLOBAL GLOBAL REQUIRED

/COM,STUD # LINK FORCE X SHEAR Z SHEAR FLANGE MU

VWRITE,SEQU,%ARG2%(1,10,K),%ARG2%(1,11,K),%ARG2%(1,12,K),%ARG2%(1,13,K)

(F5.0,3X,3(E11.4,2X),2X,F7.4)

VWRITE, ARG4

('-----',/,A,' Procedure Results- Flange Deflections',/)

/COM, UPPER FLANGE LOWER FLANGE 0-RING

/COM,STUD # ROTATION ROTATION SEPARATION

VWRITE,SEQU,%ARG2%(1,7, K) ,%ARG2%(1,8,K), %ARG2%(1,9,K)

(F5.0,4X,3(E11.4,4X))

CLNO = 0

DO, Ll, 15, 50,5 CLNO = CLNO+l L2 = Ll+l L3 = L1+2 L4 = L1+3 LS = L1+4

VWRITE,ARG4,CLNO

('-----',/,A,' Procedure Results - Cut Line ',F2. 0, / )

/COM, INNER CENTER OUTER INNER OUTER

/COM,STUD # LIN. S.I. LIN. S.I. LIN. S.I. TOT. S.I. TOT. S.I.

VWRITE,SEQU,%ARG2%(l,Ll,K), %ARG2%(l,L2,K),%ARG2%(1,L3,K), %ARG2%(1,L4,K),%ARG2%(1,LS,K)

(F5.0,2X,S(F9.0,3X))

ENDDO

ENDDO

END

/COM, --------------------- ------------------------------------------ -------------------

/COM, END PRINTENS MACRO

/COM, *************************************************************** *******************

/COM,

/COM, **********************************************************************************

/COM, *************************************************************** *******************

/COM, CREATE PRINTOLR MACRO

/COM, --------------------------------------------------------------- -------------------

/COM,

/COM, PRINTOLR arguments as follows:

/COM, ARGl = RSAVE ARRAY TEXT (e.g., 'RSAVE7')

/COM, ARG2 =Case Type (e.g., 'II')

/COM, ARG3 = Starting Case No.

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Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: - - Page - =

39 - of _....:....:.__

41

/COM, ARG4 = Ending Case No.

/COM, ARGS = Starting Vessel Cut Plane No.

/COM, ARG6 = Ending Vessel Cut Plane No.

/COM, ARG7 = Starting Head Cut Plane No.

/COM, ARG8 = Ending Head Cut Plane No.

/COM,

CREATE,PRINTOLR

/COM,

IF ,ARG2, EQ, 'II', THEN INDADD = 5

ELSE INDADD = 0

ENDIF

DO,K,ARG3,ARG4

VSCFUN,MAXCOL1,MAX,%ARG1%(1,3,K) STABLEC2(INDADD+K,2) = MAXCOL1/1000

VSCFUN,MINCOL1,MIN,%ARG1%(1,3,K) STABLEC2(INDADD+K,1) = MINCOL1/1000

VSCFUN,AVECOL1,MEAN,%ARG1%(1,3,K)

VSCFUN,MAXCOL2,MAX,%ARG1%(1,4,K) STABLEC2(INDADD+K,3) = MAXCOL2/1000

VSCFUN,MINCOL2,MIN,%ARG1%(1,4,K)

VSCFUN,AVECOL2,MEAN,%ARG1%(1,4,K)

VSCFUN,MAXCOL3,MAX,%ARG1%(1,5,K)

VSCFUN,MINCOL3,MIN,%ARG1%(1,5,K)

VSCFUN,AVECOL3,MEAN,%ARG1%(1,5,K)

VSCFUN,MAXCOL4,MAX,%ARG1%(1,14,K)

VSCFUN,MINCOL4,MIN,%ARG1%(1,14,K)

VSCFUN,AVECOL4,MEAN,%ARG1%(1,14,K)

VWRITE, ARG2, K

('-----',/,'Elongation Tolerance Case C' ,A2,'-' ,F2.0,/)

VWRITE,ARG2

('Level ',A2,' Elongation Tolerance Results- Stud Stresses',/)

/COM, MEMBRANE MEMB+BEND MAX. MEM. ACHIEVED REQUIRED

/COM,STUD # STRESS STRESS STRESS @SET NO. WASHER MU

VWRITE,SEQU,%ARG1%(1,3,K),%ARG1%(1,4,K),%ARG1%(1,5,K),%ARG1%(1,6,K),%ARG1%(1,14,K)

(FS.O,SX,4(F9.0,3X),2X,F7.4)

VWRITE,ARG2

('-----',/,'Level ',A2,' Elongation Tolerance Results - Flange Contact Forces',/)

/COM, GLOBAL GLOBAL REQUIRED

/COM,STUD # LINK FORCE X SHEAR Z SHEAR FLANGE MU

VWRITE,SEQU,%ARG1%(1,10,K),%ARG1%(1,11,K),%ARG1%(1,12,K),%ARG1%(1,13,K)

(F5.0,3X,3(E11.4,2X),2X,F7.4)

VWRITE, ARG2

('-----',/,'Level ',A2,' Elongation Tolerance Results- Flange Deflections',/)

/COM, UPPER FLANGE LOWER FLANGE D-RING

/COM,STUD # ROTATION ROTATION SEPARATION

VWRITE,SEQU,%ARG1%(1,7,K),%ARG1%(1,8,K),%ARG1%(1,9,K)

(F5.0,4X,3(E11.4,4X))

CLNO = 0

DO, L1, 15, 50,5 CLNO = CLN0+1 L2 = L1+1 L3 = L1+2 L4 = L1+3 LS = L1+4

VWRITE,ARG2,CLNO

('-----',/,'Level ',A2,' Elongation Tolerance Results - Cut Line ',F2.0,/)

/COM, INNER CENTER OUTER INNER OUTER

/COM,STUD # LIN. S.I. LIN. S.I. LIN. S.I. TOT. S.I. TOT. S.I.

VWRITE,SEQU,%ARG1%(1,L1,K),%ARG1%(1,L2,K),%ARG1%(1,L3,K),%ARG1%(1,L4,K),%ARG1%(1,LS,K)

(F5.0,2X,S(F9.0,3X))

ENDDO

DO,L,ARG7,ARG8

VSCFUN,TMPMAXSI,MAX,%ARG1%(1,L*5+13,K)

.TABLEC2(INDADD+K,4) = TMPMAXSI > TABLEC2(INDADD+K,4)

VSCFUN,TMPMAXSI,MAX,%ARG1%(1,L*5+14,K)

TABLEC2(INDADD+K,4) = TMPMAXSI > TABLEC2(INDADD+K,4)

ENDDO

DO,L,ARGS,ARG6

VSCFUN,TMPMAXSI,MAX,%ARG1%(1,L*5+13,K)

TABLEC2(INDADD+K,S) = TMPMAXSI > TABLEC2(INDADD+K,S)

VSCFUN,TMPMAXSI,MAX,%ARG1%(1,L*5+14,K) 12100 Sunrise Valley Drive, Suite 220

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Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page _....:....;'----

40 of 41 TABLEC2(INDADD+K,S) = TMPMAXSI > TABLEC2(INDADD+K,S)

ENDDO TABLEC2(INDADD+K,4) = TABLEC2(INDADD+K,4)/1000 TABLEC2(INDADD+K,S) = TABLEC2(INDADD+K,S)/1000

ENDDO

END

/COM, ------------- - ------------------------------------------------- -------------------

/COM, END PRINTOLR MACRO

/COM, **********************************************************************************

/COM, ************* *********************************************************************

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Title:

Hatch Unit 2 Operation with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page 41 of 41 B SOFTWARE USAGE RECORDS The following table lists the Software Usage Records for the ANSYS analyses performed in support of this calculation. These records are included on the Data Disk D-3944-00-01 [6] in their native electronic formats. This data disk is retained with the Task 3944 project file and is available for on-site review by Southern Nuclear personnel.

File Name Description

- HA TCH2.runs Input file which sets run parameters and performs the closure flange evaluation cases.

- MACROS.HA TCH2 Input file which sets the finite element model geometry and boundary conditions specific to the Hatch Unit 2 RPV model.

- MACROS.DEI Input file which performs stud tensioning and closure flange analyses.

RESUL TS.OUT Formatted output file which contains the stud stress results for the closure flange analysis cases.

- HATCH2.out Full output file generated automatically which includes every ANSYS operation performed throughout the analysis.

HATCH2 .err Automatically generated error file which includes all warnings generated during the analysis.

Hatch 2 Stud Primary Stress Microsoft Excel spreadsheet used to perform stud primary stress Calc vO.xlsx calculations.

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v t e Letter Sequence Request
EPID:L-2018-LLR-0137, Relief Request Reactor Pressure Vessel Stud HNP-ISI-RR-05-02 (Open)
Initiation Request Acceptance Administration Questions Answers Results Approval... Other: ML19035A550
MONTHYEAR2018-11-05 [Table View]

NL-18-1336, Relief Request Reactor Pressure Vessel Stud HNP-ISI-RR-05-02

Text

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