Text

Inservice Inspection Program, Owner'S Activity Report for Outage 2R24
	ML17150A460
Person / Time
Site:	Hatch
Issue date:	05/30/2017
From:	Wheat J; Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NL-17-0951
	Download: ML17150A460 (75)
	v • d • e

/

~ Southern Nuclear Justin T. Wheat Nuclear Licensing Manager 40 lm~me'~ Cemcr Pari.. way Post Oflice Box I::!95 Btrnungham. AI 35::!42 205 992 5998 tel 205 992 76{JI fax jtwhcat<ii 1 ~ou therncu.cont May 30,2017 Docket Nos.: 50-366 NL-17-0951 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant- Unit 2 lnservice Inspection Program Owner's Activity Report for Outage 2R24 Ladies and Gentlemen:

Enclosed is the ASME Section XI Code Case N-532-4 OAR-1 Owner's Activity Report for the 2R24 Refueling Outage. Table 1, "Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service," lists evaluations performed for continued service, and is provided as Enclosure 2. Table 2, "Abstract of Repairs, Replacement or Corrective Measures Required for Continued Service," lists repair/replacement activities, and is provided as Enclosure 3. The SNC indication notification form (INF) 117H2001 and associated documents (Relief Request and Calculation) for "Reactor Pressure Vessel (RPV) Head Stud #33 Found with a Flaw Indication," are provided as Enclosure 4.

This report is for the first period of the 51h Interval lSI activities (Interval 5, Period 1, Outage 1).

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at 205.992.7369.

Respectfully submitted, C).:t; .<~

~eat Nuclear Licensing Manager JTW/RMJ

Enclosures:

1. 2R24 Form OAR-1 Owner's Activity Report

2. 2R24 Form OAR-1 Owner's Activity Report, Table 1, Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service

3. 2R24 Form OAR-1 Owner's Activity Report, Table 2, Abstract of Repairs, Replacement or Corrective Measures Required for Continued Service

4. Indication Notification Form (INF) 117H2001 and Associated Documents (Relief Request and Calculation) for "Reactor Pressure Vessel (RPV) Head Stud #33 Found with a Flaw Indication."

U.S. Nuclear Regulatory Commission NL-17-0951 Page 2 cc: Regional Administrator, Region II NRR Project Manager- Hatch Senior Resident Inspector- Hatch RTYPE: CHA02.004

Edwin I. Hatch Nuclear Plant - Unit 2 lnservice Inspection Program Owner's Activity Report for Outage 2R24 Enclo~ure 1 2R24 Form OAR-1 Owner's Activity Report

Fonn OAR-1 -Owner's Activity Report Report NlOber 2-5-1-1 (Unit 2, 5th Interval, pt Period, 151 Report)

Owner Southern Nuclear Operating Co (agent for Georgia Power)- 40 Inverness Center Parkway, Birmingham, AL 35242 Plant Edwin I. Hatch Nuclear Plant -11028 Hatch Parkway North, Baxley, Georgia 31513 (Bin 63010)

Unit No. --....,-----:;2:;---;.-;-;--- Commercial Service Date 09/05/1979 Refueling Outage No. 2R24 (if applicable)

Current Inspection Interval (1", 2'0 , 3' 0 , 4'". other)

Current inspection Period (1*, :!"", 3"')

Ecfltion and Addenda of Section XI Applicable to the 2001 Edition through 2003 Addenda (NDE, Pressure Test, and R~R)

Inspection Plans 2007 Edition through 2008 Addenda (All Other)

Volume 1 - 02103fl017 (Version 2.0}, Volume 2 - 0210312017 (Version 1.0), Volume 3-01fl5f2017 (Version 1.0), Volume 4- 01126fl017 (Version 1.0), Volume 5- 01fl7fl017 Date and Revision of Inspection Plans (Version 1.0), and 2R24 Outage Plan: 02/0312017 (Version 1.0)

Edition and Addenda of Section XI Applicable to Repair/Replacement Activities (If different than the Inspection Plans} Same Code Cases Used: N-460, N-513-3, N-526, N-532-5, N-586-1, N-716-1, N-747, and N-805 frl applicable}

Signed Date _s~/r--::2.....:.4..&..:U__,7_ __

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Georgia and employed by The Hartford Steam Boiler Inspection and Insurance Company of Hartford. CT have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

C l~ck~'sco ~/--.---- Commissions CA-~38' /JfS-I'ttJC:08: A IJI-Insp~ National Board, State, Province, and Efidorsements Date os./'2-S /17

Edwin I. Hatch Nuclear Plant - Unit 2 lnservice Inspection Program Owner's Activity Report for Outage 2R24 1 Enclosure 2 2R24 Form OAR-1 Owner's Activity Report, Table 1, Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service

Table 1 - Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Edwin I. Hatch Nuclear Plant- Unit 2 (Cycle 24)

Examination Category Item Description Evaluation Description and Item Number Dominion Engineering, Inc. Calculation C-3944-00-01 Reactor Pressure Vessel (RPV) Head Stud #33 Found (Revision 0) shows that all studs would continue to B-G-1 (86.20) 1 with a Flaw Indication meet ASME Code Requirements for primary loads with one ( 1) stud out of service.

Flaw was evaluated in accordance with Code Case N-Through Wall Leak on 10" Plant Service Water Piping D-2 (02.10) 513-3 and the impacted piping was replaced under (Near 2P41-F067 in the Unit 2 Torus Room)

SNC8011 09 during 2R24.

Through Wall Leak on 4" Plant Service Water Pipe Flaw was evaluated in accordance with Code Case N-D-2 (02.10) Stub (Upstream of 2P41-F1176 in the Unit 2 Torus 513-3 and the impacted piping was replaced under Room) SNC823336 during 2R24.

A Site Evaluation determined that the loose jam nuts Loose Jam Nuts on Snubbers 2N11-MS-R45A and did not impact the functionality of the support, but the F-A (F1.20S) 2N11-MS-R45B noted condition should be corrected in a timely manner.

Note 1

Enclosure 4 contains Calculation C-3944-00-001 (Revision 0) as part of the Relief Request (HNP-ISI-RR-05-01) sent to the NRC for Hatch Nuclear Plant to startup from 2R24 with a flaw indication on one (1) RPV Stud.

Page 1 of 1

Edwin I. Hatch Nuclear Plant- Unit 2 lnservice Inspection Program Owner's Activity Report for Outage 2R24 Enclosure 3 2R24 Form OAR-1 Owner's Activity Report, Table 2, Abstract of Repairs, Replacement or Corrective Measures Required for Continued Service

Table 2- Abstract of Repairs, Replacement or Corrective Measures Required for Continue Service Edwin I. Hatch Nuclear Plant- Unit 2 (Cycle 24)

Code Class Item Description Description of Work Date Com pleted R&R Work Order Replaced Missing Cotter Pin on 2B21-MS-R39A (Found-1 Snubber 02/22/2017 SNC711486 during the 2R24 VT-3 Examination)

Tightened Jam Nut on the Lower Mounting Bolt and 2 Support Replaced a Bushing Spacer on the Top Mount of 2E21-CS- 02/22/2017 SNC844902 R40 (Found during the 2R24 VT-3 Examination) 10" Plant Service Replaced Leaking 10" Plant Service Water Pipe (Near 2P41-3 02/20/2017 SNC801109 Water Pipe F067 in the Unit 2 Torus Room) 4" Plant Service Replaced Leaking 4" Plant Service Water Pipe Stub 3 02/20/2017 SNC823336 Water Pipe Stub (Upstream of 2P41-F1176 in the Unit 2 Torus Room)

Page 1 of 1

Edwin I. Hatch Nuclear Plant - Unit 2 lnservice Inspection Program Owner's Activity Report for Outage 2R24 Enclosure 4 Indication Notification Form (INF) 117H2001 and Associated Documents (Relief Request and Calculation) for "Reactor Pressure Vessel (RPV) Head Stud #33 Found with a Flaw Indication."

FIGURE 1 Page 1 of 1 INDICATION NOTIFICATION FORM INF-Fonn-002-A INF # 117H2001 Part 1 Fmdinqs During lSI Ultrasonic Examination of the Hatch 2 reador pressure vessel studs 1-56, an indication was found at location 33 as marked on the flange. The indication was located 41.7 inches from the top of RPVstud.

Exam Date: NDE Method:

02-07-2017 UT X PT 0 MT 0 ET 0 RT 0 VT 0 Other 0 Comments:

Hatch CR 10327745 was written for the UT Indication for RPV Stud at location 33. It was recommended to remove this stud so a supplemental surface examination could be performed.

02-08-2017 Notification Acknowledged By: - - - .

~ ~

Date:

o'Z.I ,., \W ,.,

Comments:

SE-~ A.~ 5..:>PPL~\--\:t0\~ 5\-\~\S Corrective Action:

St~ er.~ Sv~....-\:J0f~ 5\-\Ec"fS Part 4a - Re-Examination After Corrective Action SEE ~~C\-\~0 ~~0\..E-t---\f-t-..Jrbl.. S~TS Signature - Examiner: SNTLevel:

Nl~-~\" ~~ 1'-l I A.-....,.,.,- ~~el.E:

Part 4b- Additional Examinations <Scope Expansions)

Part 4c- Successive Examinations (Future Exam Reauirementsl Date:

Date:

Indication Notification Form 117-H2-001 (Supplemental Sheet)

Part 3 - Disposition by Project/Site Comments:

HNP-ISI-ALT-05-01 (Alternative Proposing Continued Use of ASME Section XI 2001 Ed/2003 Addenda for Portion of the Fifth lnservice inspection Interval) and ML15352A294 (Edwin I. Hatch Nuclear Plant, Unit 1 and 2- Relief from the Requirements of the ASME Code), Edwin I. Hatch Nuclear Plant is permitted to use ASME Section XI 2001 Edition through 2003 Addenda in combination with the 2007 Edition through the 2008 Addenda for certain in service inspection and containment in service inspection activities from January 1st, 2016 through November 30th, 2017.

ASME Section XI (2007 Edition through 2008 Addenda)

Section IWB-2500(b)

Examination Category- B-G-1 Examination Area -Pressure Retaining Bolting, Greater Than 2 in. (50 mm) in Diameter Table IWB-2500-1 (Examination Categories)

Item No. - B6.20 Parts Examined- Reactor Vessel, Closure Studs Examination Requirements -IWB-2500-12 Examination Method - Volumetric Acceptance Criteria -IWB-3515 ASME Section XI (2001 Edition through 2003 Addenda)

Section IWB-3515 (Standards for Examination Category B-G-1, Pressure Retaining Bolting Greater Than 2 in. (51 mm) in Diameter Section IWB-3515.2 (Allowable Flaws for Volumetric Examinations of Studs and Bolts)

Paragraph (c) - Any flaw detected by the 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.

Indication Notification Form 117-H2-001 (Supplemental Sheet- Continued)

Corrective Actions:

Plan A - Work Order (WO) SNC843700 was generated to replace Reactor Pressure Vessel (RPV) Stud #33 during 2R24 (OSCR 12002).

Since Stud #33 could NOT be removed during the performance of SNC843700, Plan B will be utilized.

Plan B - Relief Request HNP-ISI-RR-05-01 (Deferment of Visual Examination for B-G-1 Bolting) and a Dominion Engineering, Inc. (DEl) Evaluation (Hatch Unit 2 Operation with One Stud Out of Service Evaluation) where sent to the Nuclear Regulatory Commission (NRC) as NL-17-0248 (Edwin I. Hatch Nuclear Plant- Unit 2 Relief Request Reactor Pressure Vessel Stud Inspection). Verbal Authorization by the Office of Nuclear Regulation for Relief Request HNP-ISI-RR-05-01 (Temporary Relief from Requirements of IWB-3515 of Section XI of the ASME Code) for Hatch Unit 2 was given on February 17, 2017 to leave Stud #33 as-is until 2R25 (Spring 2019), when it will be removed, examined, and replaced . Written relief request authorization will be issued within 150 days of 02/17/2017.

NL-17-0248 (48 Pages) and the NRC Verbal Authorization (3 Pages) have been attached to this INF.

ASME Section XI (2001 Edition through 2003 Addenda)

Section IWB-3132.3 (Acceptance by Analytical Evaluation)

A component whose volumetric or surface examination detects flaws that exceed the acceptance standards of Table IWB-3410-1 is acceptable for continued service without a repair /replacement activity if an analytical evaluation, as described in IWB-3600, meets the acceptance criteria of IWB-3600. The area containing the flaw shall be subsequently reexamined in accordance with IWB-2420(b) and (c).

The evaluation considered the stresses resulting from two (2) conditions which bound the effects of a stud out of service: (1) operation with one (1) stud left untensioned, and (2) the unlikely condition of a stud that is tensioned then fails in service. The result was that all studs would continue to meet ASME Code requirements for primary loads with one stud out of service. As such, the provided analysis/evaluation complies with Section IWB-3132.3.

Part 4a- Re-Examination After Corrective Action Plan A - The reexamination of Reactor Pressure Vessel Stud #33 will be performed in conjunction with WO SNC711486.

Since Stud #33 could NOT be removed during the performance of SNC843700, Plan B will be utilized.

Plan B- The reexamination of Reactor Pressure Vessel (RPV) Stud #33 will be performed after it is replaced during 2R25.

Part 4b- Additional Examinations (Scope Expansions)

Scope expansion is not required as all fifty six (56) Reactor Pressure Vessel Studs were examined during 2R24.

Part 4c- Successive Examinations (Future Exam Requirements)

The Reactor Pressure Vessel Stud #33 will be replaced during 2R25. As such, NO successive examinations will required on this component.

A. Southern Nuclear Charles R. Pierce Regulatory Affairs Director 40 lm*cmcss C~mcr Pitrl..wuy Pos1 Oflk~ !lox 1295 Bim1ingham. AL 35242 205 992 787:2 id 205 992 7601 fn crpicr~e@soulhemco com February 17, 2017 Docket Nos.: 50-366 NL-17-0248 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant - Unit 2 R~lief Request Reactor Pressure Vessel Stud Inspection 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-05-01. This Relief Request will allow Hatch Nuclear Plant (HNP) to startup from their current refueling outage with a flaw indication on one reactor pressure vessel (RPV) stud, in the event this stud cannot be removed from the RPV for a code-compliant examination or replacement. provides proposed Relief Request HNP-ISI-RR-05-01. Enclosure 2 provides the Dominion Engineering, Inc. (DEl) evaluation supporting operation with one stud out of service.

To support the current HNP Unit 2 refueling outage, Nuclear Regulatory Commission approval is requested by February 17, 2017.

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at 205.992.7369.

Respells~,

t.

C. R. Pierce Regulatory Affairs Director CRP/RMJ

U.S. Nuclear Regulatory Commission NL-17-0248 Page 2

Enclosures:

1. Proposed Relief Request HNP-ISI-RR-05-01

2. Dominion Engineering, Inc. (DEl) Evaluation cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. D. R. Vineyard, Vice President- Hatch Mr. M. D. Meier, Vice President- Regulatory Affairs Mr. D. R. Madison, Vice President- Fleet Operations Mr. B. J. Adams, Vice President- Engineering Mr. G. L. Johnson, Regulatory Affairs Manager- Hatch RTYPE: CHA02.0p4 U.S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. M. D. Orenak, NRR Project Manager- Hatch Mr. D. H. Hardage, Senior Resident Inspector- Hatch

Edwin I. Hatch Nuclear Plant - Unit 2 Relief Request Reactor Pressure Vessel Stud Inspection Enclosure 1 Proposed Relief Request HNP-ISI-RR-05-01 to NL-17-0248 Proposed Relief Request HNP-ISI-RR-05-01

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

References:

ASME Section XI, 2001 Edition through 2003 Addenda, IWB-3515.2 Examination Category: B-G-1 Examination Area: Pressure Retaining Bolting Greater Than 2 in. (50.8 mm) in Diameter Item Number(s): 86.20

2. Requested Date for Approval Approval is requested by February 17, 2017.

3. Applicable ASME Code Requirements ASME Section XI, 2001 Edition through 2003 Addenda, IWB-3515.2(c) Allowable Flaws for Volumetric Examination of Studs and Bolts The 2001 Edition through 2003 Addenda of ASME Section XI, IWB-3515.2(c) states: "Any flaw detected by the 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 volumetric examination (on 02/07/2017) on Unit 2 at the Edwin I. Hatch Nuclear Plant (hereinafter referred to as HNP2). During the lnservice Inspection (lSI) of the HNP2 RPV Studs (#1 through #56), a circumferential flaw indication was identified on location #33. The indication is located at a distance of 41.7 inches from the top of the RPV Stud. This correlates to just below or equal to the surface of the reactor vessel flange. The indication is approximately one inch {1 ") in length. Qualified Personnel and Procedures (to the requirements of ASME Section XI Appendix VIII) were utilized to perform the ultrasonic examination using a oo beam 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.

After discovery, an initial attempt was made to remove the stud prior to flooding the reactor cavity for fuel movement. This attempt was unsuccessful using on-site tooling. After draining down the reactor, two different methodologies (Basic Removal or Advanced Removal) are scheduled to remove the stud. The first attempt to remove the RPV Stud will utilize the E1-1 to NL-17-0248 Proposed Relief Request HNP-ISI-RR-05-01 "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, finishing removal of the stud using a stud runner tool, and installing the new stud. If the "Basic Removal" Technique is unsuccessful, the "Advanced Removal (Full STAR Tooling)" Technique will be 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, and installing a new stud.

These methods have been proven successful at other utilities. If both attempts are unsuccessful, significant additional planning will be needed for machining during the next refueling outage (2R25). This planning will be required to stage additional specialty tooling, establish contingencies, and determine methods to prevent potential damage to the RPV Head Flange.

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 are impractical based upon the time required to implement additional contingency actions.

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. Several attempts are scheduled and planned to remove RPV Stud #33 during the current refueling outage (2R24), using available tooling and techniques. In the unlikely event the stud cannot be removed, HNP2 will be unable to create a detailed plan to mobilize/create special equipment, and successfully remove the stud without damaging the RPV Head Flange without significantly extending the current refueling outage.

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 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 detensioned and a stud that fails in service. This evaluation demonstrates that the structural and leakage integrity of the RPV Head Joint will be maintained until the next refueling outage (2R25), when the RPV Stud will be removed. A Class 1 System Leakage Test conducted before start-up (from 2R24) will verify the integrity of the RPV Head Joint. The system leakage test pressure for Class 1 Systems shall correspond to rated RPV pressure (at least 1,045 psig) and be attained at a rate in accordance with the approved Pressure/Temperature Limit Curves and approved procedures. 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 during the current refueling outage (2R24) to perform the required surface examination (Liquid Penetrant or E1-2 to NL-17-0248 Proposed Relief Request HNP-ISI-RR-05-01 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 HNP2.

6. Duration of Proposed Relief Request This proposed relief request will be utilized from Mode 4 of the current refueling outage (2R24) until Mode 5 of the next refueling outage (2R25).

7. Precedents None E1-3

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

CALCULATION Dominion (nyinmin: Y Tille: Hatch Unit 2 Operation with One Slud Out of SeMce Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page 1 of 41 RECORD OF REviSIONS

~by Checked by Reviewed by Approved by Rev. Description oatJ. Date Date Date 0 Original Issue ~c~.J!5~ -,:c.~ l.t. ~ 1. .r.~ ...

-:z.lr(Qf:b1- 2/U/2ol1 '211&/P*J?- 1./tv/~,;

J.E. 8rousslud T.C. Ligon T.C. Ligm OJ. Gross Prinl:ipal EDgjDCCr Eugineer l!aAiDeer PriDcipal Eoaiuccr 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.

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 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

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 3 of 41 Last Mod.

Section Page Rev.

5.2.4.5 Emergency and Faulted Cond~ions ............................................ 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 LlhTINGS .................................................................................. 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 ill 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.

2 ~~ 'ti)I1-E. Broussard, ill, PE. Date irginia Certificate No. 032963 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 4 of 41 LIST OF TABLES Last Mod.

Table No. Rev.

Table 1. FEA Model Inputs 0 Table 2. Calculation of Phmary Stresses in Reactor Vessel Studs, One Stud Out of I 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

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 5 of 41 1 PURPOSE Dominion Engineering, Inc. (DEI) originally provided optimized tensioning and detensioning procedures for Plant Hatch in January 2015 [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: (1) operating with one stud left untensioned, and F) the unlikely condition of a stud that is tensioned then fail~ 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 5.1. 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-3937-00-01 [I] was used to perfonn 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:

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

2. The RPV inner o-ring radius is 111.0 inches [1, Table 3-3].

3. The RPV stud circle radius is 117.313 inches [I, Table 3-3].

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

5. The stud shank OD is 6.0 inches, the stud shank ID is 1.0 inches, and the stud shank cross section area is 27.489 in 2 [1, Table 3-1 ].

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

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 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 I .

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 [I].

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 (I]. 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 20 I5 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 of26.7 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:

I. 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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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 rad ius 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 [I].

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 I 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 (ll < 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.

l 0. All studs are assumed to be initially uniformly tensioned to the target stud elongation of 0.0397 inch, equivalent to a stud stress of37.146 ksi [1, Table 3-l].

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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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 ofthe stud cross section, we enforce the static equilibrium equations on the studs. Note that the linear distribution assumption is a consequence of Assumption 1. 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:

-PAl P(1rRn {I235psig}(;rx11I.0 2 in 2 )

F=-' = = =869.2 ktps [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 1. The offset &from the center of pressure is still an unknown at this point, however. The solution for &is achieved by writing the static equilibrium equations for the reactor head

[5-2]

L Mn = L F,(x,- c5)- PAd-!5) = 0 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 9 of 41 where F::: = net force in the direction parallel to the stud lengths Mn = net moment about the neutral axis x; = x-coordinate of each stud per the axes in Figure 1 B = 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 x; can be written in terms of the bolt-circle radius (R 0 ) and B; as defined in Figure I.

X1 =R"cos01 , where81 ={i-;~ 9 )x2~r [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, where/is a constant

[5-4]

Substituting Eq. [5-4] into the first of Eqs.[5-2] and taking advantage of the fact that L "F =PAir yields I

L:(F+f(x~-b'))-PA11 =0 ~ Lf(x~-b')=O ~

[5-5]

b' = 515 L:x~ = ~ L:cos8, I I where Eq. [5-3] has been used for x;. Since b'is 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 + J(x, -o))(x, -o)-PA11 (-o) =o -t I

[5-6]

The values forjand ocan 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. 1).

5.1.3 Primary Stress Comparison The distributed primary stud forces are divided by the stud stress area of27.489 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 20 15 tensioning optimization stress report. The approach used to evaluate these conditions is to: ( 1) 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 sti II meet ASME Code requirements.

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-- 0

- Page 11 of 41 5.2.2 Reactor Vessel Closure Flange Model The simulation was perfonned using the finite element analysis model described in Appendix A of Reference [1]. The modeling methods are summarized in this section; greater detail on the specifics of the model is described in Reference [1 ].

5.2.2.1 Model Geometry The vessel shell, head and flange regions were modeled using SOLID45 (3D structural solid) elements with each row of elements corresponding to one stud pitch. Studs were modeled using BEAM4 (3D 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 [1 ]. 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 100 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 ofthe 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 (3D spar) elements connecting the head and vessel flanges. The location of these interface elements was selected to act at a "reaction radius" empirically detennined 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 ofthe stud by coupling the rotational degree of freedom between the node at top of the stud beam element and the center node ofthe "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 UNK8 elements representing flange contact located at each end of the model are given half the area of the 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 Bl represents the case of one stud untensioned and with all other studs pre loaded to the specified initial stress

Case B2 same as Case B I 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 [I). 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 of 0.0 I 0 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: (1) 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 ofthese 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: ( l) 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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-- 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 1,350 psia, or a factor of 1.08 greater than the nonnal condition design pressure, but the stress allowables for emergency conditions are 1.2 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 perfonned 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 of the 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 R791 0 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 [n addition to QA controls associated with the procurement and use ofthe 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 20 I 0 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 I. DEI Report R-3937-00-1, Rev. 0, "Reactor Vessel Tensioning Optimization Stress Report-Hatch Nuclear Plant Unit 2," January 20 I 5.

2. "Analytical Report for Hatch No.2 Reactor Vessel for Georgia Power Company," Combustion Engineering Report No. CENC-1232, April1975.

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-3944-00-01, 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 B of 10 CFR 50, and ASMEIANSI 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 Confinnatory analyses for a given project may include comparison of model-computed stresses to theoretical closed-fonn solutions and other checks on model results.

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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 16 of 41

7. ASME Boiler and Pressure Vessel Code, Section Ill - 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 Unit2 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~ 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

- Resulting Stud Stress ksi 37.15

- Tensioiler CoeffiCient, Kt psilil 5.232 Bolting 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 i1 122.625

- Z dim to lD Transition in - 18.000

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

- SheiiiR in 110.720

- SheU 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 din to Recess (inner) in 0.375

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

- SheU IR in 109.500

- SheU thickness in 3.188

- Z dim to Head Coord. Sys. i1 -7.250 12100 Sunrise Valley Drive, Suite 220

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Hatch Unit 2 Oeeration with One Stud Out of Service Evaluation Calculation No.: C-3944-00-01 Revision No.: 0 Page 18 of 41 Table 2. Calculation of Primary Stresses in Reactor Vessel Studs, One Stud Out of Service Duisn Pressure, P, psig 1,235 Bob Cn:le R:ldJJS Ro ll7313n lrn:r o-~ Radi.s, Ri Ill 000 A'"'"l= ~n:e, F~ 869 2 k..s Sruds Our ofScr.ice I NeuiTal a:m ol!;e~ d 2 133 n S!Ui Slress Area, A 27 489 Coeflicien1 f -274 6 psVIl NLmb<rofSIUds 56 SIUd thetl cos(thetl) cos 2 (theta) Fo SlreSS (deg) (k'Pl (l.so)

I *180 1.1111ensoo11Cd 1111ensioncd 1111ensooncd untensooned 2 *174 -0 9937 0 99 901 8 32 80 3 -167 -0 9749 095 901 2 32 78 4 *161 *0 9439 0 89 900 2 32 15 5 -154 -09010 0 81 898 8 32 70 6 -148 -0 8467 072 897 0 32 63 7 -141 .o 7818 0 61 894 9 3256 8 *135 *0 7071 0 so 892 s 3247 9 - 129 -0 6235 039 889 8 32 37 ID -122 *0 5320 028 886 9 32 26 11 *116 -04339 019 883 7 32 I 5 12 *109 .o 3303 0 II 880 4 32 OJ 13 -103 *0 2225 0 05 876 9 31 90 14 *96

0. 1120 001 873 4 3177 IS -90 0,0000 000 869 7 3164 16 *84 0. 1120 001 866 I 31 5 I 17 -77 0,2225 0 OS 862 6 31 38 18

71 0 3303 0 II 859 I 31 25 19 -64 0 4339 0 19 8SS8 31 13 20 -58 0 S320 028 &52 6 31 02 21

51 0 6235 0 39 849 7 30 91 22 -45 0.7071 0 so 847 0 30 81 23 -39 0.7818 061 8446 3072 24 -32 0 8467 072 842 5 3065 25 *26 0,9010 0 81 840 7 30 58 26 *19 0 9439 0 89 839 3 30 S3 27 -13 09749 0 95 838 3 30 so 28 -6 0 9937 0 99 8377 3048 29 0 1.0000 I 00 837 5 30 47 30 6 0.9937 0 99 837.7 3048 31 13 0.9749 0 95 838 3 30 so 32 19 0 9439 089 839 3 30 53 33 26 0 9010 0 81 840 7 30 58 34 32 0.8467 072 842 s 30 65 35 39 0.7818 061 8446 3072 36 45 0 7071 0 50 847 0 30 81 37 51 0 6235 039 849 7 3091 38 58 0 5320 0 28 852 6 31 02 39 64 0 4339 0 19 8558 31 13 40 71 0.3303 011 859 I 3125 41 n 0 2225 0 05 862 6 31 38 42 84 0.1120 001 866 I 3131 43 90 0.0000 000 869 7 3164 44 96 -0 1120 001 8734 31 77 45 103 .o 2225 0 OS 876 9 31 90 46 109 -0 3303 011 880 4 32 03 47 116 -0 4339 0 19 883 7 32 IS 48 122 *0 5320 0 28 886 9 32 26 49 129 -0 6235 0 39 889 8 32 37 so 135 -0 7071 0 so 892 s 32 47 Sl 141 -0 7818 061 894 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 ss 167 -0.9749 0.95 901 2 32 78 56 174 -0.9937 0.99 9018 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 (ksij (2) Stud Stresses (ksij Flange Stud Load Gen. Membrane Local Memb.+Bend. MaximumS! Max Memb f- Separation Load Condition Condition Case Head Vessel Head Vessel Head Vessel Membrane Bending (10"*3 in)

Preload Only Nonnal AI O.Q7 0.28 23.82 18.11 24.60 18.48 37. 10 81.56 14.7 Preload Only I Untensioned 81 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 29.1 Prcload+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 82 & 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 Maximum 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 = 3.0Sm = 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 Reference [2) as listed in Input 10.

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

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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 20 of 41 y

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

Reston, VA 20191

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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 21 of 41 2B,OOO'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]

12100 Sunrise Valley Drive, Suite 220

Reston, VA 20191

PH 703.657.7300

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Tdte: Hatch Unit 2 Operation with One Slud Out of Service Evaluation Calculation No.: C-J944.00.01 Revision No.: 0 Page 22 of 41

-.,.m~-- 4

--:ift-~--3

--,.1++++:---- 2 1 -/-+++++-,~-

11 15 1/ '5 Figure 3. FEA Model Node Numbering and Section Cut Line Locations [1) 12100 Sunrise Valley Drive, Suite 220

Reston, VA 20191

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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- 23 Page -==-- of - - '41 A FINITE ELEMENT ANALYSIS INPUT LISTINGS A.1 FUe: _HATCH2.runs

/BATCH,LIST

/COM,

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

/COM, Hatch Unit 2 Stud Out of Service Evaluation

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

/COM,

/INP,JMACROS,HATCH2

/INP,JMACROS,DEI

/COM,

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

/COM, PRE*RUN SETUP

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

/COM,

/FILNAM, Tens-1

/SHOW,plots,grph

/TYPE, 1,4

/PREP7

/TITLE, Hatch2 Reactor Vessel Tensioning

/COM, Define run parameters NT ~ 56 I 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 ! ~lax number of Tens-* routines xs

37146 ! Final stud stress target for old tensioner XP

7100 ! Corresponding tensioner pressure Pmax

8500 I 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 Rl..MAX

NT+l ! Number of data items in RLIST (from ENOPOST macro)

DIM,TENSAR,ARRAY,TENSMX,3

/COM,

OIM,MPBTMPI,ARRAY,S

OIM,MPBTMPC,ARRAY,S

DIM,MPBTMPO,ARRAY,5

OIM,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)z1

/COM To set tensioning routine I (Tens-I) to OFF, toggle TENSAR(I,1)*D

/COM, TENSAR(I,2) is number of cyclic symmetry slices (z1 for full model) for Tens-!

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

/COM, TENSAR(l, 1) *1 STENSAR(l,2)*1 STENSAR(1,3)*1 RUNMORF

1 ! RUNMORF*1 to run out of service stud cases

/COM,

OIM,PLIST,ARRAY,NPMAX,4

OIM,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.

/PREP7 121 00 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.: - - 24 of _.....;..:........,_

Page --=-'---- 41

USE,GEOM,O ! Create geometry

/TITLE, Hatch2 Reactor Vessel Tensioning

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

/COLOR,NUM,BLAC,1

/TRIAO,OFF

/OIST ,1,1. S*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,NOOE,,1,1000

/VIEW EPLO

00,1,1,11

/COLOR,NUM,WHIT,I

ENDOO

/NUM

/PNUM,ELEM,1 ESEL,S,ELEM,,502,506 ESEL,A,ELEM,,l502,1506

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

/VIEW,1,1,1,1

/AUTO EPLO

/VIEW,l,-1,1,5

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

/USER

/OIST ,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 I 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 I Number of sets in this sequence TT

1 ! Number of sets to achieve one-pass tens .

USE,ZEROIT

OO,I,l,NT PLIST(I ,1)

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

ENODO 12100 Sunrise Valley Drive, Suite 220

Reston, VA 20191

PH 703.657.7300

FX 703.657.7301

Dominion fnvineerinv, Inc.

Title:

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

25 of 41

DO,I,NT+l,NT*2 PLIST (I, 1) a 10 I Load PLIST column 1 with stud numbers PLIST(I,2)

XP 1 Load PLIST column 2 with ref. tens. press.

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

ENDDO

IF,TENSAR(1,l),GT,0.5,THEN

USE,GOSOLV,'HatchZ','Tens-1',1 ! Solve model X1

X1*XS/RLIST(10,3) I Xl is ref. stress/av. stud stress - single stud X2

Xl*XS/RLIST(1,3) ! X2 is ref. stress/av. stud stress - all studs Kt

XS*Xl/XP ! Relate tensioner pressure to stud stress

ENDIF

/COM,

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

/COM, TENSIONING ROUTINE 10: RUN MISSING OR FAILED 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 I 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 TT

1 I 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 PLIST(I, 2) a XP ! Load PLIST column 2 with ref. tens. press.

ENDOO

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

DO,I,1,NT

00, J ,l,RLMAX RSAVE10(I,J,l)

RLIST(I,J)

EN DOD

ENDOO

USE,ZEROIT 1*1

USE,PSOLV,'Hatch2','A2',2.0,1235 ! Solve model - Case A2 SAVE, ,A2

OO,I,l,NT

DO,J,l,RLMAX RSAVE10(I,J,2)

RLIST{I,J)

END DO

ENOOO

USE, ZEROIT lzl

/COM , BEGIN SOLUTION PHASE

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

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

/POST!

SET,,,,,3~D

USE, POSTER

USE,ENDPOST FINISH SAVE, ,C1

OO,I,l,NT

OO,J,l,RLMAX RSAVElO(I,J,S)

RLIST(I,J)

ENDOO

ENOOO

USE,ZEROIT 12100 Sunrise Valley Drive, Suite 220

Reston, VA 20191

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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 26 of 41 lzl

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

OO,I,l,NT

OO,J,l,RLMAX RSAVE10(l,J,6)

RLIST(I,J)

ENDDO

ENDDO

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

0

OO,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+1 FINISH

ENOIF

ENODO

IF,LCHG,EQ,l.O,THEN

USE,ZEROIT 1*1

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

00,1,1,NT

DO,J,1,RLMAX RSAVE10(I,J,6)

RLIST(I,J)

ENDDD

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 a 1 ! Number of passes to achieve one-pass tens.

USE,ZEROIT

00,!,1,PP PLIST (I ,1)

I+1 ! Load PLIST column 1 with stud numbers PLIST(I, 2)

XP ! Load PLIST column 2 with ref. tens. press.

ENDDO

USE,GOSOLV,'Hatch2','Tens-108',1 ! Solve model - Case 81 SAVE,, 81

DO,I,1,NT

OO,J,1,RLMAX RSAVE10(I,J,3)

RLlST(I,l)

ENDDO

ENDDO

USE,ZEROIT 1*1

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

DO,I,1,NT

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

RLIST(I,J)

ENDDO

ENDOO

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

0

00,1,1,NT

IF,RL!ST(I,10),GT,O,THEN LCHG a 1.0

/PREP7 EKILL,I*1000-499 ! EKILL 501 El. in row CPDELE,I CPDELE,100+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.: 0 Page ---=27.:.__ of 41 FINISH

ENDIF

ENDDD

IF,LCHG,EQ,l.O,THEN

USE,ZEROIT I*l

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

DD,I,l,NT

DO,J,l,RLMAX RSAVE1D{I,J,4)

RLIST(I,J)

ENDDO

ENOOD

ENDIF

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

oo,I,l,NT

IF,RLIST{I,lO),GT,O,THEN LCHG

1.0

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

ENDIF

ENDDO

IF,LCHG,EQ,l.O,THEN

USE, ZERO IT 1*1

USE,PSOLV,'Hatch2' ,'82',4.0,1235 ! Re-Solve model- Case B2 SAVE, ,828

OO,I,l,NT

OO,J,l,RLMAX RSAVE10(I,J,4) c RLIST(I,J)

EN DOD

ENDDO

ENOIF FINISH

/COM, Clear the pressure boundary conditions

/PREP7 SFDELE,ALL,ALL FINISH

USE, ZEROIT

ENOIF

/COM,

/TITLE, Hatch2 Reactor Vessel Tensioning FINISH SAVE

/COM,

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

/COM, PRINT RESULTS

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

/Cr:14,

/COM, Print contents of PSAVE and RSAVE arrays

/OUT,RESULTS,OUT

/NDPR

IF,RUNMORF,EQ,l,THEN

USE,PRINTENS,'PSAVE10','RSAVE10',6,'Stud DOS',O

ENDIF

/OUT

/GOPR FINISH

/COM,

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

/COM, RUN COMPLETE

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

/COM,

/FILN, Ten s-O PARSAV,ALL

/COM, Do some file cleanup

/SYS, del CMMAKER

/SYS, del ENDPDST

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

Reston, VA 20191

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FX 703.657.7301

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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 28 of 41

/SYS, del GEOMCLUP

/SYS, del GODETEN

/SYS, del GOSOLV

/SYS, del OPTLOOP

/SYS, del POSTER

/SYS, del POSTER2

/SYS, del POSTER3

/SYS, del PRINTOLR

/SYS, del PRINTENS

/SYS, de 1 PSOLV

/SYS, de 1 READS I

/SYS, del ZEROIT

/SYS, de 1 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-10.e777

/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.: 0 Page --=2=-9_ of 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

63.568 I Stud mom. of I (inA4)

Ls

31.937 ! Stud effective length (in)

Estud

29.9E6 I Tune Estud or Ls to get right effective L

/COM,

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

NOs 2 6.750 ! Stud Hole diameter (in)

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

Ehole a 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

113.75 ! Seating Surface outer radius (in)

RR 2 113.25 I >>> TUNE REACTION RADIUS <<<

VFOR

122.625 I 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 . 50 ! Z dim to vessel outside trans. (130's row)

/COM,

/COM, Vesse 1 She 11 Dimensions VSIR = 110.72 ! Vessel shell inside radius VSTH - 5.875 ! Vessel shell thickness ZVTR --21.090 ! Z dimension to bottom of vessel transition

/COM,

/COM, Head Flange Dimensions HFIR

109.25 ! Head flange inner radius HFOR

122.625 ! Head flange outer radius HFFR - 2.750 I Head flange top fillet radius ZTHF

24.375 I Z dimension to top of head flange ZHFRI

0.375 ! 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 I ZTCS - 0.000 ! Z dimension to Transition Coordinate System I IRTR - 0.000 I Inner radius of transition area I ZUIC - 0.000 I Vertical rise of 00 Transition

/COM,

/COM, Head Shell Dimensions HSIR - 109.50 ! Head shell inner radius HSTH

3.188 ! Head shell thickness ZHCS = -7.250 I 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.: - - 0- Page _.:..;;._

30 of -~-

41 Ot

Os*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 (in~2)

/COM,

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

/COM, MATERIAL PROPERTIES

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

/COM, Set types, mats, and reals

/COM, Element types ET, 1, SOLI045 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,l,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,l,O ! Real 1: Dummy real for solid elements R,2,Ar I Real 2: Reaction links R, 3 ,Ar/2 ! Real 3: Cutting plane reaction links R,4,At,It,It,Dt,Ot,O ! Real 4: Tie bars R,S,At/2,It/2,It/Z,Dt,Dt,O ! Real 5: Cutting plane tie bars R,l1,As,Is,Is,Os,Os,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 I Cartesian on lower mating surface LOCAL,21,1,0,0,0,0,*90,0 I Cylindrical on lower mating surface (z up)

! LOCAL,22,1,RTCS,ZTCS ! Cylindrical system 1 for head curvature LOCAL,23 , 1,0,ZHCS I 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,S,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,l62, (VFIR+IDRR)/2 ,0 I "Core barrel groove inner surface" N,163,IORR,O ! Inner a-ring radius N,164,RR,O ! Reaction radius N,165,SSOR,O ! Outer limit of seating surface H,l66,SCR-NDs/Z,O ! Bolt hole inner edge N,167,SCR,O ! Bolt circle N,168,SCR+NDs/2,0 I Bolt hole outer edge N,169,VFOR,O ! Flange outer surface flwdth

HFOR-HFIR ! Flange width - head flwdtv - VFOR-VFIR I Flange width - vessel iormo

RR-IORR I Inner a-ring moment arm

/COM,

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

Reston, VA 20191

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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 31 of 41 NGEN,2,-10,161,169,l,O,(ZTHF-Ls)/2 I 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,l,O,ZVOT ! Make 110's row for O.D. feature FILL,l51,156,,,,2,-10 ! Even out 150's and 140's row FILL,lll,ll7 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 lOO's row for transition FILL,ll1,141,2,121,10,9,1

/COM,

/COM, FILL IN REST OF NODES IN VESSEL FLANGE FILL,l, 5 FILL,81,85 FILL,l,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,20l,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 NMOOIF, 231, HSIR

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

/COM,

/COM, DEFINE NODES IN FREE HEAD CSYS, 23 N,36l,HSIR,90 ! TOP OF HEAD (INNER SURFACE)

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

N,271,HSIR,AHT I 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, MAKE SOLID ELEMENTS TYPE,1 MAT,l REAL, 1 EN,1,1,2,12,11,1001,1002,1012,1011 ENGEN,l,4,1,1,1,1 I 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,l0,2,10,91,96,1 ! make 101 - 106 ENGEN,10,2,10,101 ! MAKE 111 ENGEN,1,8,1,111,111,1 I 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?ineerinv, 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,20l,20l,202,212,211,1201,1202,1212,121l ! MAKE 201 ENGEN,1,4,1,201,20l,1 ! SWEEP RIGHT TO MAKE 202 TO 204 ENGEN,10,2,10,201,20l,l I SWEEP UP TO MAKE 211 ENGEN,1,8,1,211,211,1 I 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,,l47,500,10 ! SELECT OUTER SIDE OF BOLT HOLE EMDOIF,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,S02,147,267,361 ! STUD

/COM,

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

/C0!4, MAKE LINE ELEMENTS FOR TIE BARS REAL,4 MAT,l EN,503,146,147,207 EN,504,147,148,207 EN,505,266,267,207 EN,S06,267,268,207 ! 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,l000,501,512,1 ! COPY REST OF WAY THROUGH

/COM,

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

/COM, ASSIGN INDIVIDUAL REAL PROPERTIES TO EACH STUD

/COM, STUD REAL IS STUD NO. + 10

oo,r,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 I 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 1 COUPLE IN X AXIS CPSGEN,NT,1000,1,1,1 I SWEEP UX SET AROUND CIRCLE CP,101,UV,164,204 ! COUPLE IN V AXIS CPSGEN,NT,1000,101,101,1 ! SWEEP UY SET AROUND CIRCLE

/COM, APPLY DISPLACEMENT BOUNDARY CONDITIONS NSEL,S,LOC,Z,BOTZ 1 SELECT BOTTOM OF MODEL D,ALL,UY 1 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 O,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+(I-1)*1000,FZ,-(Fspr+Fcsl)/2 F,l32+(I-1)*1000,FZ,-(Fspr+Fcsl)/2 F,201+(I-1)*1000,FZ,+Fspr/2 F,202+(I-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,ARGl,LT,O.S,THEN ! USE MIRROR SYMMETRY B.C.s

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

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

/COM, CHANGE REALS ON CUTIING 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,S ESEL,ALL NSEL,S,NODE,,1,1000 NSEL,A,NODE,,1+(NT-1)*1000,NT*l000 NSEL,U,NODE,,204,99204,1000 D,ALL,UY NSEL,ALL

IF,Fspr+Fcsl,GT,l.O,THEN F,131,FZ,-(Fspr+Fcsl)/4 F,l32,FZ,-(Fspr+Fcsl)/4 F,201,FZ,+Fspr/4 F,202,FZ,+Fspr/4 F,l31+(NT-1)*1000,FZ,-(Fspr+Fcsl)/4 F,132+(NT-1)*1000,FZ,-(Fspr+Fcsl)/4 F,20l+(NT-1)*1000,FZ,+Fspr/4 F,202+(NT-1)*1000,FZ,+Fspr/4

ENDIF

ELSE I USE CYCLIC SYMMETRY B.C.s

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

/COM, SWING LAST PLANE AROUND TO 0 DEGREES NSEL,S,NODE, ,NT*l000+l,(NT+1)*1000 CSYS, 21 NMODIF,ALL, ,0 NSEL,A,NODE,,l,lOOO NSEL,U,NODE,,164,204,40 NROTATE,ALL CPINTF,ALL,0.001 NSEL,S,NODE,,NT*1000+1,(NT+1)*1000 NMOOIF,ALL,,NT*360/NV NSEL,ALL NROTATE,ALL

/COM, BRING BACK LAST PLANE OF ELS.

ENGEN,(NT-1)*1000,2,(NT-1)*1000,1,3SO,l ! COPY AROUND CIRCLE

/COM, FIX UP COUPLES ON EDGE PLANES CP,l,,NT*l000+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 41 of _..:...,:.._

CP,l501,UZ,l64,NT*l000+164 CP,1502,UZ,204,NT*l000+204

ENDIF

ENDIF

/COM, Defin~ a few components for later use

USE,CMMAKER,201,5DO,'NHEAO' ,'EHEAO'

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

USE,CMMAKER,221,500,'NHEAOR' ,'EHEAOR'

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

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

/COM, inner a- ring NSEL,A,NODE,,l61,99999,1000 NSEL,A,NODE,,l62,99999,1000 NSEL,A,NOOE,,l63,99999,1000 NSEL,A,NOOE,,201,99999,1000 NSEL,A,NOOE,,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, O'MAKER NSEL,NONE ESEL,NONE

oo,I,O,(NT-l)*lOOO,lODO NSEL,A,NODE,,ARGl+I,ARG2+I

IF,I,EQ,(NT-l)*lOOO,THEN

!F,NT,LT,NV,EXIT

ENDIF ESEL,A,ELEM,,ARGl+!,ARG2+I

END DO CM,ARG3,NODE CM,ARG4,ELEM NSEL,ALL ESEL,ALL

END

/COM,

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

/COM, END CMMAKER MACRO

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

/COM,

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

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

/COM, CREATE GEOMCLUP MACRO

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

/COM,

CREATE,GEOMCLUP CPDELE,ALL,All CMDELE, NHEAD CMDELE,EHEAD CMOELE,NVESSEL CMDELE,EVESSEL CMOELE,NHEADR CMOELE, 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.: 0 Page ----=-35=--- of 41 EDELE,ALL NDELE,ALL

END

/COM,

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

/COM, END CMMAKER MACRO

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

/COM,

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

/COM, CREATE ENDPOST MACRO

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

/COM, RLIST columns as follows:

/COM, RLIST(J ,1)

Fl angl!' Di spl. 1ast pass

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

/COM, RLIST(J,3) = Stud Final M!!mbrane Stress

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

/COM, RL!ST(J,S) =Maximum Membrane Stress during any pass

/COM, RLIST(J,6)

Pass Number at which Max. Membrane Stress Occurs

/COM,

/COM, RL!ST(J,7) -Angular Rotation of Upper Flange (radians)

/COM, RLIST(J,B)

Angular Rotation of Lower Flange (radians)

/COM, RLIST(J,9)

Inner 0-ring separation

/COM,

/COM, RLIST(J,lO)

Force on Contact Link Element

/COM, RLIST(J,l1) =Global X Shear Force on Coupled Set

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

/COM,

/COM, RLIST(J,13)

Mu Required to Prevent Flange Mating Surf. Slide

/COM, RLIST(J,l4)

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 SI at Inner Surface

/COM, RLIST(J,l6)

Linearized 51 at Center of Surface (Membrane 51)

/COM, RLIST(J,l7)

Linearized SI at Outer Surface

/COM, RLIST(J,l8)

Total 51 at Inner Surface

/COM, RLIST(J,l9)

Total 51 at Outer Surface

/COM,

/COM, Line 2 - Vessel Local Cut Plane - Lower (RLIST(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 (RLI ST (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, 50) to RLIST (J, 54))

/COM,

CREATE,ENDPOST

/COM, Finish by loading results in RLIST

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

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

GET,DUMBOT,ELEM,ENUMB,ETAB.MAXM+BI ! El. membrane+bend stress (1)

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

RLIST(J,4)

DUMBOT > DUMTOP

/COM, RSY5,21 NNUM1 D (J-1)*1000+131 ! Node 131 NNUM2 * (J-1)*1000+139 ! Node 139 NNUM3 D (J-1)*1000+211 I 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. SOl

CET, RLIST(J ,10), ELEt-1, ENUMB, ETAB, FORCE ! El. Force CMSEL, 5, EHEAD NSEL,S,NODE,,(J-1)*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.:

- - Page --=:.36=-- of 41 FSUM ESEL,ALL NSEL,ALL

GET,RLIST(J,ll),FSUM,,ITEM,FX ! Global X-Shear Force

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

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

IF,RLIST(J,lO),LT,-1.0,THEN RLIST(J,l3) = -SQRT(RLIST(J,11)**2+RLIST(J,12)**2)/RLIST(J,10)

ELSE RLIST(J,l3) D -1 ! Trap divide by zero

ENDIF SLIPCNST = 2*ls/(Os*SWRC*As) I Constants in washer slip calc

IF,RLIST(J,3),GT,l.O,THEN RLIST(J,l4)

SLIPCNST*(RLIST(J,4)-RLIST(J,3))/RLIST(J,3)

ELSE RLIST(J,l4) * -1 ! Trap divide by zero

ENDIF

/COM,

/COM, Cut Lines:

USE,READSI,l1,15,21,15,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 I Cut 4: Nodes 81 to 85 in CSYS 21

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

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

USE,READSI,281,284,24,45,J I Cut 7: Nodes 281 to 284 n CSYS 24

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

ENDDO

END

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

/COM, END ENDPOST MACRO

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

/C~~. **********************************************************************************

/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, PRINT ENS

DO,K,1,ARG3 I

VWRITE,K

('*----',/,'Tensioning Sequence Itera*ion ',F2.0)

VWRITE, ARG4

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

VWRITE (2/, 'S*ud Stress Summary',/)

vSCFUN,MAXCOL1,MAX, ~RG2%(1, 3,K)

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

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

VSCFUN,MAXCOL2,MAX, ~RG2%(1, 4,K)

VSCFUN,MINCOL2,MIN, ~RG2%(1, 4,K)

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

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

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

VSCFUN,AVECOL3,MEAN,%ARG2X(l, S,K)

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

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

VSCFUN,AVECOL4,MEAN,%ARG2%(1,l4,K)

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

/COM, STRESS STRESS STRESS WASHER MU 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 37 of 41

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

VWRITE, 'MINIMUM' ,MINCOLl,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%(1,5l,K)

VWRITE,AVECOLl

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

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

VSCFUN,MAXCOL2,MAX,XARG2%(1,4l,K)

VSCFUN,MAXCOL3,MAX,XARG2%(1,46,K)

MAXCOL4 a 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,XARG2%(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,MAXCOLl,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,XARG2%(1,39,K)

VSCFUN,MINCOL2,MAX,XARG2%(1,44,K)

VSCFUN,MINCOL3,MAX,%ARC2%(1,49,K)

MINCOL4 a MINCOLl > MINCOL2 > MINCOL3

VWRITE,MAXCOL4 > MINCOL4

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

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

VSCFUN,AVEC0Ll,MEAN,%ARG2%(1,16,K)

VWRITE, AVECOLl

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

I

VSCFUN,MAXC0Ll,MAX,%ARG2%(1,2l,K)

VSCFUN,MAXCOL2,MAX,XARG2%(1,26,K)

VSCFUN,MAXCOL3,MAX,%ARG2%(1,3l,K)

MAXCOL4

MAXCOLl > MAXCOL2 > MAXCOL3

VWRITE,MAXCOL4

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

VSCFUN,MAXCOLl,MAX,%ARC2%(1,20,K)

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

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

MAXCOL4

MAXCOLl > MAXCOL2 > MAXCOL3

VSCFUN,MINC0Ll,MAX,%ARG2%(1,22,K)

VSCFUN,MINCOL2,MAX,XARG2%(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)

I

VSCFUN,MAXCOLl,MAX,XARG2%(1,23,K)

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

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

MAXCOL4 - MAXCOLl > MAXCOL2 > MAXCOL3

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

VSCFUN,MINCOL2,MAX,%ARG2%(1,29,K) 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 ---=-38=-- of _..:....;__

41

VSCFUN,MINCOL3,MAX,~RG2%(1,34,K)

MINCOL4

MINCOLl > MINCOL2 > MINCOL3

VWRITE,MAXCOL4 > MINCOL4

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

VSCFUN,MAXCOLl,MAX,~RG2%(1,9,K)

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

I

VSCFUN,MAXCOLl,MAX,~RG2%(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.~RG1X(l,l,K),~RG1X(l,2,K),~RG1%(1,4,K)

(4(F9.0,3X))

ENDIF

VWRITE, ARG4

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

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

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

VWRITE,SEQU,%ARG2%(1,3,K),~RG2%(1,4,K),%ARG2%(l,S,K),%ARG2%(1,6,K),%ARG2%(l,l4,K)

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

VWRITE, ARG4

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

/COM, GLOBAL GLOBAL REQUIRED

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

VWRITE,SEQU,%ARG2X(l,lO,K),%ARG2%(l,ll,K),~RG2%(1,12,K),%ARG2%(1,13,K)

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

VWRITE, ARG4

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

/COM, UPPER FLANGE LOWER FLANGE D-RING

/COM,STUO # ROTATION ROTATION SEPARATION

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

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

CLNO

0

DO,Ll,lS,SO,S CLNO

CLND+l L2

Ll+l L3

Ll+2 L4

Ll+3 LS

Ll+4

VWRITE,ARG4,CLND

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

/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),~RG2%(l,L3,K),~RG2%(l,L4,K),%ARG2%(l,LS,K)

(FS.D,2X,S(F9.0,3X))

ENDOO

ENOOO

END

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

/COM, END PRINTENS MACRO

/COMt **************~*******************************************************************

/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.

121 00 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 39 of 41

/COM, ARG4

Ending Case No.

/COM, ARGS a Starting Vessel Cut Plane No.

/COM, ARG6 z Ending Vessel Cut Plane No.

/COM, ARC7 = Starting Head Cut Plane No.

/COM, ARCB z Ending Head Cut Plane No.

/COM,

CREATE,PRINTOLR

/COM,

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

5

ELSE INDADD

D

ENDIF

DO,K,ARG3,ARG4

VSCFUN,MAXCOLl,MAX,%ARGl%(1,3,K) STABLEC2(INDADD+K,2)

MAXCDLl/lDOO

VSCFUN,MINCOL1,MIN,%ARG1%(1,3,K) STABLEC2(INOAOO+K,l)

MINCOL1/1DOO

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

VSCFUN,MAXCOL2,MAX,%ARG1%(1,4,K) STABLECZ(INDADD+K,3)

MAXCOLZ/1000

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

VSCFUN,AVECOL2,MEAN,XARG1%(1,4,K)

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

VSCFUN,MINCOL3,MIN,%ARG1%(l,S,K)

VSCFUN,AVECOL3,MEAN,%ARG1%(l,S,K)

VSCFUN,~AXCOL4,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.D,/)

I

VWRITE,ARG2

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

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

/COM,STUO I STRESS STRESS STRESS @ SET NO. WASHER MU

VWRITE,SEQU,%ARG1%(1,3,K),XARG1%(1,4,K),%ARG1%(1,5,K),%ARG1%(1,6,K),%ARG1%(1,14,K)

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

VWRITE,ARCZ

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

/COM, GLOBAL GLOBAL REQUIRED

/COM,STUO I LINK FORCE X SHEAR Z SHEAR FLANGE MU

VWRITE,SEQU,%ARG1%(1,10,K),XARG1%(1,11,K),%ARG1%(1,12,K),%ARG1%(1,13,K)

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

VWRITE, ARGZ

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

/COM, UPPER FLANGE LOWER FLANGE D-RING

/COM,STUD I 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

00,Ll,l5,50,5 CLNO

CLNO+l L2

Ll+l L3 a Ll+2 L4

Ll+3 LS

Ll+4

VWRITE,ARG2,CLNO

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

/COM, INNER CENTER OUTER INNER OUTER

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

VWRITE,SEQU,%ARG1%(1,Ll,K),%ARG1%(1,L2,K),%ARG1%(l,L3,K),%ARG1%(l,L4,K),%ARG1%(1,L5,K)

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

ENDDO

OO,L,ARG7,ARG8

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

TABLEC2(INDADO+K,4)

TMPMAXSI > TABLEC2(INDADD+K,4)

VSCFUN,TMPMAXSI,MAX,%ARG1%{l,L*5+14,K)

TABLEC2(INOADO+K,4)

TMPMAXSI > TABLEC2(INDADD+K,4)

ENODO

OO,L,ARG5,ARG6

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

TABLEC2(INDADD+K,5)

TMPMAXSI > TABLEC2(INDADD+K,5)

VSCFUN,TMPMAXSI,MAX,%ARC1%(1,L*5+14,K) 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 40 of --=-=--

41 TABLEC2(INDADD+K,5)

TMPMAXSI > TABLEC2(INDADD+K,5)

ENDDO TABLEC2(INOAOD+K,4) = TABLEC2(INDAOO+K,4)/1000 TABLEC2(INDAOD+K,5) ~ TA8LEC2(INDADD+K,5)/1000

ENDOO

END

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

/COM, END PRINTOLR MACRO

/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 41 of 41 B SOFTWARE USAGE RECORDS The following table lists the Software Usage Records for the ANSYS analyses perfonned 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.

Input file which sets the finite element model geometry and boundary

- MACROS.HA TCH2 conditions specific to the Hatch Unit 2 RPV model.

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

RESULTS.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.

12100 Sunrise Valley Drive, Suite 220

Reston, VA 20191

PH 703.657.7300

FX 703.657.7301

Patel, Dharmeshkumar B.

From: Willyard, C. Dale Sent: Tuesday, February 21, 2017 6:22AM To: Patel, Dharmeshkumar B.

Subject:

FW: Verbal Authorization for Relief Request HNP-ISI-RR-05-01 From: McElroy, G. Ken Sent: Saturday, February 18, 2017 4:01 PM To: Vanier, Randall C., III (Chuck); Willyard, C. Dale; Collins, Carl James Cc: Pierce, Chuck R.; Johnson, Greg L.; Hulett, Brian K.; Black, Sandy Moinipour; Torrance, William Michael; Do, Hien Q.;

Wells, Tim G.; Wheat, Justin Thomas

Subject:

FW: Verbal Authorization for Relief Request HNP-ISI-RR-05-01 FYI. I From: Orenak, Michael [ mailto:Michaei.Orenak@nrc.govJ Sent: Friday, February 17, 2017 1:05 PM To: Joyce, Ryan M.; McElroy, G. Ken Cc: Pierce, Chuck R.; Markley, Michael; Rudland, David; Dijamco, David

Subject:

Verbal Authorization for Relief Request HNP-ISI-RR-05-01 Ryan and Ken, Below is the script for the verbal authorization of relief request HNP-ISI-RR-05-01 that was provided at approximately 1:10pm EDT on 2/17/2017 by David Rudland and Michael Markley. As I stated during the call ,

a written relief request authorization will be issued within 150 days from today if the relief is needed .

Please let us know the results of the attempt to remove the stud by COB 1/20.

Mike VERBAL AUTHORIZATION BY THE OFFICE NUCLEAR REGULATION FOR RELIEF REQUEST HNP-ISI-RR-05-01 TEMPORARY RELIEF FROM REQUIREMENTS OF IWB-3515 OF SECTION XI OF THE ASME CODE EDWIN I. HATCH NUCLEAR PLANT. UNIT 2 SOUTHERN NUCLEAR OPERATING COMPANY. INC.

DOCKET NO. 50-366 FEBRUARY 17. 2017 Technical Evaluation read by David Rudland, Chief of the Vessels and Internals Integrity Branch, NRR By letter dated February 17, 2017, Southern Nuclear Operating Company, Inc. (the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, IWB-3515.2(c), at Edwin I. Hatch Nuclear Plant, Unit 2, which specifies surface examination requirements for the reactor pressure vessel (RPV) studs. Specifically, the relief is pursuant to 1

Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(5)(iii) on the basis that complying with the required surface examination of IWB-3515.2(c) is impractical.

On February 10, 2017, the licensee notified the U.S. Nuclear Regulatory Commission (NRC) that during the volumetric examination of the 56 RPV studs of the Hatch, Unit 2 RPV closure flange, it had detected an indication in stud location number 33. IWB-3515.2(c) of Section XI of the ASME Code requires surface examination of the stud if an indication is found through volumetric examination . The licensee has indicated that they may not be able to remove the stud during the current refueling outage (2R24), and therefore it is impractical to meet the requirements of IWB-3515.2(c) of Section XI of the ASME Code. For contingency planning, the licensee requested relief from the surface examination requirements in case the planned removal of the stud at location number 33 is not successful.

The licensee requested relief from the required surface examination to allow the stud to be untensioned during full power operations. As a basis, the licensee developed structural evaluations to determine the impact of the untensioned stud to the remaining 55 RPV studs and the ASME code stress and fatigue limits. The NRC staff reviewed the structural evaluations. The increased primary membrane stress on the remaining studs is below the design stress allowable value for the stud material. Additionally, the evaluations demonstrate that leaving one untensioned stud in service does not cause exceedance of the ASME Code stress and fatigue limits in the remaining studs and RPV closure flange. Finally, the j valuations show that the increase in flange interface separation is less than the allowable separation.

The NRC staff finds that the licensee provided reasonable assurance of structural integrity of the remaining RPV 55 studs and RPV closure flange at Hatch, Unit 2 if stud at location number 33 is left untensioned in service until the beginning of the next refueling outage (2R25) . Therefore, the NRC staff concludes that complying with the required surface examination is impractical and grants relief from IWB-3515.2(c) of Section XI of the ASME Code for RPV stud location number 33.

2

Authorization read by Michael Markley, Chief of the Plant Licensing Branch 11-1, NRR As Chief of the Plant Licensing Branch 11-1, Office of Nuclear Reactor Regulation, I agree with the conclusions of the Vessels and Internals Integrity Branch.

The NRC staff finds that the licensee has provided reasonable assurance of structural integrity of the remaining studs and the RPV closure flange if the stud at location number 33 is left untensioned in service. The NRC staff concludes that complying with IWB-3515.2(c) of Section XI of the ASME Code is impractical and that the licensee addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(5)(iii) . Therefore, as of February 17, 2017, the NRC grants Relief Request HNP-ISI-RR 01 for the Edwin I. Hatch Nuclear Plant, Unit 2, until the beginning of the next refueling outage (2R25) .

All other requirements in ASME Code,Section XI, for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.

This verbal authorization does not preclude the NRC staff from asking additional clarifying questions regarding Relief Request HNP-ISI-RR-05-01 while preparing the subsequent written safety evaluation.

3

Condition Report 10327745

RPV Stud 33 *Ultrasonic Indication Requires further Site: HATCH Evaluation During lSI Ultrasonic Examination of the Hatch 2 reactor pressure studs 1-56, an indication was found at location 33 as marked on the flange. The indication was located 41.7 inches from the top of RPV stud. It is recommended to remove this stud prior to flooding the cavity so additional surface and visual examination to determine the relevance of the ultrasonic indication.

Entry Date: 02/07/2017 01 :33 :50 PM Responsible Individual: LMMORRJS Mode Rettralnt:

Status: CLOSED Event Date: 02107/2017 01 :33 :00 PM Retponalble Manager: MAINTMGR Operation* Review N Required:

Reported By: KFWHITE Location: CRType: WWO Tech Spec Equip Related: N Name: White,Kevin Fredrick Design tag Number: Priority: 2 Technh:al Review Required: N Phone: 205-992-5798 Asset:

EMail: KFWHITE@SOUTHERNCO.COM Unit:

System:

SubSystem:

Equipment Status:

Deficiency Tag Number:

lmnH*!Iialt' \rliou l':tht*n Notified Engineering Programs ASSETNUM LOCATION DESCRIPTION PRIORITY TVPE Hl'i:tit*d I irht*h _ . ~ *

_ __:_ _ __ : ,

Ticket Description Reported Priority Reap EXP Completion Class Application Location Loc Deac Site Statui Relationehlp Individual 978872 H2R24 Startup Issue lntcrnalRcportedPriority DBPATEL IntcrnalTargctFinish TE INCIDENT HATCH INPROG FOLLOWUP Hdaird \\or 1,0, tit' " _ . ' ** ~- 0

o *~ _ *

WorkOrder Description Location Description Site Work Type Statui Relatlon*hlp SNC843700 REPLACE STUD RPV Stud 2B11AOOI REACTOR PRESSURE HATCH CM iNPRG FOLLOWUP 33 - Ultrasonic Indication VESSEL Requires further Evaluation

'Pt'rl.!ii!Hiil' .llinn l>l'l <lll"' for IIH:IIIoll . :

Sl Type Description Special Indicator Value Tech Review Required Instruction*

I.Hnll.Odt* . :

Event Description Remark Remarks Date I of 2 Condition Repon Rev 1.3 Monday. Februnry 13 , 2017

Condition Report 10327745- RPV Stud 33- Ultrnsonic Indication Requires further Site: HATCH Evaluation Record Summary Date Class Created By Type SNC843700 Released for work POC Joe Bcerger x3249 02/09/2017 KWHITSON OPERATIONS SNC843700 TO ROGER MCDONALD 02/08/2017 HDCROSBY WORKPKGLOC SNC843700 LLRT Pre-Review is COMPLETE and/or the hold 02/08/2017 MJKEATIN ENGINEERING has been RELEASED.

LLRT Pn:-Review is COMPLETE and/or the hold has been RELEASED.

A .pdf copy ofENG-1336 (LLRT/lLRT Component Review Form) can be found in the following location:

T:\EngPrograms\LLRl\2017 LLRT WO Reviews SNC843700 PIPHDC 02/0812017 HDCROSBY WORK Page 2 of 2 Condition Report Rev 1.3 Monday, February 13, 2017

{'

SOUTHERN A UT CalibrationC amination COMPANY Site/Unit: HNP 2 Procedure: NMP-ES.024*504 Outage No.:

2HR24 Procedure Rev.: 4.3 Summary No.: H2 2B11\2STUD 1 THRU 56

..................................................................- Report No.: S17H2U007 Workscope: lSI Work Order No.: Page: 1 of 2 Code: 2007 Edition with 2008 Addenda Cat./ltem: B-G-1/88.20 Location: ..........................................

REFUELING FLOOR Drawing No.: A-33

Description:

CLOSURE HEAD STUDS System ID: ........................................

811 ~ ................................... ~ .....~ ..................................................~ .............................................__. .............................._____________________

Component ID: 2B11\2STUD 1 THRU 56 See CeMme~ Size/Length : 6.0" /48.876" Thickness/Diameter: 6.0" /48.878" Limitations: NONE Start Time: 1620 Finish Time: 1828 Instrument Settings Search Unit Cal. Axial Orlentod Search Unit Serial No.: 01H1LH Serial No.: 8530 Checks Time

-Date Calibration Signal Sweep Depth Manufacturer: GEIT Manufacturer: Staveley Initial Cal. 1820 619/2017 Reflector Amplitude% Division Inter. Cal. N/A Model: USN&OSW Linearity: S17H2L006 Size: 0.5" Model: A10L Notch #1 81% 6.1 8.68 Inter. Cal. N/A Delay: 0.3228 Range: 17.0 Freq.: 10 MHz Center Freq.: N/A Inter. Cal. N/A M'tl CaiNe!: 0.2328 Pulser Type: Square Exam Angle: o* Squint Angle: NIA Final Cal. 1828 219/2017 Damping: 5000hms Reject: 0% Measured Angle: ..... N/A Mode: Long Couplant PRF: Auto High SU Freq. : 10 MHZ Exit Point NIA # of Elements: 1

....._ Cal. Batch: 158080 Circumferential Oriented Search Unit Frequency: 10MHz Rectify: Fullwave Contig.: Single Focus: NIA Type: Ultragelll Calibration Signal Sweep Voltage: 450 Pulse Width : 50 Shape: Round Contour: NIA Reflector Amplitude% Division Depth Mfg.: Sonotech Wedge Style: INTEGRAL N/A Exam Batch: 1158080 Ax. Gain (dB): 30 Circ. Gain (dB): N/A Search Unit Cable Type: Ultragelll 10 Screen Div. = ......

17 in. of Depth Type: RG-174 Length:

- 8' No. Conn.: 0 ..... Mfg.: Sonotech Calibration Block Scan Coverage Reference Block Reforence/Simuletor Block Cal. Block No. 156-H Upstream Downstream Scan dB: N/A Gain Signal Sweep Thickness 48.875 Dis.: 8.00 Scan dB: 37 Serial No. : N/A Depth cw~ ccw~ dB Reflector Amplitude% Division Cal. Blk. Temp. ......

89 _ Temp. Tool: 29880013 Exam Surface: OD I Top of Stud Type: N/A N/A Comp. Temp. ......

78 _ Temp. Tool: 29880013 Surface Condition: SMOOTH Recordable lndlcatlon(s): Yes No~ (If Yes, Ref. Attached Ultrasonic Indication Report.)

Comments: Zone 1 Results: NRI ~ Rl GEO PSIIB...llno exam for atud 38 B-8003 to replace atud

_ at location 33 Percent Of Coverage Obtained > 90%: YES Reviewed Previous Data: N/A Examiner Level 11 Signature Date Reviewer Date Michael, Dickey E. 2/9/2017 Lynda Bartlett 4.. Ja.J'1 Examiner Level Signature Date Site Review Date N/A Kevin White ..2*11* I 7 Other Level 111 Date ANti Review Signature Dote Fuller, Richard J. tiJ/oA 7 Steve Fitzwater

0 SOUTHERN COMPANY A 2 UT Calibrationj -""ami nation Procedure: NMP*ES-024*604 Site/Unit: HNP Outage No.: 2HR24 Summary No.: H2 2B11\2STUD 1 THRU 56 Procedure Rev.: 4.3 Report No. : S17H2U007 Wo~scope: lSI Wo~ Order No.: Page: 2 of 2 Code: 2007 Edition with 2008 Addenda Cat./ltem: B-G-1/B6.20 Location: REFUELING FLOOR Drawing No.: A*33

Description:

CLOSURE HEAD STUDS System ID~ B11 Component ID: ----------------~----------------~~---------------------------------------------------------------------------------------------------

2B11\2STUD 1 THRU 56 S:.~e C 0\111\ vYt ell\; Size/Length: 8.0" 148.875" Thickness/Diameter: 8.0" 148.875" Limitations: NONE Start Time: 1820 Finish Time: 1840 Instrument Settings Search Unit Cal. Time Date Axial Oriented Soarch Unit Serial No.: 01H1LH Serial No.: 8530 Checks Calibration Signal Sweep Depth Manufacturer: GEIT Manufacturer: Staveley Initial Cal. 1830 219/2017 Reflector Amplitude% Olvlalon Model: USN60sw Linearity: S17H2L008 Size: 0.5" Model: A10L Inter. Cal. N/A Notch ##3 80% 8.9 44.30 Delay: 0.3497 Range: 60.0 Inter. Cal. N/A Freq.: 10MHz Center Freq.: N/A Inter. Cal.

M'tiCaiNel: 0.2328 Puiser Type: Square Exam Angle: o* Squint Angle: N/A Final Cal.

N/A 1840 219/2017 Damping: 5000hms Reject: 0% Measured Angle: N/A Mode: Long -

PRF: Auto High SU Freq.: 10MHz Couplant Exit Point N/A # of Elements: 1 Frequency: 10MHz Rectify: Fullwave N;;:-- Cal. Batch: 168080 Clrcumforontlal Orlontod Search Unit Config.: Single Focus:

Voltage: 450 Pulse Width: 60 Type: Ultragelll Calibration Signal Sweep Shape: Round Contour: N/A Reflector Amplitude% Division Depth Mfg.: Sonotech Wedge Style: INTEGRAL N/A Ax. Gain (dB): 64 Circ. Gain (dB): N/A Exam Batch: 158080 Search Unit Cable

=

Depth Type: Ultragelll 10 60.0 in. of Screen Dlv. Type: RG-174 Length: 6' No. Conn.: 0

--- Mfg.: Sonotech Calibration Block Scan Coverage Cal. Block No. 156-H Reference/Simulator Block Upstream Downstream Scan dB: N/A Reference Block Gain Signal Sweep cw., ccw.,

Thickness 48.875 Dia.: 6.0 Scan dB: 70.0 Serial No.: N/A Depth dB Reflector Amplitude% Division Cal. Blk. Temp.

89 Temp. Tool: 29880013 Exam Surface: OD I Top of Stud Type: N/A N/A Comp. Temp.

78 Temp. Tool: 29880013 No .,

Surface Condition: SMOOTH Recordable lndlcation(s): Yes (If Yes, Ref. Attached Ultrasonic Indication Report.)

Results: NRI ., Rl GEO Comments: Zone 2 PSI/Baaellne exam for atud 38 B-8003 to replace atud Percent Of Coverage Obtained > 90%: YES Reviewed Previous Data: NIA at location 33 Examiner Level Signature Date Reviewer Date Michael, Dickey E. 219/2017 Lynda Bartlett ~ -10*17 Examiner Level Signature Date Site Review Doto N/A Kevin White "2 ... Jf-2tJI7 Other Level 111 Date ANII Review Dote Fuller, Richard J. tJ/ttJ Steve Fitzwater

r SOUTHERN A UT CalibrationC amination COMPANY Site/Unit: HNP 2 Procedure: NMP*ES-024*804 Outage No.:

2HR24 Summary No.:

Workscope:

H2 2B11\2STUD 1 THRU 56 lSI Procedure Rev. :

Work Order No.:

4.3 Report No.:

Page: -----

1 817H2U001 of 4 Code: 2007 Edition with 2008 Addenda Cat./ltem: B*G*1/B6.20 Location: REFUELING FLOOR Drawing No.: A-33

Description:

CLOSURE HEAD STUDS System ID: B11 Component ID: 2B11\2STUD 1 THRU 56 Size/Length: 8.0" /48.8711" Thickness/Diameter: 8.0" I 48.875

Limitations: NONE Start Time: 1130 Finish Time: 1240 Instrument Settings Search Unit Cal. Time Date Axial Oriented So*rch Unit Serial No.: 01H1LH Senai No.: 697340 Checks Calibration Signal Sweep Depth Manufacturer: GEIT Manufacturer: Panametrlcs Initial Cal. 1040 217/2017 Reflector Amplitude % Division Model: USN60sw Linearity: S17H2L006 Inter. Cal. N/A Size: .50" Model: A111S Notch #1 81% 8.1 8.611 Inter. Cal. N/A Delay: 0.3228 Range: 17.0 Freq.: 10.0 MHz Center Freq.: NIA Inter. Cal. N/A M'tl Cai/Vel: 0.2326 Pulsar Type: Square Exam Angle: o* Squint Angle: N/A Final Cal. 1250 217/2017

--# of Elements:

Damping: 6000hms Reject: 0% Measured Angle: N/A Mode: Long Couplant PRF: Auto High SU Freq.: 10.0 MHZ Exit Point N/A 1

- - Cal. Batch: 111B080 Clrcumferentl*l Oriented Search Unit Frequency: 10MHz Rectify: Fullwave Config. : Single Focus: N/A Type: Ultragelll Calibration Signal Sweep Voltage: 450 Pulse Width: 50 Shape: Round Contour: NIA Reflector Amplitude% Division Depth Mfg.: Sonotech Wedge Style: INTEGRAL N/A Exam Batch: 15B080 Ax. Gain (dB): 59 Clrc. Gain (dB): N/A Search Unit Cable Type: Ultragelll 10

--- Screen Div. =

--17 in. of Calibration Block Depth Type: RG-174 Length:

Scan Coverage 6' No. Conn.: 0

- Mfg.: Sonotech Upstream Downstream Scan dB: N/A Reference Block Reforencol81mulator Block Cal. Block No. 156*H Gain Signal Sweop Serial No.: Depth Thickness 48.875 Dia.: 6.00 cw"' CCW'I/ Scan dB: 70 N/A dB Reflector Amplitude% Division Cal. Blk. Temp. 101 Temp. Tool: 29880013 Type: N/A N/A Exam Surface: OD I Top of Stud Comp. Temp. 115 Temp. Tool: 29880013 Surface Condition: SMOOTH Recordable lndlcatlon(s): Yes r No ., (If Yes, Ref. Attached Ultrasonic Indication Report.)

Comments: Zona 1 Results: NRI 'II Rl GEO Percent Of Coverage Obtained > 90%: YES Reviewed Previous Data : YES Examiner Level n Signature Date Reviewer Date 11 Michael, Dickey E. 217/2017 Lynda Bartlett <<-fO ..

Examiner Level Signature Date Site Review Date N/A Kevin White 2- 11-2.()17 Other Level 111 Date ANII Review Signature Date Fuller, Richard J . ~ g 11 Steve Fitzwater

f" ~

SOUTHERN A UT Calibration,_.(amination COMPANY Site/Unit: HNP 2 Procedure: NMP*ES-024*504 Outage No.: 2HR24

4.3 Workscope

Summary No.: H2 2B11\2STUD 1 THRU 66 Procedure Rev.: Report No.: 817H2U001 lSI Work Order No.: Page: 2 of 4 Code: 2007 Edition with 2008 Addenda Cat. litem: B-G*1/B6.20 Location: REFUELING FLOOR Drawing No.: A*33

Description:

CLOSURE HEAD STUDS System ID: B11 Component 10: 2B11\2STUD 1 THRU 56 Size/length: 6.0"/48.876" Thickness/Diameter: 6.0" /48.876" Limitations: NONE Start Time: 1130 Finish Time: 1240 Instrument Settings Search Unit Cal. Time Date Axial Oriented Search Unit Serial No.: 01H1LF Serial No.: 8530 Checks Calibration Signal Sweep Manufacturer: GEIT Manufacturer: Staveley Initial Cal. 1045 217/2017 Depth Reflector Amplitude% Division Model: USN&Osw Linearity: S17H2L004 Size: 0.5" Model: A10L Inter. Cal. N/A Notch #3 80% 8.9 44.30 Delay: 0.3497 Range: 50.0 Freq.: Inter. Cal. N/A 10MHz Center Freq. : NIA Inter. Cal.

M'tiCaiNel: 0.2326 Pulsar Type: Square Exam Angle: o* Squint Angle: N/A N/A Final Cal. 1255 217/2017 Damping: 5000hms Reject: 0%

PRF: Auto High SU Freq .: 10 MHz Measured Angle:

Exit Point N/A

# of Elements:

N/A Mode: Long 1

Couplant Frequency: 10MHz Rectify: Fullwave ----Cal. Batch : 15B080 Circumferential Orlontod Soarch Unit Config.: Single Focus: N/A Voltage: 450 Pulse Width: 50 Type: Ultragelll Calibration Signal Sweep Shape: Round Contour: N/A Reflector Amplitude% Division Depth Mfg.: Sonotech Wedge Style: INTEGRAL N/A Ax. Gain (dB): 65.6 Circ. Gain (dB): N/A Exam Batch: 168080 Search Unit Cable Type: Ultragelll 10 Screen Div. = 50.0 Depth

--- in. of Calibration Block Type: RG-174 Length: 6' No. Conn.: 0

- Mfg. : Sonotech-Scan Coverage Cal. Block No. 156-H Upstream Downstream Scan dB: N/A Reference Block Reference/Simulator Block Gain Signal Sweep Thickness 48.875 Dia.: 6.0 cw, ccw, Scan dB: 71.6 Serial No. : N/A Depth

-- dB Reflector Amplitude% Division Comp. Temp.

Cal. Blk. Temp. 101 Temp. Tool:

~Temp. Tool:

29880013 29880013 Exam Surface:

Surface Condition:

OD I Top of Stud Type: N/A N/A SMOOTH Recordable Indication(&): Yes , No (If Yes, Ref. Attached Ultrasonic Indication Report.)

NRI Rl , GEO Rl @ Location #33 Comments: Zone 2 Percent Of Coverage Obtained > 90%: YES Reviewed Previous Data: YES Examiner Signature Date Reviewer Jennings, Jason J. 217/2017 Lynda Bartlett Examiner Level N/A Signature Date N/A Other Level 111 ANII Review Date Fuller, Richard J. Steve Fitzwater

IDDEAL.

SOUTHERN. \

Component Summary 211012017 COMPANY 10:21 AM Paga 1 of 1 Summary No.: H2 2B11\2STUD 1 THRU 56 Component ID: 2B11\2STUD 1 THRU 56 Component

Description:

CLOSURE HEAD STUDS ASME SECTION XI Calibration Blocks: Code Requirements:

Class: 1 156-H ~* Volumetric Exam Cat.: B-G-1 Surface Item: 86.20 VIsual Report No. Method Status Remarks Eval Report No. Eval Disposition Eval Remarks INF Report No. INF Disposition S17H2U001 UT ~ S e, ..-. C. o vV"\ V""' -e""" ':-c;, b'C..\c -J ~ R.,..) 2- [ ~ * ~0\L S17H2U007 UT NRI Percent of required area examined - Surface: N/A Relief Request No. or Relief Request Required: N/A Percent of required area examined - Volumetric: >90% Code Case Used (if applicable): N/A Remarks (Describe limitations, code coverage, etc.):

Zone 1 - NRI and Zone 2

Rl indication at location #33 in Zone 2 *see supplemental sheet S17H2U001 Sheet 3 for comments. UT dataeheet S17H2U007 11 for PSI for the replacement stud, ID: 53 B-8003.

Reviewer 1:

Title:

Date:

Reviewer2:

Title:

Date:

Review Complete:

Title:

Date:

SOUTHERN COMPANY A Supplemental Report Report No.: S17H2U001 Page: 3 of 4 Summary No.: H2 2B~TUD 1 THRU 56 Examiner: Jenni~ ~ _11_ Reviewer: ....;;_..------"~t!GA"-'JJI&~-.r-,__,Date: ~ .. 10~ J7 Date: 2 -It-t J Date: z/V3/17 Comments:

Hatch 2R24 RPV Closure Head Stud NDE Evaluation This NDE evaluation is applicable to the RPV Closure Head Stud located at position 33.

During inservice inspection (lSI) volumetric (ultrasonic) examination of all Reactor Vessel studs (1-56), utilizing procedure NMP-ES-024-5041 Version 4.3 and PDI-UT-Sl Revision F, an indication was found in the stud at location 33 as marked on the head. This indication was recordable and reportable.

The applicable Code is 2007 Edition, 2008 Addenda of ASME Section XI, paragraph IWB-3515, Acceptance Standards for Examination Ca~ory B-G-1, Item 86.20. I IWB-3515.2 is applicable for volumetric examination. IWB-3515.2(a) refers to Table IWB-3515-1 which is not applicable since there is not a qualified ultrasonic technique for ultrasonic flaw sizing for bolting examinations.

IWB-3515.2(b) is also not applicable.

IWB-3515.2(c) requires that flaws detected by volumetric examination be investigated by a surface examination. This paragraph is applicable.

The indication was located 41.78 inches from the top of the RPV stud. This places the indication very near the stud/RPV flange interface. The stud is 48.875 inches long. The threaded depth of the flange is 7.0 inches.

Removal of this stud has been requested to perfonn a supplemental surface examination per IWB-3515-1.

Kevin White SNC Level Ill

r SOUTHERN COMPANY A. Ultrasonic Indication Report - Bolting Site/Unit: HNP Summary No.: H2 2811\2STUD 1 THRU 56 2 Procedure:

Procedure Rev. :

NMP-ES-024-604 4.3 Outage No.:

Report No.:

2HR24 S17H2U001 Workscope: lSI Work Order No.: ------------------- Page:

4 of 4 Ind. o/oDAC Depth X Max. X1 X2 YMax. Y1 Y2 Studs and Bolts No. Max. (D) 1 35% 41.78 #lA ~A NA NA NA NA Y2

+

Nuts and Flange Ligaments Remarks:

Stud located at position #33 as marked on the head. Using the reactor vessel head as a designated datum "0" position, the Indication Is located at approximately 300".

The Indication has an approximate X dimension of 1.0" and an approximate Y dimension of 0.75".

Examiner Signature Date Reviewer /Date zs. 217/2017 Lynda Bartlett 11 Dt-/- '1 N/A Signature Date Site Review Date Kevin White 2 *11-2() 17 Other Level 111 Date ANII Review Date Fuller, Richard J. ,)/1(~ Steve Fitzwater 4/23/(7 Additional - UT Indication Data

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OLYMPus* Olympus NOT, Inc.

48WoerdAve

( Your Vision, Our future Waltham, MA 02453 USA Tel (800) 225-8330 www.olympus-ims.com info@olympusNDT .com DATE: 313112014 TO: Ronald Swain. PDI Project Manager. EPRI FROM: Mark Menesses. Sales Engineer- Transducers & Pulsar Receivers RE: Equivalency of transducers Dear Mr. Swain.

This letter confinns the compan"bility of the Staveley A1OL and Panamebics A1OL transducers. The A1OL transducer design fonnerly belonged to Staveley. This design has since been owned by Harrisonic and Panamebics before being acquired by Olympus NDT. A transducer labeled as A1OL with Staveley, Harrisonic, or Panamebics branding will all have an identical design and performance.

Please feel free to contact me if you have any additional questions or concerns.

Sincerely, Mark Menesses Sales Engineer: Transducers & Pulser/Receivers Olympus NDT I 48 Woerd Avenue I Waltham MA 02453 I USA Tel. (800) 998-8330 x552# 1 Fax (781) 419-3980

NL-17-0951, Inservice Inspection Program, Owner'S Activity Report for Outage 2R24

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