ML19331A916
| ML19331A916 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/27/2019 |
| From: | Mark D. Sartain Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 19-483 | |
| Download: ML19331A916 (83) | |
Text
{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 27, 2019 10 CFR 50.55a U.S. Nuclear Regulatory Commission Serial No.: 19-483 Attention: Document Control Desk NRA/GDM: RO Washington, DC 20555-0001 Docket No.: 50-281 License No.: DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 ASME SECTION XI INSERVICE INSPECTION PROGRAM PROPOSED ALTERNATIVE REQUEST S2-15-ISl-05 TO USE A MECHANICAL CLAMPING DEVICE FOR A ONE-INCH MAIN STEAM LINE PIPE REPAIR Pursuant to 10 CFR 50.55a(z)(2), Virginia Electric and Power Company (Dominion Energy Virginia) hereby requests NRC approval to use an alternative repair for an identified pinhole leak recently identified in a one-inch Main Steam pipe at Surry Power Station (Surry) Unit 2. Specifically, on November 22, 2019, a pinhole steam leak was identified in the one-inch bypass piping in the Turbine Driven Auxiliary Feedwater Pump steam supply line. A permanent American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code (ASME Code), Section XI, Code repair is not currently possible since Surry Unit 2 is operating at full power, and the leak is unisolable, subject to full steam generator (SG) pressure, and constitutes part of the containment boundary. 10 CFR 50.55a(g) requires that nuclear power facility components must meet the requirements contained in specific editions of ASME Section XI Code for lnservice Inspection, and Repair and Replacement Programs. The applicable requirements for Surry Unit 2 are the 2004 Edition with No Addendum of the ASME Section XI Code. Article IX-1000 of Appendix IX, "Mechanical Clamping Devices for Class 2 and 3 Piping Pressure Boundary," Paragraph (c), states in part "Clamping devices shall not be used on the following: (1) Class 1 piping; (2) portions of a piping system that forms the containment boundary." Since the pinhole leak is located in a portion of a piping system that forms the containment boundary, use of a mechanical clamping device is not permitted by the Code. Also, Paragraph (a) of Article IX-6000 contains monitoring requirements associated with use of a clamping device. Paragraph (a) states: "Except as permitted by (b) below, or where precluded by the clamping device configuration, the area immediately adjacent to the clamping device shall be examined using a volumetric method." NRC approval of an alternative repair to the ASME Code requirements noted above is requested to permit application of a mechanical clamping device to the pinhole leak location, as well as to use increased visual inspection of the repair location instead of
Serial No. 19-483 Docket No. 50-281 Alternative Request - Main Steam Line Pinhole Leak Repair Page 2 of 3 volumetric monitoring. Otherwise, performing a code repair in accordance with Appendix IX of ASME Section XI would require shutting down Unit 2, making the pipe repair, and then restarting Unit 2. This would result in a hardship without a compensating increase in quality and safety, since the shutdown and subsequent restart of Surry Unit 2 unnecessarily cycles plant systems and components, and the temporary use of a mechanical clamping device together with daily visual inspections will provide an acceptable leak-tight repair until a permanent repair can be made. Verbal authorization of the proposed alternative is requested to permit expeditious repair of the leak to preclude the potential worsening of the leak and to eliminate the personnel hazard associated with an unisolated steam leak. The proposed alternative request is provided in Enclosure 1. The alternative request has been approved by the Facility Safety Review Committee. Should you have any questions or require additional information, please contact Mr. Gary D. Miller at (804) 273-2771. Sincerely, Mark D. Sartain Vice President - Nuclear Engineering and Fleet Support Commitment made in this letter:
- 1. The temporary repair of the pinhole leak in the one-inch Main Steam piping will be permanently repaired in accordance with ASME Section XI during the Surry Unit 2 spring refueling outage.
Attachment:
Alternative Request for Use of a Mechanical Clamping Device on Main Steam Pressure Boundary Leak
Serial No. 19-483 Docket No. 50-281 Alternative Request - Main Steam Line Pinhole Leak Repair Page 3 of 3 cc: U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 Mr. Vaughn Thomas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 04 F12 11555 Rockville Pike Rockville, MD 20852-2738 Mr. G. Edward Miller NRC Senior Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 09 E3 11555 Rockville Pike Rockville, Maryland 20852-2738 NRC Senior Resident Inspector Surry Power Station
Serial No. 19-483 Docket No. 50-281 Attachment, Page 1 of 8 Attachment ALTERNATIVE REQUEST FOR USE OF A MECHANICAL CLAMPING DEVICE ON MAIN STEAM PRESSURE BOUNDARY PIPING LEAK ALTERNATIVE REQUEST S2-15-ISl-05 Virginia Electric and Power Company (Dominion Energy Virginia) Surry Power Station Unit 2
Serial No. 19-483 Docket No. 50-281 Attachment, Page 2 of 8 Alternative Request for the Use of a Mechanical Clamping Device on Main Steam Pressure Boundary Piping Leak Alternative Request S2-I5-ISl-05 SURRY POWER STATION UNIT 2 DOMINION ENERGY VIRGINIA
--In Accordance with 10 CFR 50.55a(z)(2), Hardship or Unusual Difficulty without a Compensating Increase in the Level of Quality and Safety--
- 1. ASME Code Component(s) Affected Code Class: ASME Class 2 Piping Component Number: 1-inch SHP-601 off 4-inch SH P-127-601
Description:
1-inch Main Steam Piping Upstream of Valve 2-MS-377
Reference:
Drawing 11548-CBM-064A-5, Sheet 3 of 6
2. Applicable Code Edition and Addenda
The following table identifies the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code Section XI Code of Record for performing inservice inspection (ISi) activities at Surry Power Station Unit 2 (Surry Unit 2). 10-Year ASME Section XI Interval Interval Plant ISi Interval Edition/ Addenda Start Date End Date 2004 Edition/ No Surry Unit 2 5th May 10, 2014 May 9, 2024 Addenda [Ref.11
Serial No. 19-483 Docket No. 50-281 Attachment, Page 3 of 8
- 3. Applicable Code Requirements The applicable ASME Code requirements are ASME Section XI, 2004 Edition with No Addenda, Article IX-1000 of Appendix IX, "Mechanical Clamping Devices for Class 2 and 3 Piping Pressure Boundary."
Paragraph (c) of Article IX-1000 states, in part, "Clamping devices shall not be used on the following: (1) Class 1 piping; (2) portions of a piping system that forms the containment boundary: ... " Paragraph (a) of Article IX-6000 states, in part, "Except as permitted by (b) below, or where precluded by the clamping device configuration, the area immediately adjacent to the clamping device shall be examined using a volumetric method .... " Dominion Energy Virginia has reviewed 10 CFR 50.55a and has not identified any conditions regarding Article IX-1000 of Mandatory Appendix IX.
4. Reason for Request
Background - At 10:41 on November 22, 2019, during a routine walkdown by plant Operations personnel, a measured six drops per minute leak was found dripping from the insulation just upstream of valve 2-MS-377 (part of the "C" Main Steam Header, Penetration No.# 074). (See Enclosure 1.) At 19:48 on November 22, 2019, after scaffolding was installed and pipe insulation was removed to facilitate investigation of the source of the leakage, Non-destructive Engineering and System Engineering personnel identified a potential through-wall leak on the 1-inch Main Steam (MS) piping upstream of valve 2-MS-377. A small through-wall leak (characterized as a pinhole) was confirmed using a mirror, as well as the sound of escaping steam. The location of the pinhole is on an elbow to pipe socket weld at approximately the 1:00 o'clock position. The pinhole was estimated to be 1/32-inch or less and was likely caused by a fabrication welding defect (i.e., lack of fusion). The defect was bounded to account for nondestructive limitations per Article IX-2000. Ultrasonic testing (UT) of the pipe was performed to obtain thickness readings on both sides of the 90-degree elbow next to the welds and extended to areas where a proposed mechanical clamp could be installed. (NOE Report BOP-UT-19-076.) The readings ranged from 0.170-inch to 0.186-inch. (The nominal pipe wall thickness is 0.179 inch.) No degradation of the piping was noted, and no pipe movement or vibration was observed. The 1-inch MS piping is ASME Class 2 and is located outside the reactor containment in the Main Steam Valve House on the 27-foot elevation at 12 feet off the floor. The 1-inch piping is the bypass line around valve 2-MS-158, the Steam Generator (SG) C Turbine Driven Auxiliary Feedwater Pump (TDAFWP) Steam Supply Isolation Valve. Valve 2-MS-377 is normally closed during power operations. The SG C steam supply
Serial No. 19-483 Docket No. 50-281 Attachment, Page 4 of 8 line is one of three steam supply lines to the TDAFWP. The other two steam supply lines are supplied from SG A and SG B. An extent of condition evaluation of the other two steam supply lines was completed through piping walkdowns, and no other similar steam leaks were identified. The piping is 1-inch, Schedule 80 (0.179-inch nominal wall thickness), seamless carbon steel pipe, A 106 Grade B piping. The ISi Classification Boundary Drawing is provided in Enclosure 1. The design and operating conditions for the 1-inch line are as follows:
- Design conditions: 1085 psig and 570 ° F - Operating conditions (full power): 811 psig and 520 ° F The steam supply lines to the TDAFWP are within the containment isolation boundary outside of containment. The MS system is considered a closed system (i.e., an extension of the primary containment) as described in the Surry Power Station Units 1 and 2 Updated Final Safety Analysis Report (UFSAR) (Ref. 3).
The UFSAR Chapter 14 accident analyses environmental consequences were reviewed to assess the potential radiological impact of the pinhole leak. It was determined that the steam releases and associated dose consequences for the Main Steam Line Break (MSLB) and the Steam Generator Tube Rupture (SGTR) (including releases from the TDAFWP exhaust) are of such a magnitude that the additional release from the pinhole steam leak on the 1-inch line for the duration of the event is negligible. Reason for the Request - ASME Section XI requires that a permanent Code repair of the pinhole leak in the 1-inch MS piping be performed. While Dominion Energy Virginia intends to perform a permanent Code leak repair during the Surry Unit 2 spring 2020 refueling outage, it is not currently possible to perform the repair since Surry Unit 2 is in POWER OPERATION mode, and the MS piping leak is unisolable and subject to full SG pressure. Although a mechanical clamping device would provide an acceptable repair to control leakage and ensure continued structural integrity of the 1-inch pipe, Paragraph (c) of Article IX-1000 of Appendix IX of ASME Section XI prohibits the use of such devices on portions of a piping system that forms the containment boundary. Under these conditions, it would be necessary for Surry Unit 2 to shutdown from POWER OPERATION to COLD SHUTDOWN to perform a permanent ASME Code repair. When the plant is shutdown from POWER OPERATION to COLD SHUTDOWN and then returned to POWER OPERATION, plant inspections and Technical Specifications surveillances need to be performed, which result in radiological dose to personnel. In addition, a shutdown and subsequent restart of Surry Unit 2 unnecessarily cycles plant systems and components and may result in plant transients in addition to the shutdown and restart of the Surry Unit 2 reactor.
Serial No. 19-483 Docket No. 50-281 Attachment, Page 5 of 8 Dominion Energy Virginia has determined that shutting down Surry Unit 2 to perform a permanent ASME Code repair results in a hardship without a compensating increase in the level of quality and safety. Therefore, an alternative to Paragraph (c) of Article IX-1000 of Appendix IX and Paragraph (a) of Article IX-6000 of Appendix IX is proposed in Section 5 to permit the temporary repair of the 1-inch MS line leak until a permanent Code repair can be performed during the next Surry Unit 2 refueling outage.
- 5. Proposed Alternative and Basis for Use Pursuant to 10 CFR 50.55a(z)(2), an alternative to the ASME Section XI Code repair requirements is proposed for the repair of the 1-inch MS line piping. Specifically, Dominion Energy Virginia proposes to take an exception to the containment boundary restriction of Paragraph (c) of Article IX-1000 of Appendix IX of ASME Section XI and from the volumetric method monitoring requirements of Paragraph (a) of Article IX-6000, so that the 1-inch MS piping leak can be repaired using a mechanical clamping device that meets the remaining provisions of Article IX-1000 of Appendix IX of ASME Section XI. All other provisions of ASME Code, Section XI, Paragraph IWA-4133 and Appendix IX will be met.
As required by Paragraph (a) of Article IX-1000 of Appendix IX of ASME Section XI, the proposed clamping device will not remain in service beyond the next scheduled Surry Unit 2 refueling outage currently scheduled for spring 2020, at which time the defect will be repaired, or the piping replaced. Dominion Energy Virginia proposes to use a mechanical clamping device to:
- 1) control the leak and maintain the MS containment boundary, and 2) ensure the structural integrity of the MS piping.
Leakage Control and Maintenance of the Containment Boundary Paragraph (c) of Article IX-6000 of Appendix IX of ASME Section XI states: "The clamping device shall be monitored for leakage at least weekly. Any leakage at any time shall be dispositioned." The Surry Unit 2 clamping device will be visually monitored for leakage once per day (24 hours). This significantly exceeds the requirements of Paragraph (c) of Article IX-6000 and provides equivalent assurance that any leakage will be promptly identified without the performance of volumetric method inspections. In addition, Paragraph (a) of Article IX-6000 allows an exception to performing examinations of the area immediately adjacent to the clamping device using a volumetric method, when it is precluded by the clamping device configuration. As discussed earlier, the pipe in question is part of the closed system outside containment and is considered an extension of the containment boundary. The mechanical clamping device will be located on a small 1-inch pipe outside
Serial No. 19-483 Docket No. 50-281 Attachment, Page 6 of 8 containment, and the closed system will continue to provide a passive containment isolation barrier. The normal operating pressure at the location of the mechanical clamping device is in the range of 800 - 1000 psig. The clamping device is in an area that is readily accessible for visual inspection. As such, positive verification of the leak-tight integrity of the mechanical clamping device will be accomplished by visual observations. As noted above, the clamping device will be visually monitored for leakage once per day (24 hours). This significantly exceeds the requirements of Paragraph (c) of Article IX-6000 of Appendix IX, which states "The clamping device shall be monitored for leakage at least weekly. Any leakage at any time shall be dispositioned." Mandatory Appendix IX, Article IX-1000, Paragraph (d), requires that a
- Repair/Replacement Plan be developed in accordance with IWA-4150 and shall identify the defect characterization method, design requirements, and monitoring requirements. Dominion Energy Virginia is developing a Repair/Replacement Plan in accordance with IWA-4150 for the steam leak on the 1-inch MS pipe. A system leakage test (at normal operating temperature and pressure) in accordance with IWA-5000 will be performed on the portion of the piping system containing the mechanical clamping device. The leakage acceptance criterion for the installed clamping device, post maintenance testing, is ze'ro leakage. Should leakage be identified during any of the daily inspections, a plant Condition Report will be written, and a leak evaluation will be performed.
Structural Integrity of the MS piping The proposed mechanical clamping device will be designed to comply with the design requirements of Article IX-3000 of Appendix IX and the material requirements of Article IX-4000 of Appendix IX. These requirements meet or exceed the design rating of the piping. The clamping device enclosure material is carbon steel (SA 516 GR 70); therefore, the clamping device is suitable for the intended application and capable of performing its specified design functions. A sketch of the proposed clamping device is provided in Enclosure 2, as well as the design information for the clamping device. Calculation CEM-0231, Rev. 0 [Ref. 4 and Enclosure 3], was prepared to provide the loading environment and stress levels for design basis conditions in the original design configuration of the piping and with the structural clamp installed together with a new temporary pipe support. The clamp weighs approximately 60 lbs. and is designed to provide more than adequate structural capacity to accommodate the postulated reaction forces in the event the 1-inch Carbon Steel, Schedule 80 socket welded elbow connection completely separated. In addition, the clamp provides more than adequate structural capacity to function as the structural element of the piping and will withstand all design basis loading conditions. The calculation demonstrates that with the clamp and additional vertical support installed, the piping system and pipe supports remain within the limits of the design code, with margins consistent with those of the original configuration, without the structural clamp installed.
Serial No. 19-483 Docket No. 50-281 Attachment, Page 7 of 8 The impact of the additional weight of the sealant and any supporting boxes, frames, or structures added during the repair process on the seismic adequacy of the piping system was evaluated in calculation CEM-0231 [Ref.4], and it was determined that an additional support needs to be installed. Impact of system changes, with respect to the degraded component condition relative to the ability of the system to withstand a seismic event, has also been evaluated. Calculation CEM-0232 [Ref.5 and Enclosure 4] demonstrates the ability of the piping in the current configuration to withstand the design loading conditions, including seismic, given the identified degraded weld. Paragraph (a) of Article IX-6000 contains monitoring requirements associated with use of a clamping device. Paragraph (a) states: "Except as permitted by (b) below, or where precluded by the clamping device configuration, the area immediately adjacent to the clamping device shall be examined using a volumetric method. The examination frequency shall not exceed three months and shall be specified in the Repair/Replacement Plan. When the examination reveals defect growth to a size that exceeds the projected size determined by IX-3100(b), the defect shall be removed or reduced to an acceptable size." Dominion Energy Virginia proposes to ensure the structural integrity of the 1-inch pipe containing the defect, as an alternative to the volumetric method monitoring requirements of paragraph (a) of Article IX-6000, by ensuring the clamping device being installed on the pipe will entirely encapsulate the piping section containing the flaw (see clamping device drawing in Enclosure 2). This configuration will prevent access to perform a volumetric method inspection of the piping immediately adjacent to the clamping device. However, as noted above, the clamping device will be visually monitored for leakage once per day (24 hours), which significantly exceeds the requirements of Paragraph (c) of Article IX-6000 of Appendix IX, which states "The clamping device shall be monitored for leakage at least weekly." Therefore, the use of the proposed alternative will continue to provide an acceptable level of quality and safety.
- 6. Duration of Proposed Alternative The proposed relief will apply until the next Surry Unit 2 refueling outage currently scheduled for spring 2020 (Refueling Outage 2R29).
- 7. Precedents
- 1. Waterford Steam Electric Station, Unit 3 (TAC No. MC8542) dated February 9, 2006 (ADAMS Accession No. ML060460590).
- 2. Turkey Point Nuclear Power Plant, Unit 4 (TAC No. MC7338) dated August 15, 2005 (ADAMS Accession No. ML052090182).
Serial No. 19-483 Docket No. 50-281 Attachment, Page 8 of 8
- 8. References
- 1. ASME Pressure Vessel and Boiler Code, Section XI Rules for lnservice Inspection of Nuclear Power Plant Components, 2004 Edition, No Addenda.
- 2. Mechanical Clamping Device Design Information, Eng. Order# 4211975, Rev 2, TEAM Industrial Services, 11/25/19.
- 3. Surry Unit 2 - Updated Final Safety Analysis Report (UFSAR), Revision 51.01.
- 4. Calculation CEM-0231, Revision 0, "Evaluation of Line 1"-SHP-601 off 4"-SHP-127-601 for Leak Seal Enclosure Device," dated 11/26/19.
- 5. Calculation CEM-0232, Revision 0, "Evaluation of Degraded Socket Weld on 1" Diameter Steam Supply Bypass Line Through-Wall Leak Flaw Characterization as Reported in Condition Report CR1136592," dated 11/26/19.
Serial No. 19-483 Docket No. 50-281 Enclosure 1 ISi CLASSIFICATION BOUNDARY DRAWING Virginia Electric and Power Company (Dominion Energy Virginia) Surry Power Station Unit 2
Serial No. 19-483 ISi Classification Boundary Drawing Docket No. 50-281 Enclosure 1, page 1 of 1 w w w w 0: 0: 0: 0: w w w w I I I I a.. a.. a.. a.. U) U) U) U) 0 0 0 0 0 0
.... ....0 0 6"-SAE-103-121 N
5' X 6'
> RED.
U) U) 2-MS-FE 0 ONE CAP TO BE SHIPPED LOOSE FOR FIELD WELO!NG PRIOR TO CHEMICAL CLEANING. 2-RC E-lC STEAM GENERATOR
<ISi CLASS 2A SECONDARY SIDE> 0 2-PEN PN-74
WALL OF REACTOR CONTAINMENT-----
2-MS-PT 2-MS-PT
!SI CLASS 2 NON CLASSED Approximate I 2-MS TD-8 Location of leak VCS-60A .--
Steam supply to TDAFW pump Enclosure 1 cropped from Drawing No: 11548-CBM-064A-5
Serial No. 19-483 Docket No. 50-281 Enclosure 2 MECHANICAL CLAMPING DEVICE DESIGN INFORMATION Virginia Electric and Power Company (Dominion Energy Virginia) Surry Power Station Unit 2
TEAM Industrial Services Registration# F-003143 Engineering Department. Tel: (281) 388-5695 Fax: (281) 388-5690 ROUTING SLIP & COVER SHEET FOR NUCLEAR SAFETY RELATED JOBS Branch Work Order#: 140400181701 Status: Priority Caller: J. JONES Safety Review#: 4211975DS Engr Order#: 4211975 REV 1 Customer: DOMINION SURRY I Name: Signature: Date: Time: Data Taken By: 11/23/2019 1245
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QC Received By: Specifications: Design Pressure: 1085 psi Design Temperature: 570 °F Service: STEAM Torque Value: 5/8" STUDS 125 ft-lb 7/8" STUDS 351 ft-lb Total Weight: 56.60 lb Sealant Type: FSC-N-3B Routing: ESTIMATE Void: 24.60 in3 BC Maximum Injection Pressure: 1835 psi 26.07 in3 AC Estimated Quantity of Do Not Paint: 29 STICKS Sealant: Seal Type: CRUNCH TEETH Revision Note: ADDED STRONGBACKSFOR SEPARATION Equipment Number: 2-MS-377 QC FINAL INSPECTION REQUIRED Nuclear - Safety Related MTRs and COCs Required PMI Required Nuclear - Safety Related
.,tL:-U t-1 fo E1wyth'ft1_r: He Do Rev. 3/3/2010
TEAM Sheet 1 of 1 egistration # F-003143 MATERIAL SPECIFICATIONS D Non-Critical/Nuclear Critical/Nuclear Drawn By: KC/UMW Date: 11/24/19 Engineering Order No.: 4211975 REV 1 Checked By: UMW/GVD/KC Date: 11/24/19 Enclosures Material Specification MTR coc NR PIPE FITTING ROLLED PLATE BLOCK / PLATE / SIDEBARS SA 516 GR 70 X X ENDPLATES STRONGBACK BARS SA 516 GR 70 X X S.B. EARS/FINGERS Fasteners STUDS ENCLOSURE SA 193 GR 87 X X STUDS STRONGBACK SA 193 GR 87 X X NUTS ENCLOSURE SA 194 GR 2H X X NUTS STRONGBACK SA 194 GR 2H X X SET SCREWS Misc. uirements
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TEAM FORM 901.DS124 Engineering Procedure Supplement Rev: 3 Corporate Page 1 of 1 90° Ell SCREWED/SOCKET FITTING GIVEN BY: DATE: I 11/23/19 PLANT: I Surry I UNIT: 12 CHKD. BY: DATE: I 11/23/19 SURFACE CONDITION: I Good LINE SIZE: 1" SEVERITY OF LEAK: 1ON 10 I SHIP TO: I 5570 Hog Island Rd. Surry, Va. TYPE SEAL: [3J CRUNCH PACKING SKIN TEMP. [3J VOID FILL TONGUE TUBING LINE: 570 FLG. PERIMETER SEAL [3J OTHER: !PEENING LIPS I DIMENSIONAL Al (MTAO) DATA LTR. DIM. --Bl (BPTC) A1 17" L- 1 81 1"
- WI C1 1.315 01 1.315 Fl E1 1.300 I
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I F1 1.865 Dl / G1 .560 J--// W1 .350 E2 A2 17"
,/ - ,_L W2 (MTAO) = MEASURE TO 82 1" ANY OBSTRUCTION (BPTC) = BEST PLACE C2 1.315 Kl TO CLOSE ON 02 1.315 E2 .900 i F2 1.865
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G2 .400 W2 .350 L/ H1 1" FOR DIMS Hl,H2 & JU2 & Kl,K2 PLACE SQUARE AGAINST END Of H2 1" WELD/THREADS AS SHOWN J1 2" J2 1" OBSTRUCTIONS K1 3" (Looking into C 1 /D 1) K2 1" L .130 3/8" UNC INJECTION PORTS REQUIRED NOTE: IF SQUARE CANNOT BE REPLACED AS SHOWN - "HI" & "H2" STILL MUST BE TAKEN AT ASSUME SCH. 40/80 WELDS/THREADS FOR CALCULATION LOCATION OF BLOW: -12 THREADED WELDED SEISMIC; KEEP WEIGHT DOWN TO A MINIMUM
Clamp Clamp Detai Is: (2) Halves as shown Nuclear Safety Related Weight 56.6 lbs Void Volume 24.6 in3 Overall Dimensions 5 1/211 x 5 1/2"
Summary of Calculations Rectangular Plate Stress Calculations Cover Plate Maxu = 14453.93 psi < Sall.ow=: 19580 psi Design Margin = 1 .35 Longer Side Wall (Worst Case) .Alax0 =5215.& psi < Sallow = 19580 psi Design Margin 3.75 = Shorter Side Wall (Worst Case) Maxu = 12327.38- psi < Sallow 19 580 psi Design Margin = 1.59 Bolting Calculations - 5/8" Stud SL= 15579.15 /hf < SH:28250 lbf Design Margin = 1.81 Bolting Calculations - 7/8" Stud SL =9890.65 !bf < SH= 11542.5 !bf Design Margin = 1 . 17 Buckling of Pipe Due to External Pressure Circumferential Membrane stress (I2-:-"6,74* 10 3 psi < Spqie- =(1.71 d0 4 ) psi Design Margin= 2.54 Meridional Bending Stress uu.0.156 psi <. Design Margin = 109685.65 Circumferential Bending Stress o-Zb-=0.047 psi < Design Margin 365618.84 Thrust Calculation Due to Separation Thrust Produced 2492.169 /bf Number of studs required ND=0.703 < NS=2 Design Margin = 2.845
Bending Calculation: Ear Force per Ear Fs=1246.O84 /bf Thickness Required: Bending in Ears tr=0.522 in < W=0.625 in Design Margin = 1.197 Thrust and Bending Calculation: Crunch Ring Force per Ear Fs=1246.O84- !bf Thickness Required : Bending in Ears tr=0.513 in< W=2.125 in Design Margin = 4.144 Thickness Required: Bending in Diameter tr-0.667 in< W=2.125"in Design Margin= 3.186
Serial No. 19-483 Docket No. 50-281 Enclosure 3 CALCULATION CEM-0231, REVISION 0, "EVALUATION OF LINE 1"-SHP-601 OFF 4"-SHP-127-601 FOR LEAK SEAL ENCLOSURE DEVICE," (EXCERPT) DATED 11/26/19 Virginia Electric and Power Company (Dominion Energy Virginia) Surry Power Station Unit 2
fJi; Dominion Complete Calculation Energy CM-AA-CLC-301 ATTACHMENT 7 Page 1 of 11 Complete the fields with text or an X as required. Calculation Number: Revision: Addendum: Sub type: Decommissioning Record? CEM-0231 0 N/A 000 D Yes 0 No Vendor (If not Dominion): N/A Contains Proprietary Information: D Yes 0 No Proprietary Information Owner: QA Program Owner: 0 Dominion Energy D Other: Calculation Quality Class: 0 Safety Related 0NSQ D Non-Safety Related Subject (Calculation Title): Evaluation of Line 1" -SHP--601 off 4"-SHP-127-601 for Leak Seal Enclosure Device, Surry Unit 2 Addendum
Title:
I N/A Station(s) and Unit(s): NAO 1 02 0 ISFSI SU O 1 2 ISFSI MP O1 02 03 0ISFSI Affected System(s), Structure(s), or Component(s): AFW Pump Steam Supply Bypass 1"-SHP- - 601 4"-SHP-127-601 2-MS-377 Purpose (Executive Summary): The purpose of the calculation is to document the acceptability of the seal enclosure device installed on the AFW Pump Steam Supply 1"-SHP--601 bypass line off of line 4"-SHP-127-601. Originator (Qual. Required): Printed Name (1 l l3 l Sig Date: ( l ( 3 l 1 JFJ& _., 11 Reviewer (Qual. Required): Printed Name (1 J Type of Review: (2 J Signature: Date: Independent I 1-Z - J9 Approver: Printed Name Signature: Date: Note: Physical or electronic signatures are acceptable. {J
- I II --;& -/! r Note: (1) Add lines for additional originators or reviewers as necessary. (2) Note if reviews are "Independent," "Peer", "Subject Matter Expert", "Supervisor, or "Owner's". (3) Enter N/A for Owner's Review of Vendor Calculation 731234 (Feb 2019)
fW,: Dominion Complete Calculation
,;,# Energy*
CM-AA-CLC-301 ATTAC HMENT 7 Page 2 of 11 Calculation # CEM-0231 Rev. 0 Instructions: To update the Table of Contents page numbers, click within the Table of Contents to select the table, then select "Print Preview," (Click the Office Button at the upper left of the computer screen; then select "Print," and then "Print Preview") close "Print Preview." The page numbers should update. Table of Contents
- 1. Record of Revisions and Addenda.............................................................................................................................. 2
- 2. Cumulative Effects Review......................................................................................................................................... 2
- 3. References ................................................................................................................................................................. 3
- 4. Computer Codes Used ............................................................................................................................................... 3
- 5. Identification of Computer Inputs and Outputs ......................................................................................................... 4
- 6. Background................................................................................................................................................................ 6
- 7. Design Inputs ............................................................................................................................................................. 7
- 8. Assumptions/ Comments.......................................................................................................................................... 7
- 9. Methodology ............................................................................................................................................................. 8
- 10. Calculations ............................................................................................................................................................... 8
- 11. Acceptance Criteria..........................................................................................................................................._......... 8
- 12. Results ....................................................................................................................................................................... 9
- 13. Conclusions.............................................................................................................................................................. 11
- 14. Precautions and Limitations .................................................................................................................................... 11
- 15. Calculation Review Checklist ................................................................................................................................... 11
- 16. Attachments ............................................................................................................................................................ 11 Revision O Original issue of this calculation dated November 2019.
Issued to document acceptability of the seal enclosure device on the AFW Pump Steam Supply 1" SHP- -601 bypass off of line 4"-SHP-127-601. This is to be a temporary condition until the flaw at the weld can be repaired at the next refueling outage.
- 2. Cumulative Effects Review N/A 731234 (Feb 2019)
Complete Calculation Dominion j# Energy" CM-AA-CLC-301 ATTACHMENT 7 Page 3 of 11 Calculation# CEM-0231 Rev. 0
- 3. References 3.1 Code, ASA B31.1 "Standard Code for Power Piping", 1955 Edition including addenda thru Code Case N7 dated September 1962.
3.2 Code, ANSI I USAS B31.1.0 -1967, "Power Piping" 3.3 Code, ANSI B31.7 -1969 with addenda through 1970, "Nuclear Power Piping" 3.4 Calculation CE-0581 Rev. 0 Add. 00A, Pipe Stress Analysis of Problem 2746 of the Steam High Pressure System (DCP 84-80 Replacement of Control Valves). 3.5 Drawing 11548-MKS-131C1 Rev. 3, HP Steam to Aux. Feedwater Pump, 2-FW-T-2, Surry Power Station, Unit 2 3.6 Drawing 11548-CBM-064-5 Sheet 3, Rev. 2, ISi Classification Boundary Drawing lnterval-5, Main Steam System, Surry Power Station Unit 2 3.7 Computer Code: "NUPIPE-II Version 3.0, Pipe Stress Analysis Software 3.8 Standard, DNES-SU-ME-0004, Rev. 0, Piping Class Design Standard 3.9 Calculation CEM-0232 Rev. 0, Evaluation of Degraded Socket Weld on 1" diameter Steam Supply Bypass Line with Through-Wall Leak for As-Found Flaw Characterization as Reported in Condition Report CR1136592 3.10 Standard DNES-SU-EM-0023, Rev. 0, Analysis of Safety Related Piping, Surry Power Station Units 1 & 2 3.11 Condition Report CR1136592, Through-wall leak identified upstream of 2-MS-377 3.12 Vendor Document 4211975-DPK-00002, TEAM Industrial Services Branch Work Order 140400181701, Engineering Order# 4211975 Rev. 2 3.13 Temporary Design Change, DC SU-19-00161 Rev.a 3.14 Drawing 11548-FM-064, Sheet 3 of 6, Revision 58 3.15 Dominion Index 4.1 Excalibur -A web based Document Storage Site located at http://index4/DBSSearch.aspx within Dominion's intranet site. 3.16 Navco Piping Datalog, Edition No. 11, 1984, National Valve and Manufacturing Co.
- 4. Computer Codes Used
- NUPIPE-II (Reference 3.7) 731234 (Feb 2019)
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- iii" Energy (!
CM-AA-CLC-301 ATTACHMENT 7 Page 4 of 11 Calculation # CEM-0231 Rev. 0
- 5. Identification of Computer Inputs and Outputs NUPIPE 119025464 I 25-Nov-2019I Corr_ Seismic.inp I Corr_ Seismic.out I Correlation Run 1 - Correlation to CE-0581 Run AAAEPEM Dated 7-29-86 ( Seismic Pipe Stress Run, Tload =17)
Attachment I (Reference3. 7) See NUPIPE (Reference3. 7) 119121703 I 25-Nov-2019I Corr_DW.inp I Corr_DW.out I Correlation Run 2 - Correlation to CE-0581 Run AAAEDCB Dated 8-11-86 (DW + TH Pipe Stress Run, Tload =3) See Attachment J Study Run 1 - Combine the Seismic and DW Runs into one Analysis eadweigt, Thermal, Seismic Pipe Stress Analysis (Tload = 3) of piping 19263425 25-Nov-2019 DW_ Seismic.inp DW_ Seismic.out in correlation runs NUPIPE (Reference3. 7) See Index 4 for the input and output files. I I Study Run 2 - Results for use in Calculation CEM-0232 (Reference 3.9) 119501858 DW_Seismic_1Line. DW_Seismic_1Line. I25_Nov-2019I Deadweight, Thrmal, Seismic Pipe Stress Analysis (Tload = 3) with mp out . NUPIPE add1t1on of the 1' Bypass line off of 4"- SHP-127-601 (Reference3.7) See Attachme nt H Study Run 3 -To determine if support is required. Deadweight, Thermal, Seismic Pipe Stress Analysis (Tload = 3) with DW Seismic_ 1Line_ DW_ Seismic_ 1Line_ _ j 20404614 j 25_Nov-20191 Box.mp I Box.out add1t1on of the 1" Bypass line off of 4"- S HP-127-601 and a seal enclosure NUPIPE 1 device (Reference3. 7) See Index 4 for the input and output files. 731234 (Feb 2019)
r-. Dominion
- .;iii"' Energy 0 Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Page 5 of 11 Calculation # CEM-0231 Rev. 0 I I I I I Study Run 4 -Results used for the evaluation in this calculation NUPIPE (Reference3. 7) j 20385315 I 25_Nov-2019 I DW_ Seisr:nic_1Line_
Box_Sup.inp I DW_ Seismic_1Line_ Box_S up.out Deadweight, Thermal, Seismic Pipe Stress Analysis (Tload = 3) with addition of the 1" Bypass line off of 4"-SHP-127-601, seal enclosure 1 device, and new support on 1" bypass line See Attachment G Study Run 5 -Sensitivity Run for Insulation DW_Seismic_1Line- DW_Seismic_1Line_ Uses Study Run 4 with a change to the weight per foot for the 1" Bypass 18153800 26-Nov-2019 Box_S up_lns.inp Box_Sup_lns.out line as described in Assumptions/Comments Section. NUPIPE (Reference3. 7) See Index 4 for the input and output files. Study Run 6 -Sensitivity Run for Insulation I I I DWSeismic_1Line_ DW_Seismic_1Line_ Uses Study Run 2 with a change to the weight per foot for the 1" Bypass 11423936 26_Nov-2019 1 lns.1np Ins.out line as described in Assumptions/Comments Section. NUPIPE (Reference3. 7) See Index 4 for the input and output files. 731234 (Feb 2019)
- o. om. inion Complete Calculation f£':
p Energy (g CM-AA-CLC-301 ATTACHMENT 7 Page 6 of 11 Calculation # CEM-0231 Rev. 0
6. Background
Condition Report CR1136592 (Reference 3.11) documents the discovery of a through-weld leak at a socket weld on the 1" diameter steam supply bypass line (labeled as 1 "-SHP--601 on 11548-FM-064A, Sheet 3, Reference 3.14). The following flaw characterization was provided by Surry Power Station and is documented in the 100 attached to Condition Report CR1136592: CR1136545 documented a measured 6dpm leak was found dripping from th& insulation just upstream of 2-MS-377 ( SG 1 C AFW Pump Steam Supply Bypass). The leak target was 1-FW-MOV-1608 1/..F\/\/ Crosstie rsoiation to Unit '1), NDE and System Engineering were tasked to investigate a potential through-wail ieak on i" main steam piping upstream of 2-MS-3T7 Unexplained water was identified in the genera! area and insulation was removed. A very sma!I through--wail ieak (characterized as a pinhole) was confi11T1ed using a mirror and based on the sound of the Jisak. lt is very difficult to see steam exiting the pinhole, The location appears to be at the fitting side weld toe at approximately *1:00 when looking upstream. The we!d is a socket weld and is at a 90-degree fitting located t1.vo elbows upstrearn of 2-MS-377. This pipina is shown on drawino 1 i548-CBM-064A-5 Sheet 3 of 6 and is iocated in the Main Steam Valve House 27' elevation approximE1tefy 12 feet off the f!oor. It is a i" line that bypasses vaive 2-MS-*158. This i" line is i\SME Class 2 piping To summarize the flaw characterization, the flavv is located at or ver)' near the fitting side weld toe at approximately 1 :00 when looking upstream, is very small pinhole (i/32" or less) and is ilkely caused by a fabrication welding defect. An additional engineering wa!kdown confirmed no apparent leakage on tt1e sister A and B trains. fviinor low frequency movement of the 1" bypass line was observed. Calculation CEM-0232 (Reference 3.9) evaluated the as-found weld flaw in the affected socket weld of the 1" SHP line to demonstrate that it would have remained structurally adequate for pressure thrust forces corresponding to the design pressure and for design basis loading conditions. Calculation CE-0232 was used to support the past operability of the line. An integral leak seal enclosure / structural clamping device is to be installed to secure the leak until repairs of the line can be made. The qualification of the leak seal enclosure device is provided in Reference 3.12. This calculation evaluates the adequacy of the piping with the proposed leak seal enclosure device installed and also provides stresses, forces, and moments for the existing piping without the leak seal enclosure for use in Calculation CEM-0232 (Reference 3.9). The analysis of the record for the piping associated with this 1" bypass line is CE-0581 (Reference 3.4). It should be noted that CE-0581 does not include the 1" bypass line. Thus, the analysis completed herein utilizes the stress analysis from CE-0581 and updates it to include the 1"-SHP- -601 line off of the 4"-SHP-127-601 line and the leak seal enclosure device. Several NUPIPE runs were made in order to determine if the addition of the leak seal enclosure device would be acceptable and meet the piping code requirements. (Refer to Section 5 for a list of the NUPIPE input and output files used in this calculation.) Correlation runs were initially completed to ensure the results of the NUPIPE runs that were based on the runs of records in CE-0581 matched (refer to Assumptions/Comments Section). Since CE-0581 maintained separate runs of records for the Seismic case and the OW and Thermal case, a run was made to combine the two runs into one study run (Study Run 1) for use in this calculation. Study Run 2 was then made to add the 1" bypass line in question as the CE-0581 runs did not include this line. Study Run 3 was made to determine if a support would be required for the 1" bypass line with the leak seal enclosure device installed. Review of Study Run 3 indicated that the stresses exceed the code allowables (Reference 3.2), thus it was determined that a support would be required. Study Run 4 was made which includes the 1" bypass line, the weight of the leak seal enclosure and a vertical support on the 1" bypass line. The results documented in this calculation are based on Study Run 4. Note that both Study Runs 5 and 6 were made as sensitive runs for to determine impact of insulation on the 1"-SHP- -601 bypass line - refer to Assumptions / Comments Section for additional information. 731234 (Feb 2019)
Complete Calculation Dominion j# Energy* CM-AA-CLC-301 ATTACHMENT 7 Page 7 of 11 Calculation # CEM-0231 Rev. 0
- 7. Design Inputs
- 1. Existing NUPIPE Runs from Problem 2746, Calculation CE-0581 Rev. 0; in particular the Seismic Stress Run of Record, Run AAAEPEM, Dated 7-29-86 and the Deadweight and Thermal Stress Run of Record, Run AAAEDCB, Dated 8-11-86.
- 2. The leak seal enclosure device weighs 57 lbs. per Document 4211975-DPK-00002 which was provided by TEAM Industrial Services (Reference 3.12). Note that this pipe stress analyses made in this calculation conservatively uses a weight of 60 lbs. for the leak seal enclosure device.
- 3. As-built dimensions of the 1"-SHP - -601 bypass line off of line 4"-SHP-127-601 provided by Station Engineering (See Attachment B)
- 8. Assumptions I Comments
- The new support installed on the 1"-SHP- -601 bypass line off of line 4"-SHP-127-601 is modeled in the NUPIPE analysis (input file: DW_Seismic_1 Line_Box_Sup.inp) at the mid-point (i.e., node point 6040) between the elbows at node points 6030 and 6060. In other words, the support is modeled 11.5" from the centerline of the elbow with the as-found weld flaw (node point 6030).
- Calculation CE-0581 Rev. 0 has an addendum (Addendum 00A) that reviews a proposed routing change to line 3"-SHP-129-601. The addendum did not re-analyze the piping. Given that the area of interest of this calculation was not near this re-routed piping, this change was not included in the NUPIPE analyses completed herein; however, as was previously documented in Add. 00A of CE-0581, the piping and support loads in the vicinity of the routing change for line 3"-SHP-129-601 will not significantly affect the structural integrity of the piping or the pipe supports.
- Insulation on the 1"-SHP- - 601 line was overlooked when the analysis was performed and thus it was not included as part of the weight of the 1" pipe. Based on the Navco Piping Datalog (Reference 3.16), the 1" line at 505 deg F should have 2" of insulation which would weigh 1.76 lbs/ft assuming calcium silicate insulation with a density of 11 lbs/cu.ft. Sensitivity runs were performed for comparison to Study Runs 2 and 4 to ensure that the added weight from the insulation would not adversely affect the results of the analyses used herein. Review of the sensitivity runs show that the resulting maximum stresses on the 1" line minimally increase. Therefore, the results of Study Runs 2 and 4 are still acceptable for use in both CEM-0232 and this calculation evaluation, respectively. (Note that the two sensitivity runs, Study Runs 5 and 6, are only provided in Index 4 as part of the source documents for this calculation.)
- The Correlations Runs 1 and 2 compared well to the results (both support reactions and stresses) documented on the microfiche for Calculation CE-0581 Rev. 0 Run of Records for the Seismic analysis (Run ID AAAEPEM, dated 7-29-86) and for the Deadweight and Thermal analysis (Run AAAEDCB, dated 8-11-86), respectively. Therefore, the NU PIPE Correlation Runs 1 and 2 are acceptable for use in this calculation.
731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Page 8 of 11 Calculation # CEM-0231 Rev. 0
- 9. Methodology To determine acceptability of the leak seal enclosure device on the 1" line, pipe stress analyses are made and the stresses are compared to the code allowables as defined in Dominion Standard DNES-SU-EM-0023 which follows the requirements of ANSI B31.1-67 (References 3.10 and 3.2, respectively). The piping stresses are analyzed in NUPIPE-11 (Reference 3.7).
The basic method of analysis used in NUPIPE-11 is the finite element stiffness method. In accordance with this method, the continuous piping is mathematically idealized as an assembly of elastic structural members connecting discrete nodal points. Nodal points are placed in such a manner as to isolate particular types of piping elements, such as straight runs of pipe, elbows, valves etc., for which force-deformation characteristics can be categorized. Nodal points are also placed at all discontinuities; such as piping supports, concentrated weights, branch lines and changes in cross section. System loads, such as weights are applied at the nodal points. Stiffness characteristics of the interconnecting members are related to the effective shear area and moment of inertia of the pipe.
- 10. Calculations The computer code, NUPIPE (Reference 3.7), is used to evaluate the piping system in this calculation. Thus, refer to the NUPIPE output file for Study Run 4 in Attachment G and for Study Run 2 in Attachment H.
The supports are compared in a table provided in Attachment E for the Support Load Comparison. The temporary new support evaluation is provided in Attachment F.
- 11. Acceptance Criteria
- 1. PIPING CODE APPLICABILITY The code of record for Surry Power Station Pressure Piping is ASA B31.1-1955 including addenda thru Code Case N7 dated September 1962. For the purpose of piping analysis, Power Piping Code USAS B31.1.0 - 1967 is used. The 1967 code meets or exceeds the requirements of the 1955 code.
- 2. PIPING SPECIFICATION
- DNES-SU-ME-0004 "Pipe Class Design Standard", (Reference 3.8).
731234 (Feb 2019)
Complete Calculation f,$ p D om* * .inion Energy CM-AA-CLC-301 ATTACHMENT 7 Page 9 of 11 Calculation # CEM-0231 Rev. O
- 12. Results 12.1 Review of Maximum Pipe Stress Summary of Entire Piping System Analyzed in Study Run 4 NUPIPE Input File: DW_Seismic_1 Line_Box_Sup.inp NUPIPE Run ID: 20385315 NUPIPE Run Date: 25-Nov-2019 2,830 + 3,311 = 6,141 15,000 (2) 400 2,830 + 13,232 = 16,062 18,000 (3) 260 2,376 + 19363 = 21,739 27,000 (4) 100 24,244 22,500
- 2,376 + 2,778 + 24,244 (5) 100 37,500
= 29,398 12.2 Review of Pipe Stress Summary of the 1"-SHP- -601 Bypass Line off of 4"-SHP-127-601 (Node Points 6000-6110 only) Analyzed in Study Run 4 NUPIPE Input File: DW_Seismic_1 Line_Box_Sup.inp NUPIPE Run ID: 20385315 NUPIPE Run Date: 25-Nov-2019 PQJnt(s) psi) 6000 2,830 + 2,780 = 5,610 15,000 (2) 6010 1,222 + 13,529 = 14,751 18,000 (3) 6000 2,830 + 16155 = 18,985 27,000 (4) 6110 7,669 22,500 12.3 Review of the Pipe Vertical Displacement on the 1"-SHP- - 601 Bypass Line off of 4"-SHP-127-601 The maximum vertical deadweight displacement is 0.026" at Node Point 6060 (from Study Run 4, NUPIPE Run ID: 20385315), which is less than the generally accepted value of 1/16" (0.0625") for vertical deadweight displacement. Therefore, the vertical deadweight displacement is acceptable for the 1"-SHP- - 601 bypass line with the leak seal enclosure device and the new support at node point 6040 installed.
731234 (Feb 2019)
Complete Calculation Dominion
'I)# Energy" CM-AA-CLC-301 ATTACHMENT 7 Page 10 of 11 Calculation # CEM-0231 Rev. 0 12.4 Review of the Pipe Support Loads The supports have been reviewed to determine if the support loads for each load case (i.e, Deadweight, Thermal, OBET, DBEI) have changed from the correlation runs (Correlation Runs 1 and 2) to the Study Run 4 of this calculation. Attachment E contains the Support Load Comparison table. Based on the load comparisons provided in the table, only the support at node point 1335 will require additional review. All other existing supports have minimal to no change from the existing analysis completed in the Run of Record Calculation CE-0581 Rev. 0 (Correlation Runs 1 and 2) to Study Run 4 of this calculation.
The support at node point 1335 is actually the location that line 4"-SHP-127-601 connects to line 30"-SHP-103-601. Thus, as long as the stresses on the piping at this location are acceptable then the "support" loads at this connection point are considered acceptable. Reviewing the stress at this point as shown in the following table indicates that all stresses at this location meet the code allowables. Therefore, this "support" location is considered acceptable without further review. S.tress fr9m $tudy RLJn si (pi) (1) 1335 2,830 + 1,602 = 4,432 15,000 (2) S1p + (Sdl + Sobei
- B + Sobea) < 1.2Sh 1335 2,830 + 6,883 = 9,713 18,000 (3) 1335 2,830 + 9253 = 12,083 27,000 (4) 1335 1,327 22,500 A new support is added at Node Point 6040 on the 1"-SHP- - 601 to support the 60 lb. leak seal enclosure device. Per Reference 3.13, this new support will be a temporary support. It is reviewed and analyzed in Attachment F. The new support will be installed per Design Change SU 19-00161 (Reference 3.13). Based on the review provided in Attachment F, the new support is acceptable for all design bases loading conditions.
Based on the results of the support reviews provided above and in Attachments E and F, the supports are acceptable for the loads calculated in Study Run 4 of this calculation. 731234 (Feb 2019)
Complete Calculation &1; p, Dom in.ion Energy . ( CM-AA-CLC-301 ATTACHMENT 7 Page 11 of 11 Calculation# CEM-0231 Rev. O
- 13. Conclusions Based on the review of the stresses for the analyzed piping system and in particular the 1"-SHP- -601 bypass line with the leak seal enclosure device, the piping meets the requirements of the ANSI 831.1 Power Piping Code provided that a vertical support is installed (at node point 6040, see Attachment C) downstream of the leak seal enclosure device. Refer to the design change (Reference 3.13) for the details on the installation of the new support.
- 14. Precautions and Limitations The analysis in this calculation is only to determine acceptability of a temporary condition until the as-found weld flaw at the socket weld elbow connection (Node Point 6030) on the 1"-SHP- - 601 bypass line can be repaired at the next refueling outage. This analysis and its results bound the temporary piping configuration with the clamp installed. The analysis documented in Calculation CE-0581 Rev. 0 is considered to be the run of record for the permanent design configuration.
- 15. Calculation Review Checklist See Attachment A.
- 16. Attachments Attachment A - Calculation Review Checklist (1 page)
Attachment B - As-built Dimensions and Pictures from Station Engineering (3 pages) Attachment C - Math Models (3 pages) Attachment D - Support Load Summary Sheets for the Study Run 4 (22 pages) Attachment E - Support Load Comparisons Table (3 Pages) Attachment F - Evaluation of the New Support on the 1 "-SHP- - 601 Bypass Line (7 pages) Attachment G - NUPIPE Input and Output for Study Run 4 (1429 pages) Attachment H - NUPIPE Input and Output for Study Run 2 (1402 pages) Attachment I - NUPIPE Input and Output Files for the Correlation Run 1 (Seismic) (1229 pages) Attachment J - NU PIPE Input and Output Files for the Correlation Run 2 (DW + TH) (102 pages) 731234 (Feb 2019)
Dominion Complete Calculation p Energy CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. O Attachment A Page A1 of A1 Attachment A - Calculation Review Checklist NOTE: If "Yes" is not answered, an explanation may be provided below. Reference may be made to explanations contained in the calculation or addendum.
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- 1. Have the sources of design inputs been correctly selected and referenced in the calculation? [ X] [ ]
- 2. Are the sources of design inputs up-to-date and retrievable/attached to the calculation? [ X] [ ]
3, Where appropriate, have the other disciplines reviewed or provided the design inputs for which they are responsible? [ X] [ ]
- 4. Have design inputs been confirmed by analysis, test, measurement, field walkdown, or other I
pertinent means as appropriate for the configuration analyzed? [ X] [ ]
- 5. Have the bases for assumptions been adequately and clearly presented and are they bounded by the Station Design Basis? [ X] [ ]
i
- 6. Were appropriate calculation/analytic methods used and are outputs reasonable when compared I
to inputs? [ X] [ ]
- 7. Are computations technically accurate? [ X] [ ]
- 8. Has the calculation made appropriate allowances for instrument errors and calibration equipment errors? [ ] [ X]
- 9. Have those computer codes used in the analysis been referenced in the calculation? [ X] [ ]
- 10. Have all exceptions to station design basis criteria and regulatory requirements been identified and justified in accordance with NQA-1-1994? [ ] [Xl I
- 11. Has the design authority/original preparer for this calculation been informed of its revision or addendum, if required? [ X] [ ]
- 12. Was the pre-job brief completed without any identified HU error precursors/compensating actions?
(If HU error precursors/compensating actions were identified, then mark N/A and provide [ X] [ ] explanation/summary below or attach pre-job brief form to calculation.) Comments: (Attach additional pages if needed) Signature:
-- Date: ?(..-2l,-l°t (Reviewer)
Signature: N/A Date: (Owner's Review, if applicable) Note: Physical or electronic signatures are acceptable. 731234 (Feb 2019)
Complete Calculation
!"9:;
p Dominion Energym CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment 8 Page 81 of 83 Attachment B - As-built Dimensions and Pictures of the 1" Bypass line from Station Engineering Section of Drawing 11548-MKS-131C1 Marked Up with Field Conditions 1" C Stt\N E7!E F:
\IS48-FP-'2+7C:,
731234 (Feb 2019)
Complete Calculation i1' p, Dominion Energy CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. O Attachment 8 Page 82 of 83 731234 (Feb 2019)
Complete Calculation fJ$ Dominion Energy CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. O Attachment B Page 83 of 83 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment C Page C1 of C3 Attachment C - Math Models Note the following Math Models shown on Pages C1 and C2 are from CE-0581 Rev. O
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. (Feb 2019)
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Complete Calculation f=- p Dom.in ion Energy* * (9 CM-AA-CLC-301 ATTACHMENT 7 Calculation# CEM-0231 Rev. 0 Attachment C Page C3 of C3 The following Math Model is generated for this calculation to show the layout and node points of the 1"-SHP- - 601 Bypass Line off of the 4"-SHP-127-601. As shown the 1" line ties into the 4"-SHP-127-601 line at Node Points 1310 and 6000. See the math model on page C2 for additional details of the 4" line. Location of the Seal Enclosure Device 160301 II I'/
.t I Naw upport L ocation I !604ol 1"-SHP- -601
!60701 2-MS-377 ,.
2-MS-158
,r-4"-SHP-127-601 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page D1 of D22 Attachment D - Support Load Summary Sheets for the Study Run 4 The following Support Load Summary Sheets are for Study Run 4 (Input File: DW_Seismic_ 1 Line_Box_Sup.inp), which is the analysis that includes the Leak Seal Enclosure Device and the new support on the 1" bypass line. SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO. [ 5 SUPPORT TYPE: [ COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 115 118 83 286 1136 1680 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 209 140 153 295 2066 1962 (+ OR -) 5 DEADLOAD 31 228 51 -949 762 1506 6 T (+)NORMAL 0 0 279 0 2064 11260 H 7 M (-)NORMAL -227 -320 0 -5389 0 0 8 DESIGN + 146 + 346 + 413 + 0 + 3962 + 14446 LOADl - 311 - 210 - 32 - 6624 - 374 - 174 9 DESIGN + 31 + 228 + 330 + 0 + 2826 + 12766 LOAD2 - 196 - 92 - 0 - 6338 - 0 - 0 10 DESIGN + 240 + 368 + 204 + 0 + 2828 + 3468 LOAD3 - 178 - 0 - 102 - 1244 - 1304 - 456 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + 0 + .036 + .045 (Positive) +Fx = East (Global-in.) .058 0 - 0 (Negative) +Fy Vertical (up)
+Fz = South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA),OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy = Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page D2 of D22 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO. [ 25 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 0 1 0 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 0 0 0 0 0 0 (+ OR -) 5 DEADLOAD 0 0 0 0 0 0 6 T (+)NORMAL 0 4 0 0 0 0 H E R 7 M (-)NORMAL 0 0 0 0 0 0 8 DESIGN + 0 + 5 + 0 + 0 + 0 + 0 LOADl - 0 - 1 - 0 - 0 - 0 - 0 9 DESIGN + 0 + 4 + 0 + 0 + 0 + 0 LOAD2 - 0 - 0 - 0 - 0 - 0 - 0 10 DESIGN + 0 + 0 + 0 + 0 + 0 + 0 LOAD3 - 0 - 0 - 0 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + 0 + .036 + .045 (Positive) +Fx East (Global-in.) .066 0 - 0 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA) ,OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1. 50 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTAC HMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page D3 of D22 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO. [ 43 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 0 149 0 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 0 146 0 0 0 0 (+ OR -) 5 DEADLOAD 0 0 0 0 0 0 6 T (+)NORMAL 0 0 0 0 0 0 H E R 7 M (-)NORMAL 0 0 0 0 0 0 8 DESIGN + 0 + 149 + 0 + 0 + 0 + 0 LOADl - 0 - 149 - 0 - 0 - 0 - 0 9 DESIGN + 0 + 0 + 0 + 0 + 0 + 0 LOAD2 - 0 - 0 - 0 - 0 - 0 - 0 10 DESIGN + 0 + 146 + 0 + 0 + 0 + 0 LOAD3 - 0 - 146 - 0 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + 0 + .016 + .035 (Positive) +Fx East (Global-in.) .191 0 - 0 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA) ,OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page D4 of D22 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO.[ 60 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 0 349 91 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 0 351 158 0 0 0 (+ OR -) 5 DEADLOAD 0 -453 -27 0 0 0 6 T (+)NORMAL 0 0 440 0 0 0 H 7 M (-)NORMAL 0 -385 0 0 0 0 8 DESIGN + 0 + 0 + 504 + 0 + 0 + 0 LOADl - 0 - 1187 - 118 - 0 - 0 - 0 9 DESIGN + 0 + 0 + 413 + 0 + 0 + 0 LOAD2 - 0 - 838 - 27 - 0 - 0 - 0 10 DESIGN + 0 + 0 + 131 + 0 + 0 + 0 LOAD3 - 0 - 804 - 185 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + 0 + 0 + .002 (Positive) +Fx East (Global-in.) .212 .002 - 0 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA) ,OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTAC HMENT 7 Calculation # CEM-0231 Rev. 0 Attachment 0 Page 05 of 022 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO.[ 82 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 131 0 0 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 146 0 0 0 0 0 (+ OR -) 5 DEADLOAD 0 0 0 0 0 0 6 T (+)NORMAL 0 0 0 0 0 0 H E 7 M (-)NORMAL 0 0 0 0 0 0 8 DESIGN + 131 + 0 + 0 + 0 + 0 + 0 LOADl - 131 - 0 - 0 - 0 - 0 - 0 9 DESIGN + 0 + 0 + 0 + 0 + 0 + 0 LOAD2 - 0 - 0 - 0 - 0 - 0 - 0 10 DESIGN + 146 + 0 + 0 + 0 + 0 + 0 LOAD3 - 146 - 0 - 0 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + 0 + 0 + 0 (Positive) +Fx East (Global-in.) .207 - .04 - .075 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA),OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTAC HMENT 7 Calculation # CEM-0231 Rev. 0 Attachment 0 Page 06 of 022 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO. [ 120 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 0 239 0 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 0 345 0 0 0 0 (+ OR -) 5 DEADLOAD 0 -941 0 0 0 0 6 T (+)NORMAL 0 0 0 0 0 0 H 7 M (-)NORMAL 0 -326 0 0 0 0 8 DESIGN + 0 + 0 + 0 + 0 + 0 + 0 LOADl - 0 - 1506 - 0 - 0 - 0 - 0 9 DESIGN + 0 + 0 + 0 + 0 + 0 + 0 LOAD2 - 0 - 1267 - 0 - 0 - 0 - 0 10 DESIGN + 0 + 0 + 0 + 0 + 0 + 0 LOAD3 - 0 - 1286 - 0 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + 0 + 0 + 0 (Positive) +Fx East (Global-in.) .131 .002 - .049 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA),OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page D7 of D22 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO.[ 240 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 0 551 303 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 0 512 126 0 0 0 (+ OR -) 5 DEADLOAD 0 155 -34 0 0 0 6 T (+)NORMAL 0 688 52 0 0 0 H E R 7 M (-)NORMAL 0 0 0 0 0 0 8 DESIGN + 0 + 1394 + 321 + 0 + 0 + 0 LOADl - 0 - 396 - 337 - 0 - 0 - 0 9 DESIGN + 0 + 843 + 18 + 0 + 0 + 0 LOAD2 - 0 - 0 - 34 - 0 - 0 - 0 10 DESIGN + 0 + 667 + 92 + 0 + 0 + 0 LOAD3 - 0 - 357 - 160 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + 0 + .003 + 0 (Positive) +Fx East (Global-in.) .185 0 - 0 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA) ,OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page 08 of D22 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO. [ 256 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 474 580 0 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 379 625 0 0 0 0 (+ OR -) 5 DEADLOAD -78 -791 0 0 0 0 6 T (+)NORMAL 0 0 0 0 0 0 H 7 M (-)NORMAL -52 -55 0 0 0 0 8 DESIGN + 396 + 0 + 0 + 0 + 0 + 0 LOADl - 604 - 1426 - 0 - 0 - 0 - 0 9 DESIGN + 0 + 0 + 0 + 0 + 0 + 0 LOAD2 - 130 - 846 - 0 - 0 - 0 - 0 10 DESIGN + 301 + 0 + 0 + 0 + 0 + 0 LOAD3 - 457 - 1416 - 0 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + 0 + 0 + .367 (Positive) +Fx East (Global-in.) 0 - 0 - 0 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA) ,OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
f,:; p Dominion Energy (!) Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page D9 of D22 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO.[ 335 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 0 13 0 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 0 2 0 0 0 0 (+ OR -) 5 DEADLOAD 0 -1 0 0 0 0 6 T (+)NORMAL 0 23 0 0 0 0 H 7 M (-)NORMAL 0 0 0 0 0 0 8 DESIGN + 0 + 35 + 0 + 0 + 0 + 0 LOADl - 0 - 14 - 0 - 0 - 0 - 0 9 DESIGN + 0 + 22 + 0 + 0 + 0 + 0 LOAD2 - 0 - 1 - 0 - 0 - 0 - 0 10 DESIGN + 0 + 1 + 0 + 0 + 0 + 0 LOAD3 - 0 - 3 - 0 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + .059 + .249 + .666 (Positive) +Fx East (Global-in.) 0 - 0 - 0 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA),OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page D1 O of D22 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO. [ 500 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 212 285 592 21240 18018 5025 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 154 104 308 3372 7374 2982 (+ OR -) 5 DEADLOAD 13 -345 -44 2770 2095 -2818 6 T (+)NORMAL 0 305 0 0 0 3734 H 7 M (-)NORMAL -32 0 -1125 -16127 -3174 0 8 DESIGN + 225 + 245 + 548 + 24010 + 20113 + 5941 LOADl - 231 - 630 - 1761 - 34597 - 19097 - 7843 9 DESIGN + 13 + 0 + 0 + 2770 + 2095 + 916 LOAD2 - 19 - 345 - 1169 - 13357 - 1079 - 2818 10 DESIGN + 167 + 0 + 264 + 6142 + 9469 + 164 LOAD3 - 141 - 449 - 352 - 602 - 5279 - 5800 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + .091 + .15 + . 43 (Positive) +Fx East (Global-in.) - 0 - 0 - 0 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA) ,OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTAC HMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page D11 of D22 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO. [ 1580 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 0 0 213 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 0 0 115 0 0 0 (+ OR -) 5 DEADLOAD 0 0 18 0 0 0 6 T (+)NORMAL 0 0 319 0 0 0 H E R 7 M (-)NORMAL 0 0 0 0 0 0 8 DESIGN + 0 + 0 + 550 + 0 + 0 + 0 LOADl - 0 - 0 - 195 - 0 - 0 - 0 9 DESIGN + 0 + 0 + 337 + 0 + 0 + 0 LOAD2 - 0 - 0 - 0 - 0 - 0 - 0 10 DESIGN + 0 + 0 + 133 + 0 + 0 + 0 LOAD3 - 0 - 0 - 97 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + 0 + 0 + .002 (Positive) +Fx East (Global-in.) - .192 - .016 - 0 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA) ,OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
Complete Calculation f:;, p Dominion Energy(ll CM-AA-CLC-301 ATTAC HMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page D12 of D22 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO.[ 1620 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 0 15 0 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 0 9 0 0 0 0 (+ OR -) 5 DEADLOAD 0 1 0 0 0 0 6 T (+)NORMAL 0 0 0 0 0 0 H E R 7 M (-)NORMAL 0 0 0 0 0 0 8 DESIGN + 0 + 16 + 0 + 0 + 0 + 0 LOADl - 0 - 14 - 0 - 0 - 0 - 0 9 DESIGN + 0 + 1 + 0 + 0 + 0 + 0 LOAD2 - 0 - 0 - 0 - 0 - 0 - 0 10 DESIGN + 0 + 10 + 0 + 0 + 0 + 0 LOAD3 - 0 - 8 - 0 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + 0 + 0 + 0 (Positive) +Fx East (Global-in.) .139 - .006 - .013 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA),OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page D13 of D22 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO. [ 1680 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 0 23 0 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 0 3 0 0 0 0 (+ OR -) 5 DEADLOAD 0 -1 0 0 0 0 6 T (+)NORMAL 0 14 0 0 0 0 H E R 7 M (-)NORMAL 0 0 0 0 0 0 8 DESIGN + 0 + 36 + 0 + 0 + 0 + 0 LOADl - 0 - 24 - 0 - 0 - 0 - 0 9 DESIGN + 0 + 13 + 0 + 0 + 0 + 0 LOAD2 - 0 - 1 - 0 - 0 - 0 - 0 10 DESIGN + 0 + 2 + 0 + 0 + 0 + 0 LOAD3 - 0 - 4 - 0 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + .18 + .147 + .554 (Positive) +Fx East (Global-in.) 0 0 - 0 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA) ,OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTAC HMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page D14 of D22 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO.[ 2000 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 271 138 128 7769 11679 6480 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 329 160 156 6516 13921 5931 (+ OR -) 5 DEADLOAD 19 -298 -13 2116 853 -1923 6 T (+)NORMAL 117 0 0 0 365 0 H E R 7 M (-)NORMAL 0 -15 -87 -3988 0 -463 8 DESIGN + 407 + 0 + 115 + 9885 + 12897 + 4557 LOADl - 252 - 451 - 228 - 9641 - 10826 - 8866 9 DESIGN + 136 + 0 + 0 + 2116 + 1218 + 0 LOAD2 - 0 - 313 - 100 - 1872 - 0 - 2386 10 DESIGN + 348 + 0 + 143 + 8632 + 14774 + 4008 LOAD3 - 310 - 458 - 169 - 4400 - 13068 - 7854 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + .114 + .148 + .405 (Positive) +Fx East (Global-in.) 0 - 0 - 0 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA) ,OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page D15 of D22 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. [ PROB NO. STRESS POINT NO. [ 1210 -SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 0 0 233 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 0 0 188 0 0 0 (+ OR -) 5 DEADLOAD 0 0 53 0 0 0 6 T (+)NORMAL 0 0 181 0 0 0 H E R 7 M (-)NORMAL 0 0 0 0 0 0 8 DESIGN + 0 + 0 + 467 + 0 + 0 + 0 LOADl - 0 - 0 - 180 - 0 - 0 - 0 9 DESIGN + 0 + 0 + 234 + 0 + 0 + 0 LOAD2 - 0 - 0 - 0 - 0 - 0 - 0 10 DESIGN + 0 + 0 + 241 + 0 + 0 + 0 LOAD3 - 0 - 0 - 135 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + 0 + 0 + .001 (Positive) +Fx East (Global-in.) - .464 - .025 - 0 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA) ,OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page D16 of D22 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO.[ 1230 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 6 0 0 3 EARTHQUAKE OBEI + OBEA 0 25 0 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 0 18 0 0 0 0 (+ OR -) 5 DEADLOAD 0 6 0 0 0 0 6 T (+)NORMAL 0 0 0 0 0 0 H E R 7 M (-)NORMAL 0 -12 0 0 0 0 8 DESIGN + 0 + 31 + 0 + 0 + 0 + 0 LOADl - 0 - 31 - 0 - 0 - 0 - 0 9 DESIGN + 0 + 6 + 0 + 0 + 0 + 0 LOAD2 - 0 - 6 - 0 - 0 - 0 - 0 10 DESIGN + 0 + 24 + 0 + 0 + 0 + 0 LOAD3 - 0 - 12 - 0 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + 0 + 0 + 0 (Positive) +Fx East (Global-in.) .471 - .13 - .107 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA) ,OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page D17 of D22 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO.[ 1245 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 0 5 0 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 0 4 0 0 0 0 (+ OR -) 5 DEADLOAD 0 1 0 0 0 0 6 T (+)NORMAL 0 0 0 0 0 0 H E R 7 M (-)NORMAL 0 -2 0 0 0 0 8 DESIGN + 0 + 6 + 0 + 0 + 0 + 0 LOADl - 0 - 6 - 0 - 0 - 0 - 0 9 DESIGN + 0 + 1 + 0 + 0 + 0 + 0 LOAD2 - 0 - 1 - 0 - 0 - 0 - 0 10 DESIGN + 0 + 5 + 0 + 0 + 0 + 0 LOAD3 - 0 - 3 - 0 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + 0 + 0 + .203 (Positive) +Fx East (Global-in.) .196 - .038 - 0 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA) ,OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page D18 of D22 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO.[ 1255 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 0 206 0 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 0 107 0 0 0 0 (+ OR -) 5 DEADLOAD 0 20 0 0 0 0 6 T (+)NORMAL 0 214 0 0 0 0 H 7 M (-)NORMAL 0 0 0 0 0 0 8 DESIGN + 0 + 440 + 0 + 0 + 0 + 0 LOADl - 0 - 186 - 0 - 0 - 0 - 0 9 DESIGN + 0 + 234 + 0 + 0 + 0 + 0 LOAD2 - 0 - 0 - 0 - 0 - 0 - 0 10 DESIGN + 0 + 127 + 0 + 0 + 0 + 0 LOAD3 - 0 - 87 - 0 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + 0 + .001 + .354 (Positive) +Fx East (Global-in.) .077 0 - 0 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA) ,OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
r:;e Dominion Complete Calculation jJ! Energy* CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page D19 of D22 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO.[ 1290 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 0 34 0 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 0 13 0 0 0 0 (+ OR -) 5 DEADLOAD 0 9 0 0 0 0 6 T (+)NORMAL 0 11 0 0 0 0 H E R 7 M (-)NORMAL 0 0 0 0 0 0 8 DESIGN + 0 + 54 + 0 + 0 + 0 + 0 LOADl - 0 - 25 - 0 - 0 - 0 - 0 9 DESIGN + 0 + 20 + 0 + 0 + 0 + 0 LOAD2 - 0 - 0 - 0 - 0 - 0 - 0 10 DESIGN + 0 + 22 + 0 + 0 + 0 + 0 LOAD3 - 0 - 4 - 0 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + .249 + .086 + .626 (Positive) +Fx East (Global-in.) 0 0 - 0 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA),OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment 0 Page 020 of 022 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO.[ 1300 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 0 31 0 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 0 6 0 0 0 0 (+ OR -) 5 DEADLOAD 0 5 0 0 0 0 6 T (+)NORMAL 0 13 0 0 0 0 H E R 7 M (-)NORMAL 0 0 0 0 0 0 8 DESIGN + 0 + 49 + 0 + 0 + 0 + 0 LOADl - 0 - 26 - 0 - 0 - 0 - 0 9 DESIGN + 0 + 18 + 0 + 0 + 0 + 0 LOAD2 - 0 - 0 - 0 - 0 - 0 - 0 10 DESIGN + 0 + 11 + 0 + 0 + 0 + 0 LOAD3 - 0 - 1 - 0 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + .231 + .106 + .541 (Positive) +Fx East (Global-in.) 0 - 0 - 0 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA) ,OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234(Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment D Page D21 of D22 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO. [ 1335 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 372 346 176 15843 16993 5915 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 505 162 272 10662 21763 6211 (+ OR -) 5 DEADLOAD 15 -174 -5 -6791 626 -535 6 T (+)NORMAL 194 0 0 4670 2276 0 H E R 7 M (-)NORMAL 0 -243 -58 0 0 -2272 8 DESIGN + 581 + 172 + 171 + 13722 + 19895 + 5380 LOADl - 357 - 763 - 239 - 22634 - 16367 - 8722 9 DESIGN + 209 + 0 + 0 + 0 + 2902 + 0 LOAD2 - 0 - 417 - 63 - 6791 - 0 - 2807 10 DESIGN + 520 + 0 + 267 + 3871 + 22389 + 5676 LOAD3 - 490 - 336 - 277 - 17453 - 21137 - 6746 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + .147 + .146 + .417 (Positive) +Fx East (Global-in.) 0 - 0 - 0 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA),OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1.50 731234 (Feb 2019)
Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment 0 Page 022 of 022 SUPPORT LOAD TABULATION SHEET RUN ID. 20385315 SURRY POWER STATION RUN DATE 11/25/19 SUPPORT NO. LINE NO. PROB NO. STRESS POINT NO.[ 6040 SUPPORT TYPE: COL LOAD TYPE Fx Fy Fz Mx My Mz (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) 1 LARGEST 0 POSITIVE 0 0 0 0 0 0 C 2 C LARGEST NEGATIVE 0 0 0 0 0 0 3 EARTHQUAKE OBEI + OBEA 0 122 0 0 0 0 (+ OR -) 4 EARTHQUAKE DBE (NOTEl) 0 33 0 0 0 0 (+ OR -) 5 DEADLOAD 0 -68 0 0 0 0 6 T (+) NORMAL 0 87 0 0 0 0 H E R 7 M (-)NORMAL 0 0 0 0 0 0 8 DESIGN + 0 + 141 + 0 + 0 + 0 + 0 LOADl - 0 - 190 - 0 - 0 - 0 - 0 9 DESIGN + 0 + 19 + 0 + 0 + 0 + 0 LOAD2 - 0 - 68 - 0 - 0 - 0 - 0 10 DESIGN + 0 + 0 + 0 + 0 + 0 + 0 LOAD3 - 0 - 101 - 0 - 0 - 0 - 0 (Fx) (Fy) (Fz) 11 THERMAL MVMTS + .329 + 0 + .434 (Positive) +Fx East (Global-in.) - 0 - 0 - 0 (Negative) +Fy Vertical (up)
+Fz South DESIGN LOAD 1 DL + THERMAL + SRSS[(OBEI+OBEA) ,OCCASIONAL]
DESIGN LOAD 2 DL + THERMAL DESIGN LOAD 3 DL + DBE
+Fx = East : +Fy Vertical (UP) : +Fz = South NOTES:
- 1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED
- 2) REFER TO STD-CEN-0023
- 3) OBEI HAS BEEN BUMPED BY 1.25
- 4) DBEI HAS BEEN BUMPED BY 1. 50 731234 (Feb 2019)
i= Dominion Energy'* Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment E Page E1 of E3 Attachment E - Support Load Comparison Table Deadweight Case Thermal Case i OBETx Bump DBEI x Bump Correlation Correlation Correlation Correlation Study Study Study Study Run 1 Run 1 I Run 2 Run 2 Run 4: Ratio Run 4: Ratio Run 4: Ratio Run 4: Ratio (DW+TH (DW+TH (Seismic (Seismic NODE LOAD TYPE DIRECTION Revised Revised I Revised Revised I Revised Revised Revised Revised Comments Analysis) - Analysis)- Analysis) - Analysis)- Loads to Loads to Loads to Loads to Existing Loads Existing Loads Existing Loads Existing Loads Existing Existing Existing Existing lbf or lbf or lbf or lbf or lbf or in-lbf lbf or in-lbf lbf or in-lbf lbf or in-lbf in-lbf in-lbf I in-lbf in-lbf 5 FORCE COORD Minimal changes to loads, further review not required.
-31 -31 1.00 227 227 1.00 116 115 0.99 210 209 1.00 X
5 FORCE y COORD I Minimal changes to loads, further review not required.
-228 -228 1.00 320 320 1.00 I 119 118 0.99 141 140 0.99 5 FORCE z COORD Minimal changes to loads, further review not required.
-51 -51 1.00 -279 -279 1.00 83 83 1.00 153 153 1.00 5 MOMENT X COORD Minimal changes to loads, further review not required.
949 949 1.00 5389 5389 1.00 I 286 286 1.00 290 295 1.02 5 MOMENT y COORD Minimal changes to loads, further review not required.
-762 -762 1.00 -2062 -2064 1.00 1134 1136 1.00 2061 2066 1.00 5 MOMENT z COORD Minimal changes to loads, further review not required.
-1507 -1506 1.00 -11259 -11260 1.00 1692 1680 0.99 1968 1962 1.00 25 FORCE y COORD Existing= Minimal changes to loads, further review not required.
0 0 1.00 -4 -4 1.00 0 1 0, Review 0 0 1.00 43 FORCE y COORD
! Snubber I
Snubber I 149 149 1.00 I 144 146 1.01 Minimal changes to loads, further review not required. 60 FORCE COORD Minimal changes to loads, further review not required. y 453 453 1.00 386 385 1.00 350 349 1.00 348 351 1.01 60 FORCE z COORD I f Minimal changes to loads, further review not required. 27 27 1.00 -440 -440 1.00 I 91 91 1.00 156 158 1.01 82 FORCE X COORD Snubber Snubber
; 132 131 0.99 145 146 1.01 Minimal changes to loads, further review not required.
120 FORCE y COORD 941 941 1.00 326 326 1.00 I, 239 239 1.00 344 345 1.00 No changes to the support loads, further review not required. 240 FORCE y COORD Minimal changes to loads, further review not required.
-155 -155 1.00 -686 -688 1.00 I 561 551 0.98 530 512 0.97 240 FORCE z COORD 34 34 1.00 -53 -52 o.98 I 305 303 0.99 126 126 1.00 Minimal changes to loads, further review not required.
256 FORCE COORD Minimal changes to loads, further review not required. 78 78 1.00 53 52 0.98 482 474 0.98 394 379 0.96 X 256 FORCE y COORD Minimal changes to loads, further review not required. I 791 791 1.00 54 55 1.02
- 607 580 0.96 651 625 0.96 Existing=
335 FORCE y COORD Existing= 0, 1 1 1.00 -23 -23 1.00 I 0 13 0, Review 0 2 Review Loads are minimal (only 13 lbf], further review not required.) 731234(Fob2019)
Dominion Complete Calculation
- iiiiii' Energy CM-AA-CLC-301 ATTACHMENT 7 Calculation# CEM-0231 Rev. O Attachment E Page E2 of E3 Deadweight Case Correlation Correlation Thermal Case I OBETx Bump DBEI x Bump Correlation Correlation Run 1 Study Run 1 Study* I Run 2 Study Run 2 Study Run 4
- Ratio Run 4: Ratio Run 4: Ratio Run 4: Ratio (DW+T H (DW+TH (Seismic (Seismic NODE LOAD TYPE DIRECTION Analysis)-
Revised Revised Analysis)- Revised Revised I Analysis)- Revised Revised Analysis)- Revised Revised Comments Loads to Loads to Loads to Loads to Existing Loads Existing Loads Existing Loads Existing Loads Existing Existing Existing Existing lbf or lbf or lbf or lbf or lbf or in-lbf lbf or in-lbf lbf or in-lbf lbf or in-lbf in-lbf in-lbf in-lbf in-lbf 500 FORCE X COORD Minimal changes to loads, further review not required.
-13 -13 1.00 32 32 1.00 213 212 1.00 156 154 0.99 500 FORCE y COORD I 345 Minimal changes to loads, further review not required.
345 1.00 -305 -305 1.00 278 285 1.03 101 104 1.03 500 FORCE z COORD I Minimal changes to loads, further review not required. 45 44 0.98 1124 1125 1.00 580 592 1.02 304 308 1.01 500 MOMENT X COORD Minimal changes to loads, further review not required.
-2765 -2770 1.00 16125 16127 1.00 : 21251 21240 1.00 3605 3372 0.94 500 MOMENT y COORD Minimal changes to loads, further review not required.
-2095 -2095 1.00 3198 3174 0.99 18184 18018 0.99 7634 7374 0.97 500 MOMENT z COORD Minimal changes to loads, further review not required.
2818 2818 1.00 -3741 -3734 1.00 5002 5025 1.00 2919 2982 1.02 1580 FORCE z COORD Minimal changes to loads, further review not required.
-18 -18 1.00 -319 -319 1.00 213 213 1.00 120 115 0.96 I
Existing= 1620 FORCE y COORD Existing= 0, I -1 -1 1.00 0 0 1.00 I 0 15 0, Review 0 9 Review Loads are minimal (under 25 lbf) further review not required. Existing= 1680 FORCE y COORD Existing= 0, 1 1 1.00 -14 -14 1.00 I 0 23 0, Review 0 3 Review Loads are minimal (under 25 lbf) further review not required. 2000 FORCE X COORD Minimal changes to loads, further review not required.
-19 -19 1.00 -116 -117 1.01 277 271 0.98 338 329 0.97 2000 FORCE y COORD 298 298 1.00 15 15 1.00 123 138 1.12 160 160 1.00 Load increase Is minimal (only 15 lbf), further review not required.
2000 FORCE z COORD Minimal changes to loads, further review not required. 13 13 1.00 87 87 1.00 128 128 1.00 155 156 1.01 2000 MOMENT X COORD
-2116 -2116 1.00 3988 3988 1.00 I 7066 7769 1.10 I 6560 6516 0.99 '
Minimal changes to loads, further review not required. 2000 MOMENT y COORD I I
-851 -853 1.00 Minimal changes to loads, further review not required.
-345 -365 1.06 11918 11679 0.98 14325 13921 0.97 2000 MOMENT z COORD Minimal changes to loads, further review not required.
1924 1923 1.00 454 463 1.02 6727 6480 0.96 6113 5931 0.97 1210 FORCE z COORD Minimal changes to loads, further review not required.
-53 -53 1.00 -180 -181 1.01 229 233 1.02 192 188 0.98 Existing=
1230 FORCE y COORD Existing= 0,
-7 -6 0.86 12 12 1.00 0 25 0, Review 0 18 Review Load increase is minimal (upto 25 lbf), further review not required.
Existing= 1245 FORCE y COORD I Existing= 0,
-1 -1 1.00 2 2 1.00 0 5 0, Review 0 4 Review Load increase is minimal (upto 5 lbf), further review not required.
731234 (Fob 2019)
Dominion Complete Calculation
- iiiiii" Energy CM-AA-CLC-301 ATTACHMENT 7 Calculation# CEM-0231 Rev. O Attachment E Page E3 of E3 Deadweight Case Thermal Case OBETx Bump DBEI x Bump Correlation Correlation Correlation Correlation i Study Study Study Study Run 4
- Run 4: Run 4:
Run 1 I Run 1 Run 2 Run 2 Ratio Ratio Ratio Run 4: Ratio (DW+TH (DW+T H (Seismic (Seismic NODE LOAD TYPE DIRECTION Revised Revised Revised Revised Revised Revised Revised Revised Comments Analysis) - Analysis) - Analysis)- Analysis) Loads to Loads to Loads to Loads to Existing Loads Existing Loads Existing Loads Existing Loads Existing Existing Existing Existing I lbf or lbf or lbf or lbf or lbf or in-lbf lbf or in-lbf lbf or in-lbf lbf or in-lbf in-lbf in-lbf in-lbf in-lbf 1255 FORCE y COORD
-18 -20 1.11 -215 -214 1.00 213 206 0.97 109 107 0.98 Load increase is minimal (only 2 lbf), further review not required.
Existing= 1290 FORCE y COORD I I Existing= 0, I
-8 -9 1.13 -12 -11 0.92 0 34 0, Review 0 13 Review Load increase is minimal (only 1 lbf), further review not required.
Existing= 1300 FORCE y COORD Existing= 0,
-4 -5 1.25 -14 -13 0.93 0 31 0, Review 0 6 Review Load increase is minimal (only 1 lbf), further review not required.
1335 FORCE X COORD I Minimal changes to loads, further review not required.
-15 -15 1.00 -196 -194 0.99 1 366 372 1.02 496 505 1.02 1335 FORCE y COORD J Further Review Required -
144 174 1.21 158 243 1.54 202 346 1.71 170 162 0.95 Refer to Section 12.4 for Review 1335 FORCE z COORD Further Review Required - 5 5 1.00 59 58 0.98 148 176 1.19 225 272 1.21 Refer to Section 12.4 for Review IiI Further Review Required - 1.29 1335 MOMENT X COORD 6598 6791 1.03 -3776 -4670 1.24 12290 15843 10975 10662 0.97 Refer to Section 12.4 for Review 1335 MOMENT y COORD I
-618 -626 1.01 -2347 -2276 0.97 16689 16993 1.02 21200 21763 1.03 Minimal changes to load cases, further review not required.
I, z 4.78 1335 MOMENT COORD Further Review Required -
-112 535 -513 2272 4.431 8625 5915 0.69 6380 6211 0.97 Refer to Section 12.4 for Review 731234(Fob2019)
S-:. Dominion Attachment F
- iii" Energy Calculation CEM-0231 Rev. 0 Add. N/A if1i e f F * {JPr t-e fe_cof.v\
Prepared By:
- da
-e, 1Jate: 11/26/19 Reviewed By: ; J L, Date:11/26119 The temporary pipe support is evaluated in this attachment using the following*:
DNESVA-EM0024 DNES-VA-EM-0019 DNES-VA-EM-0018 AISC Allowable Stress Design, 9th Edition GTSTRUDL Baseplate Wizard See Attachment 1 to DC SU-19-00161, Pipe Support Design Drawing Design Loads from Stress Model (Stress Point 6040): Fy_up := 1411b Fy_dowrt := -1901b Fy_ne.ad := 681b Angle Iron Properties, 4x4x1/4: Ffriction ;;: 0.3:*Fy_Dead = 20.4lb 1b
\\'tangle:=- 6.6 ft lengthangle := 39in Wtangle := -wtang1e:1engthangle - -21.451b Forces and Moments for Baseplate and Anchor Bolt Assessment length.angle . . .. .
Mx := \Vtang1e* + Fy_do\m*1engthmg1e;;;;;; -,828tn*1b Fy := Fy_down = 0lb "t
- 2 lviy := Ffriction'lengthangle = 796in-Ib
!viz:;;; Oin*lb (No significant torsion on angle section) Fz := Fx == 20.41b Check Stresses in Angle Section:
- 3 San e := LO)tn A.angle ::;:::; 1.94in.
gl I . 2 . 2 F she.at:= ,}Py + Fz = 191 lb T she:. ar **= Fshear = 99-') OKAY, Negligible Aangle in... 2 . 2 115, Mx + My ,., lb lb lb e1h ,ndin := --------- = 9.,(j7 - < OJ,. :36000 -* = 21600 - e ,..,.2 . 1 . 2 s angl e in2 m tn Bending moments increased by factor of 125 per AlSC, Section C5.2.2 t Design of Single Angle Members, This factor accounts for lateral torsional buck.flog The support is intended to be a vertical restraint onfy. There is approximately Q_ T' displacement from seismic event in the X direction. The thermal movements are 0.329 1! in the X direction. The gap on either side (if centered initially) is the following: 4in - :1315:in gap '.= ')
= 1 "J.U1 w"f-;)
i!* Therefore. adequate actual_movement : 0.7in + OJ29in = 1.02m spacing exists, Page F-1 of F-7
Attachment F
!i'i; Dominion Energy Calculation CEM-0231 Rev. 0 Add. N/A Units: Incl1es Pounds 576 -e-le:ments, 6:25 j,a,ints 12.0 11.0 10.0 9.0 7.0 6.0 5.0 4.0 3.0 1.0 0.0 y
Lx o.o 4.0 6.0 8.0 10.CI Baseplate Wizard Model Input File: tempsupportBP.GTBP GTSTRUDL Base Plate save file, version 1.1 $ This is NOT a GTSTRUDL input file, $ and can only be processed by the Base Plate Wizard. $ Generated by Base Plate Wizard version 2017 $ at 13:59:46 November 26, 2019. $---- Plate data ---------------------------------------- 10 12.000000 12.000000 0.500000 0.500000 1 1 1 80 1 28000000.0 0.290000 27000.0 $ Job ID + description ------------------------------ 13 'GT BPW' 'Base plate model from GTSTRUDL Base Plate Wizard' $ Attachments: 1 attachments specified --------------- 100 1 0 1 -1.0000 1.0000 0.0000 0.0000 90.0000 0.0000 Page F-2 of F-7
Dominion Attachment F
,:;# energy* Calculation CEM-0231 Rev. 0 Add. N/A 110 1 6 0 L4x4xl/4 ANGLES 4.0000 4.0000 0.2500 0.0000 0.0000 0.0000
$ ---- Anchors: 4 anchors specified --------------- 200 2 2.5000 2.5000 0.5000 0.0000 0.0000 1 1 1 0 220 1 240000.0000 0 0.0000 0.0000 230 1 0 150000.0000 0 0.0000 240 1 1160.0000 0.0000 0.0000 0.0000 1.0000 1500.0000 0.0000 1.0000 1.0000 200 2 9.5000 2.5000 0.5000 0.0000 0.0000 2 2 2 0 220 2 240000.0000 0 0.0000 0.0000 230 2 0 150000.0000 0 0.0000 240 2 1160.0000 0.0000 0.0000 0.0000 1.0000 1500.0000 0.0000 1.0000 1.0000 200 2 9.5000 9.5000 0.5000 0.0000 0.0000 3 3 3 0 220 3 240000.0000 0 0.0000 0.0000 230 3 0 150000.0000 0 0.0000 240 3 1160.0000 0.0000 0.0000 0.0000 1.0000 1500.0000 0.0000 1.0000 1.0000 200 2 2.5000 9.5000 0.5000 0.0000 0.0000 4 4 4 0 220 4 240000.0000 0 0.0000 0.0000 230 4 0 150000.0000 0 0.0000 240 4 1160.0000 0.0000 0.0000 0.0000 1.0000 1500.0000 0.0000 1.0000 1.0000 $---- Bearing surface --------------- $ User specified concrete Fcp of 4.000 ksi 600 4.000 0.000 0.000000 0.000 0.0000 0.0 $---- Load Cases --------------- 700 0 1 '1' $---- Load values --------------- 701 0 1 20.000 -190.000 20.000 7828.000 796.000 0.000 Results File: tempsupportBP.txt GTSTRUDL Base Plate Wizard 2017 Results Summary Job ID: GT BPW Job
Description:
Base plate model from GTSTRUDL Base Plate Wizard PASSED: Anchors, Plate Stress Input file: \\inbfscdata4\data4_3\nuclear engineering documents\Engineering Mechanics\Calculations\Minton\SPS Main Steam Leak Evaluation\tempsupportBP.gti Plate: 12.000 in X 12.000 in x 0.5000 in 1 load case 1 attachment
# FE ext LoadPoint Section, Offset, Rotation 1 No Plt surf ANGLES: :L4x4xl/4 Offset Plt Center: -1.000, 1.000 Rotation: 90.0 No stiffeners Page F-3 of F-7
Dominion Attachment F
,:JI energy* Calculation CEM-0231 Rev. 0 Add. N/A 4 anchors No constraints No cutouts Bearing surface: Specified concrete Fcp of 4.000 ksi Applied Loads - Units: Inches Pounds Name Att FX FY FZ MX MY MZ 1 1 20.0 -190.0 20.0 7828.0 796.0 0.0 Bearing Surface Pressure Results Maximum pressure of 154.654 psi occurs at joint 185 (4.500, 3.500), load 1 Plate Displacement Results Maximum uplift (+Z) of 0.004697 in occurs at joint 611 (5.000, 12.000), load 1 Maximum depression (-Z) of -0.000475 in occurs at joint 185 (4.500, 3.500), load 1 Plate Stress Results for Stress Types: Von Mises, S1, S2 PASSED: Maximum Von Mises criteria less than allowable of 27000.0 psi PASSED: Maximum Principal plate stress S1 less than allowable of 27000.0 psi PASSED: Maximum Principal plate stress S2 less than allowable of 27000.0 psi Maximum Von Mises criteria of 15807.716 psi occurs at joint 209 (4.031, 3.969), load 1 Maximum Principal stress 81 of 17494.050 psi occurs at joint 209- (4.031, 3.969), load 1 Maximum Principal stress S2 of -17549.780 psi occurs at joint 209 (4.031, 3.969), load 1 Anchor Results: Axial and Shear forces in lbs Interaction exponents: Axial = 1.0000, Shear = 1.0000, Allow = 1.00 All anchors pass the specified allowables Anchor P/F Intact Tension T allow Ratio Shear V allow Ratio Bl P 0.0365 -0.0 1160.0 -0.000 54.7 1500.0 0.036 1 1 1 Page F-4 of F-7
Dominion Attachment F j# Energy* Calculation CEM-0231 Rev. 0 Add. N/A B2 p 0.0285 -0.0 1160.0 -0.000 42.8 1500.0 0.029 1 1 1 B3 p 0.3330 354.3 1160.0 0.305 41.5 1500.0 0.028 1 1 1 B4 p 0.7476 825.7 1160.0 0.712 53.6 1500.0 0.036 1 1 1 Individual anchor results, by load Anchor Load I ratio P/F Axial A Allow A Ratio Shear V Allow V Ratio Bl 1 0.0365 p 0.0 1160.0 0.0000 54.7 1500.0 0.0365 B2 0.0285 p 0.0 1160.0 0.0000 42.8 1500.0 0.0285 B3 0.3330 p -354.3 1160.0 0.3054 41.5 1500.0 0.0276 B4 0.7476 p -825.7 1160.0 0.7118 53.6 1500.0 0.0358 Baseplate Stress Check: Mp = 2 x 826 lb x 4 in = 6608 in*lb (Assume 4" for Ll) S = 12 in x (l/2in) 2 / 6 = 0.5 in3 Fb = Mp/ S = 13,216 psi < 27 ksi, OKAY The following weld check is for the all-around fillet weld at the baseplate attachment. Uses 3/16" all-around weld; drawing specifies 1/4"; therefore results are conservative. All other welds are acceptable by inspection. Page F-5 of F-7
Dominion Attachment F -:J# Energy* Calculation CEM-0231 Rev. 0 Add. N/A ll'.fT.D CA.I CTIP,ITON* (Angle Shapes - \VeldA..11Around Conservative Eq. 11) DEIEBMINE WELD SIZE BETWEEN' LOADS FROM: D STRUDL D CALC. D OTHER MEMBER JOllH START nm COORDUTATE SYSTEM: D LOCAL( D GLOBAL Material Thickness of Thicker Pm Joined: 0.500 m LOADUW CASE; 0EMVELOP:E D LOADING COMD!tlOM FORCES 8.. MOMENTS AT CENTER OF WELD* F1=Fv"" 200 1bf M1=My= 8000 m*1bf F2=Fx= 20 lb{ Mz=Mx= 0 m*lbf F3=Fz= 20 lbf. Mi = Mz= sooo fo *lbf F(.?.II.Ot;*I) = 21000 psi PROVIDED WELD SIZE: 0.250 tn Fy(l,:: },{ctI) = 36000 psi WEID PROPI:;RIIES * (TREATED ASA LINE) a= 4.00 in b= 4.00 fo A=a+b = S.00 in Cs= b8l(2(a + h)] = LOO fo Z1 = a(a + 4b)l6 = 13..33 m2 C1 = <1a/{2(a + b}]"' LOO in I1/C0 =Z,a7(<1+2b)= 4.44 fot: Z = b(4 a+ b)/6 = 13.3:3 fo2 Cp=b*Cs= 3.00 m I3/t;,=Zb/(2a+b)= 4A4. io2 JlCo = Z1al( + 2b) + Z$b3/[a(a + 2b = J/Cp = Z1{a )11b(2 a+ l:>)] + Zsb/(2 <1 + b) = ma 3 F= [ ( t..<1.1 M3 )2 ( F1 M2 r ... A 11 /Co Is /Cp A J/Co
)2 F.3 M2 f2 / 2 EQ.1.1 A J/Cp
+ sooo + sooo )2 F= [ ( 20 )'). + ( 200 + 0 8,00 4.44 4.44 S.00 8.89 20 + 0 )2 f2 2 S.00 8.89 FORCE ON WELD : F ::: 1801 1bf Im REQHIBED WELD SI7.E "Base Metal Gwerns) FY (Base Metal)<= 3S000psi" F = 1801 = 0.125 in < 0.250 in 0.4 (FY (Base Metal)) .4 { 36000 )
CONCLUSION: USE OF . lf4 INCH WELD IS ACCEPTA.BLK Page F-6 of F-7
Dominion Attachment F -:,# energy* Calculation CEM-0231 Rev. 0 Add. N/A su.;F<l?O liO:AJ.) "r}J1T=r.ION sa:E.ET' ROM ID. li 2Cii'.BSal5 l sugR¥ POWER SAlON IUJN" D}\TE ll/25/19 l SUPPORT N(J... f PROB :NO, OOL Fx Fy Fz; Mx y Mz {Th} {lh,} (l:b) {b-lb} (im-lh} {in-lb} 1 (j. 0 0
!.,AAGEST liEll,":lA'TI'iliE 0 {}
3 ..RTRQU..U..E tJBEI: ,t, OEEA 1.22 0 0 {+ O:Jt -)
- 4. ..R'X'H.:QUAKE
;DEi;E ('NOTE1} 0 0
{ (rR -} O* 0 0 T ( +} NORMAL D D H M { ffl } NDP..M1.u.t 0 0 0 0
- OESIG + 0 it* 141
- 0 'F D 4 0 LCll{\Pl - 0 - 190 - 0 - Q - 0 DESIGN + O + 0 LOAD2 ..- G ... 0 1-0 DE8 I Gt ,1, 0 ,i., D + .0 + 0 LO.Jt-.03 - c, - 101 - 0 - 0 (Fx.;} (Fy) (Fz) 11 THE¥:.JU.. MVM'rS + ,. -3 2 + 0 + ., 434 (Pc*aitiva) +Fx z. East 1)Gloha1 - in. } .... o - 0 ,= o (:Nea,ti-vaJ +r.r == Vei".tiaa1 ,(up)
DESIGN !.tD,?:!.D l :; bL -t T"E'.R.Mjj),L ,i, SRB'S ( (0.BE!*OBEA)' t OCCASIONAL] ORS x GJN 1tJ..4]) 2 L'IL + TfllsR}1At DESIGN l!C.\ 3- = DL + Dli.lE l} DEi'.SA MtTST BE I:W.CLUDED Wr'rli PEEI wmu- f'4 l l.. :VES ARE USED
- &J !UtF.t!Jt ':to S':Itl-CtN-002:':I 3} {JB:l!l'. AAS BEEt if..'IMPEti EY J. , ,2 5 i} J:iJ;iE'.I Bl Jif!;{l!JJi tJMPEP. BY 1-, SO-Page F-7 of F-7
Serial No. 19-483 Docket No. 50-281 Enclosure 4 CALCULATION CEM-0232, REVISION 0, "EVALUATION OF DEGRADED SOCKET WELD ON 1" DIAMETER STEAM SUPPLY BYPASS LINE THROUGH WALL LEAK FLAW CHARACTERIZATION AS REPORTED IN CONDITION REPORT CR1136592," DATED 11/26/19 Virginia Electric and Power Company (Dominion Energy Virginia) Surry Power Station Unit 2
fi. Dominion Energy Complete Calculation Complete the fields with text or an X as required. Calculation Number: Revision: Addendum: Sub type: Decommissioning Record? CEM-0232 0 N/A 000 D Yes No Vendor (If not Dominion): Contains Proprietary Information: D Yes No Proprietary Information Owner: N/A QA Program Owner: Dominion Energy D Other: Calculation Quality Class: Safety Related NSQ D Non-Safety Related Subject (Calculation Title): Evaluation of Degraded Socket Weld on 1" diameter Steam Supply Bypass Line with Through-Wall Leak for As-Found Flaw Characterization as Reported in Condition Report CR1136592 Addendum
Title:
N/A Station(s) and Unit(s): NA 1 D2 ISFSI SU 1 2 ISFSI MP 1 D2 03 ISFSI Affected System(s), Structure(s), or Component(s): 38-02-MS-PP-4.00-SHP-PIPE-127-601 38-02-MS--377-VALVE-Purpose (Executive Summary): See page 2 of this calculation. Originator (Qual. Required): Printed Name l l ( l Signature: ( l ( l Date: l l ( l 1 3 1 3 1 3 11/25/19 Reviewer (Qual. Required): Printed Name ( 1 l Type of Review: l2J Signature: Date: Independent 11/i6/11 Approver: Printed Signcffure: Date: Name l \/zt,/19 Note: Physical or electronic signatures are acceptable. Note: (1) Add lines for additional originators or reviewers as necessary. (2) Note if reviews are "Independent," "Peer, "Subject Matter Expert", "Supervisor, or "Owner 's". (3) Enter N/A for Owner's Review of Vendor Calculatio 731234 (Feb 2019)
Complete Calculation il; p Dominion Energy CM-AA-CLC-301 ATTACHMENT 7 Page 2 of 6 Calculation# CEM-0232 Rev.Q Add. N/A Table of Contents
- 1. Record of Revisions and Addenda ...................................................................................................... 2
- 2. Cumulative Effects Review (required for Revisions and Addenda) ...................................................... 2
- 3. References ........................................................................................................................................ 2
- 4. Computer Codes Used ....................................................................................................................... 2
- 5. Identification of Computer Inputs and Outputs .................................................................................. 2
- 6. Purpose ............................................................................................................................................ 2
- 7. Background ....................................................................................................................................... 3
- 8. Design Inputs .................................................................................................................................... 3
- 9. Assumptions ..................................................................................................................................... 3
- 10. Methodology .................................................................................................................................... 3
- 11. Calculations ...................................................................................................................................... 4
- 12. Conclusions ....................................................................................................................................... 4
- 13. Precautions and Limitations .............................................................................................................. 5
- 14. Calculation Review Checklist ............................................................................................................. 5
- 15. Attachments ..................................................................................................................................... 5
- 1. Record of Revisions and Addenda Initial issue
- 2. Cumulative Effects Review (required for Revisions and Addenda)
NIA
- 3. References
[1] Cah;ulation CEM-0049, Revision 0, Add. 00A, "Evaluation of Socket Weld to Valve 2-RH-33 with Through Weld Leak for As-Found Flaw Characterization" [2] Calculation CEM-0231, Revision 0, "Evaluation of Line 1" -SHP--601 off 4"-SHP-127-601 for Leak Seal Enclosure Device" [3] Condition Report CR1136592, "Through-wall leak identified upstream of 2-MS-377" [4] Drawing 11548-FM-064, Sheet 3 of 6, Revision 58 [5] Formulas for Stress and Strain, 5th Edition, Roark and Young
- 4. Computer Codes Used None
- 5. Identification of Computer Inputs and Outputs NIA
- 6. Purpose The purpose of this calculation is to evaluate the as-found weld flaw on the 1" SHP bypass line off Line 4" SHP-127-60 as reported in Condition Report CR1136592 [3] in order to provide additional justification for the Initial Operability Determination (IOD) and to support the Prompt Operability Determination (POD). The subject 1" line is labeled as 1"-SHP--601 on 11548-FM-064A, Sheet 3 [4].
731234 (Feb 2019)
Complete Calculation iJ';; Dominion Energy CM-AA-CLC-301 ATTACHMENT 7 Page 3 of 6 Calculation# CEM-0232 Rev.Q Add. N/A
- 7. Background Condition Report CR1136592 [3] identifies through wall leakage at a socket weld on the 1" diameter steam supply bypass line (labeled as 1"-SHP--601 on 11548-FM-064A, Sheet 3 [4]).
The following flaw characterization was provided by Surry Power Station and is documented in the 1OD attached to Condition Report CR1136592 [3]: CR 1*136545 documented a rrieasurec! 6dpm reak was found dripping from trre 1nsuLat1on Just upstream of 2--Ms... 3r7 {SG 1 c
/.\FW Pump Stearn Supply Bypass). The ieak target was 1-FVV-MOV-1608 {AFW Crosstie !solation to Unit 1). NOE and System Engineering were tasked to mvestigate a potential through-wail isak on 1" main steam pipir:g upstrearn of 2-MS-:3Tl Unexplained water vvas identified in the generai area and insulation was removed ,£\ very small through. -wali leak (characterized as a pinhoie) was confirmed using a mirror and based on the sound of the leak. it is verv diffic:uit to see steam exiting the pinhole The location appears to be at the fitting side v-1eld toe at approximately -1:00 when l01king upstream The weld is a socket weld and is at a 90-degree fitting located two elbov.rs upstream of 2-MS-377. This piping is shown on drawinr; 1 i 548-CBM-064A-5 Sheet 3 of 6 and is located in the fvfain Steam Vaive House 27' elevation approximately 12 feet off the floor. lt is a i" !ine that bypasses valve 2-MS-158. This 1 iine ls ASME Class 2 piping. To summarize the fiaw characterization, the flaw* is located at or very near the fitting side weld toe at approximate1y 1 :00 when looking upstrean,, is very small pinhole (1132" or less) and is likely caused by a fabrication welding defect An additional engineering wa!kdown confirmed no apparent leakage on the sister A and 8 trains. Minor iow frequency movement of the 1" bypass line was observed.
The as-found weld flaw in the affected socket weld of the 1" SHP line is conservatively evaluated compared to the characterized degradation and demonstrated herein to remain structurally adequate for pressure thrust forces corresponding to the design pressure and for design basis loading conditions. The results of this evaluation demonstrate that the degraded socket weld connection will maintain structural integrity. Note that a leak seal enclosure (clamping device) will be installed to secure the leak until repairs of the line can be made. Calculation CEM-0231 [2] evaluates the adequacy of the piping for the proposed enclosure and also provides stresses, forces, and moments for the existing piping for purposes of this evaluation.
- 8. Design Inputs
- NUPIPE-11 computer pipe stress analysis results from Calculation CEM-0231 [2] for the nominal piping configuration. (This line was previously decoupled from the stress analysis of the 4" line and, hence, a design basis run needed to be developed.)
- Flaw characterization per [3].
- 9. Assumptions
- It is assumed that there is no active degradation mechanism for the subject flaw in the weld. This is supported by the characterization statement provided which indicates that the likely cause is a lack of fusion in the weld at the time of installation. Field reports also indicate that this line is not subject to excessive vibrations at power. Until installation of the leak seal device, measures are currently in place to monitor the leak to ensure that the identified pin hole leak remains stable.
- For purposes of this evaluation, the degradation is postulated to be at the 12 o'clock location; whereas, based on the characterization, the pin hole is actually located at the 1 o'clock location. The use of the larger size flaw of1/2" adequately compensates for this inconsistency as the actual flaw is enveloped within the postulated degradation.
- 10. Methodology The indication in the socket weld is characterized as less than a 1/32" pin hole at the toe of the weld on the fitting side at the 1 o'clock position. For conservatism, a degraded cross section is considered that accounts for a much larger pin hole by assuming a flaw size of1/4". Properties of this conservatively postulated 731234 (Feb 2019)
i';;, Dominion Complete Calculation p Energy CM-AA-CLC-301 ATTACHMENT 7 Page 4 of 6 Calculation# CEM-0232 Rev.Q Add. N/A degraded cross section are estimated and the shift in neutral axis, reduction in weld area, and change in section modulus are accounted for to increase loads and therefore stresses in the weld. The method used is consistent with the methodology outlined in Calculation CEM-0049, Revision 0, Addendum 00A [1]. Use of this method is appropriate based on the similarity between flaws. Application of the method in this calculation is verified by independent review.
- 11. Calculations Review of Nominal Socket Weld for Pressure Thrust plus Applied Mechanical Loads Stresses in the un-degraded weld are calculated in Attachment A. The minimum factor of safety for the nominal (i.e., un-degraded) weld is 3.11 based on allowable shear stress in the pipe. This demonstrates significant reserve strength in the existing socket weld to accommodate substantial degradation.
Review of Degraded Socket Weld for Pressure Thrust plus Applied Mechanical Loads As is shown in Attachment B, the moment of inertia for a degraded cross section considering a through weld leak 1/2" in size (diameter) is 78.5% of nominal. (Note that per [3], the maximum diameter of the flaw is reported to be only 1/32"; whereas for purposes of this evaluation a diameter of1/2" is conservatively postulated in order to assure a bounding configuration.) In addition, there is a shift in the neutral axis which applies additional bending stress due to the axial force. The recalculated bending stress for the reduction in section modulus also includes an additional stress intensification of 2.0 for the pinhole. Also in Attachment B, the metal area is reported to be reduced approximately to 90% of nominal due to consideration of a 1/2" diameter through-weld indication. The stresses as calculated in Attachment A for the un-degraded configuration, the multipliers accounting for the effect of the degradation, and the resulting stresses in the degraded configuration are given in the table below. Nominal Socket Weld Stress Multi lier De raded Socket Weld 2,032 1.111 2,258 694 See Attachment B 2,750 Combined Stress [psi] 2,725 5,008 Allowable Combined Stress 15,000 15,000 [psi Maximum Shear Stress [psi] 3,854 Allowable Shear Stress [psi] 12,000 12,000 ** Factor of Safet 3.11 1.69
** Allowable stress could be increased for purposes of an operability evaluation.
- 12. Conclusions This calculation has conservatively demonstrated that the nominal socket weld configuration (i.e., un degraded) has a Factor of Safety of over 3 for all design loads including pressure thrust, using design allowables. The degraded configuration has been very conservatively modeled using a bounding flaw size of 1/2" and it is shown that reduced factors of safety remain greater than unity for design allowables. No credit is taken in this analysis for increases ih allowables that could be used corresponding to operability evaluations, as allowed per NRC Inspection Manual Guidance, Chapter IMC-0326. Therefore, it is concluded that the as found socket weld will maintain structural integrity for design basis loads including seismic and pressure thrust forces.
731234 (Feb 2019)
Dominion Complete Calculation Energy
- iii" CM-AA-CLC-301 ATTACHMENT 7 Page 5 of 6 Calculation# CEM-0232 Rev.Q Add. N/A
- 13. Precautions and Limitations The flaw size postulated in this analysis is conservative compared to the characterized flaw as reported in the Condition Report [3] for purposes of assuring a bounding analysis.
This analysis presumes no active degradation mechanisms exist and that the flaw is stable.
- 14. Calculation Review Checklist See next page.
- 15. Attachments A. Review of Existing Un-Degraded Weld for Pressure Thrust Plus Applied Mechanical Loads (2 pages)
B. Calculation of Properties for the Degraded Socket Weld (3 pages) 731234 (Feb 2019)
Dominion Complete Calculation
,:;# energy*
CM-AA-CLC-301 ATTACHMENT 7 Page 6 of 6 Calculation# CEM-0232 Rev.Q Add. N/A NOTE: If "Yes" is not answered, an explanation may be provided below. Reference may be made to explanations contained in the calculation or addendum. :
*. : :;:, - . . ;_::'.}\,:\?/*./'.\{;_:'.i:/(::.=* \tt/;/_\/"'!;, :;,- *:'* **. :;. :*"'>.'..-.'.*;:\._;:};-..>-;'./?:'_*:, .:;*: *,.-.--:.-,;-::. :*:c- *,:*;_ ,;:,: ;*_:t* ::\ - .::--- :.: ,;;_"'*:*::i'* .. *:,. - :-
* ::,;Nl}i
.. *" . _ : : / , .. *..
- 1. Have the sources of design inputs been correctly selected and referenced in the calculation? [X] [ ]
- 2. Are the sources of design inputs up-to-date and retrievable/attached to the calculation? [X] [ ]
- 3. Where appropriate, have the other disciplines reviewed or provided the design inputs for which they are responsible? [X] [ ]
- 4. Have design inputs been confirmed by analysis, test, measurement, field walkdown, or other pertinent means as appropriate for the configuration analyzed? [X] [ ]
- 5. Have the bases for assumptions been adequately and clearly presented and are they bounded by the Station Design Basis? [X] [ ]
- 6. Were appropriate calculation/analytic methods used and are outputs reasonable when compared to inputs? [X] [ ]
- 7. Are computations technically accurate? [X] [ ]
- 8. Has the calculation made appropriate allowances for instrument errors and calibration equipment errors? [ ] [X]
- 9. Have those computer codes used in the analysis been referenced in the calculation? [ ] [X]
- 10. Have all exceptions to station design basis criteria and regulatory requirements been identified and justified in accordance with NQA-1-1994? [ ] [X]
- 11. Has the design authority/original preparer for this calculation been informed of its revision or addendum, if required? [ ] [X]
- 12. Was the pre-job brief completed without any identified HU error precursors/compensating actions?
(If HU error precursors/compensating actions were identified, then mark N/A and provide [X] [ ] explanation/summary below or attach pre-job brief form to calculation.) Comments: (Attach additional pages if needed) Signature: Date: 1 ( Lb Lt q (Reviewer) Signature: N/A Date: (Owner's Review, if applicable) Note: Physical or electronic signatures are acceptable. 731234 (Feb 2019)
Calculation CEM-0232, Revision O Attachment A Page 1 of 2 Review of Existing Socket Weld for Pressure Thrust Plus Applied Mechanical Loads Pipe Tnickness, t := 0.179in Schedule 808, Class 601 Design Pressure"' P := 1085psi Inside Diameter ofFitt:ing, fitting := Ll3in (minimum) Design Teu1perature, T := 570 degrees Pipe Outside Diameter, D0 := 1Jl5in
\Veld Size, w := OJ95in
'1
.rt"-c\ fitting""-_ p Forc.e due to Pressu:reThrust, Fp := = 1)07.38-lbf
-4 A.xial Forc.e for Design Basis Loading {Deadweight + Seismic}, F ax := 2lbf + 101bf ref. CEl"'vi-0231 Metal Area based on Pipe Wall, 1\-tipe := t-7r-c\_fitt:ing = OJ5-in *
""' Note: di_:!itti:r,g is MetalA..reabased on Weld Size MA,.veld := \V*7r-c\_fitt:ing = 0.81-in conservatively used here Fp + Fax
,\ **;*-
..i1J.. 1 s.tress 1:t1. ,:,:T Y,'eld* ., a-a.rial := --- = 21\"*1 .vj .*J:s *ps1. M...:\ Iviaxi:mum Resultant Bending Moment for Desi_gn Basis Loading (Faulted), ref. CEt\1-0231 (Faulted Condition} hi1i- := (15.3in-1bf) 2 2
+ (69in-1bf) = 167.84-in-lbf O.o982-[(* D0 + 2-wr' - {D )
1
' 0*
Section Modulus fonveld, Z := = 0.3145-in D 0 + 2-w l.31\*1i-1\*iaximum Resultant Stress due to Bending,. ab:= -- = 69.3.76-psi z Note: Includes an SIF of 1.3 fo1*the socket \Veld. 731234 (Feb 2019)
Calculation CEM-0232, Revision O Attachment A Page 2 of 2 Review of Existing Socket Weld for Pressure Thrust Plus Applied Mechanical Loads Iviax:im.ll:111 Total Combinedi..xial Stress in the \Veld: a- := eraxial + ab = 2725.2-psi Maxfrnum Shea.:rStress in "Vleld at 4.S: 1.J := cr-{2.. = 385-4.1-psi For the subject piping at 570 deg,F (Design Temperature), Sh := 15000psi Per B3L1, Shear stresses in the pipe are limited to s./o of allowable stress, .:\llO\V := o.ssh = 12000-psi
. .. A.110\V Safety Factor usmg Code .allm,v.able stress = FS := -- = 3.H
'Ll 731234 (Feb 2019)
Calculation CEM-0232, Revision O Attachment B Page 1 of 3 Calculation of Properties for the Degraded Socket Weld 19-* t = -- = 0...
. I\ . )ll1 V.
l * . s.*111
.'J* . '\Veld Thickness Based on Corporate \Veld !vianual
. {i Outside Diau1eter - '\Veld D0 := L315rn. + 2-t = L591-rn.
Do . -. Outside Radius - '\Veld Ro:= - = 0.?9)*111 2 Inside Radius - '\leld
. := Ro - t = 0.65 8-rn.
1\1.oment of Inertia of a Sedor of a Hollow Cirde (Refere:nce 10) t = 0.138-rn. Thickness oflviissrn.g Section (Through '\:Veld} D0 = 1.591-rn. Outside Diameter Ro= 0.795-rn. Outside Radius Ri = 0.658-rn. Inside Radius
-111 l 2 Half-.1\.ngle of Se<::tor ct:= - -- = 18.009-de.-g 2 D0 2
2 Actual measure pinhole = 1/32" Conservatively, consider 1/2 2 731234 (Feb 2019)
Calculation CEM-0232, Revision O Attachment B Page 2 of 3 Calculation of Properties for the Degraded Socket Weld jI .l - H t l" . . 2*(sin(a:)}"" A:= +- ""! - - c.\:**+ sm(o}c.os(o.)-
"" : .. ... . a: '""]
\ .t.Ro Ro""! 4R/. .
/' "' ) [
B := l(sin(c}l
. (
3*Ro2 *cq 2-- t l t'\I
.f'i _ __!_ __ t_
Ro 6-Ro 2 _j*
. 2* .
\. Ro) \.
.L,.._ ,,.
t C:=1--+----
.. .)
J-t t 2 3
- R.o R} 4Ro D := 0:- sin(a:)-c.os(0:)
3 . 4 I1_SEC. := Ro *t-(A + B) = 0.0001-lll Moment of Inertia about 1-1 for I\..fissing Section I2._SEC. := Ro3 *t-C-D = 0.00108-lll . 4 Moment of Inertia about 2-2 for I\&issing Section Apply Paralleliu::is Theorem: { 2-sin(a} ') ( t 1 \ * . . .. Yia := Ro* 1- j . J *. 1 - -- + --- * = 0.079-lll
- 1. **
Ro 2-- [ [
\. j-Q t
-- R.oj d : =
Ro- Yis = 0.717-in Area:= cx*t*(2*Ro- t) = .06297-0 in *
"I Location .of Neutralaxis (i.e. distance benveen the parallel ID::is):
Outside diameter .f o \Veld D0 = L591-in Inside diameter of . \Veld 7!:( l 2 .. 2 Ivfotal .Area .of the \veld i\.reas := --1 D0 Di } 0.629-lll 4 \.
- =
.i\.rea-d Distance of neutral axis . :.= = .
0 8 0 -in
.i\.reas - .i\.rea Moment of Inertia of mis sing section about the neutral axis 731234 (Feb 2019)
Calculation CEM-0232, Revision O Attachment B Page 3 of 3 Calculation of Properties for the Degraded Socket Weld M.om.en.t of Inertia. of Composite Sedi.o.n Moment of Inertia -of the Composite section a.bout the neutral ID:is = 1/4_n 4 ln_n = 0.132-in I1 n Bending Stress Incre.aseFactor = F.ac.torfa_g := - = 1.27 T
"1li_n FromAtt.achtnenL.i\, the Total AxialForce is, F..,. := 1507.381bf + l21bf = 1519.38-lbf Additional bending moment due to shift in N.A. = Ma<!d := Fax* 6 = 121.057-in-lbf FromAtt.achtnenLA.., the resultant moment is I\r :.= 16&in-lbf 3
A.lso in Attachment A, the section modulus used \Vas Z := 0.3145in Reduced Section Modulus for Degradation - z,.;o><led :- z. ;-* - 0.247 *in3 l_:11 Therefore., the maximum bending stress fo:rthe degraded \veld is rec.acul.ated .as: U-?vi,. + Ma4:S Ub aea;raded := 2.0----- = 2750.256-psi zde Note:. An SIF -of 2 was applied for the pinhole. C akulation of Reduced 'fetal Area
')
Non-Degraded l\*ietalAre.a = A.re.as = 0.629-in-
"'I Reduced IvfotalAre.a = rvLedoced := A.re.as - .1\.re.a = 0.566-in *
.3/4eas
.kcial Stress Incre.aseFactor = F.actorax,12,1 := . = 1.111 n,1A1'ed'll>;. 731234 (Feb 2019)}}