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ASME Section XI Inservice Inspection Program Proposed Alternative Request S2-15-ISI-05 to Use a Mechanical Clamping Device for a One-Inch Main Steam Line Pipe Repair
	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)
	v • d • e

{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 27, 2019 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 ASME SECTION XI INSERVICE INSPECTION PROGRAM 10 CFR 50.55a Serial No.: 19-483 NRA/GDM: RO Docket No.: 50-281 License No.: DPR-37 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

Attachment Serial No. 19-483 Docket No. 50-281 Attachment, Page 1 of 8 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:

Component Number:

== Description:==

Reference:

ASME Class 2 Piping 1-inch SH P-601 off 4-inch SH P-127-601 1-inch Main Steam Piping Upstream of Valve 2-MS-377 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). Plant 10-Year ASME Section XI Interval Interval ISi Interval Edition/ Addenda Start Date End Date Surry Unit 2 5th 2004 Edition/ No May 10, 2014 May 9, 2024 Addenda [Ref.11

3. Applicable Code Requirements

Serial No. 19-483 Docket No. 50-281 Attachment, Page 3 of 8 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 1 0 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-31 00(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).

8. References Serial No. 19-483 Docket No. 50-281 Attachment, Page 8 of 8

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 CR 1136592," dated 11/26/19.

ISi CLASSIFICATION BOUNDARY DRAWING Virginia Electric and Power Company (Dominion Energy Virginia) Surry Power Station Unit 2 Serial No. 19-483 Docket No. 50-281

2-RC E-lC STEAM GENERATOR <ISi CLASS 2A SECONDARY SIDE> 2-MS-FE 0 ISi Classification Boundary Drawing 2-PEN PN-74 w 0: w I a.. U) 0 0 w 0: w I a.. U) 0 0 ONE CAP TO BE SHIPPED LOOSE FOR FIELD WELO!NG PRIOR TO CHEMICAL CLEANING. w 0: w I a.. U) 0 0.... w 0: w I a.. U) 0 0

WALL OF REACTOR CONTAINMENT-----

Steam supply to TDAFW pump Approximate Location of leak N U) U) 0 Serial No. 19-483 Docket No. 50-281, page 1 of 1 6"-SAE-103-121 5' X 6' RED. 2-MS-PT !SI CLASS 2 NON CLASSED 2-MS-PT I 2-MS TD-8 VCS-60A.-- cropped from Drawing No: 11548-CBM-064A-5 Serial No. 19-483 Docket No. 50-281 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 Customer: DOMINION SURRY Safety Review#: 4211975DS Engr Order#: 4211975 REV 1 Name: Signature: Date: Time: Data Taken By: //J;J/ 11/23/2019 1245 Designed By: -;,/_---/ 11/23/2019 1530 /,:, ,..,z.r-11/24/2019 1600 Verified By: 11/23/2019 1830 ...,.,.,--'___,, 11/23/2019 2359 .v; / ,*r,. _,. '-f::,::l'/f 11/24/2019 1945 Shop Received By: 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 29 STICKS Do Not Paint: Sealant: Seal Type: CRUNCH TEETH Revision Note: ADDED Equipment Number: 2-MS-377 QC FINAL INSPECTION REQUIRED Rev. 3/3/2010 STRONGBACKSFOR SEPARATION Nuclear - Safety Related MTRs and COCs Required PMI Required Nuclear - Safety Related .,tL:-U t-1 fo E1wyth'ft1_r: He Do I

TEAM Sheet 1 of 1 egistration # F-003143 MATERIAL SPECIFICATIONS D Non-Critical/Nuclear 4 Critical/Nuclear Drawn By: KC/UMW Checked By: UMW/GVD/KC Date: 11 /24/19 Date: 11 /24/19 Engineering Order No.: 4211975 REV 1 Enclosures Material Specification MTR PIPE FITTING ROLLED PLATE BLOCK / PLATE / SIDEBARS SA 516 GR 70 X ENDPLATES STRONGBACK BARS SA 516 GR 70 X S.B. EARS/FINGERS Fasteners STUDS ENCLOSURE SA 193 GR 87 X STUDS STRONGBACK SA 193 GR 87 X NUTS ENCLOSURE SA 194 GR 2H X NUTS STRONGBACK SA 194 GR 2H X SET SCREWS Misc. uirements Ut-T '\\ f-<.1._...*...... -1 \\\\ 1----------------------+-----*,.**** - ***...., 1----------------------+-----/.:...................... 0.*.1

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TEAM GIVEN BY: CHKD. BY: LINE SIZE: 1" TYPE SEAL: [3J VOID FILL PERIMETER SEAL DIMENSIONAL DATA LTR. DIM. A1 17" 81 1" C1 1.315 01 1.315 E1 1.300 F1 1.865 G1 .560 W1 .350 A2 17" 82 1" C2 1.315 02 1.315 E2 .900 F2 1.865 G2 .400 W2 .350 H1 1" H2 1" J1 2" J2 1" K1 3" K2 1" L .130 Engineering Procedure Supplement Corporate FORM 901.DS124 Rev: 3 Page 1 of 1 90° Ell SCREWED/SOCKET FITTING DATE: I 11/23/19 PLANT: I Surry I UNIT: 12 DATE: I 11/23/19 SURFACE CONDITION: I Good SEVERITY OF LEAK: 1ON 10 I SHIP TO: I 5570 Hog Island Rd. Surry, Va. [3J CRUNCH PACKING SKIN TEMP. TONGUE TUBING LINE: 570 FLG. [3J OTHER: !PEENING LIPS L-E2 W2 I Fl Al (MTAO) --Bl (BPTC) 1 WI I I .__Cl--. Dl / J--// ,/ - ,_L Kl (MTAO) = MEASURE TO ANY OBSTRUCTION (BPTC) = BEST PLACE TO CLOSE ON i I --- C2 D2 / - K2 --i - L/ L_J FOR DIMS Hl,H2 & JU2 & Kl,K2 PLACE SQUARE AGAINST END Of WELD/THREADS AS SHOWN OBSTRUCTIONS (Looking into C 1 /D 1) NOTE: 3/8" UNC INJECTION PORTS REQUIRED IF SQUARE CANNOT BE REPLACED AS SHOWN - "HI" & "H2" STILL MUST BE TAKEN AT WELDS/THREADS LOCATION OF BLOW: 12 THREADED WELDED ASSUME SCH. 40/80 FOR CALCULATION SEISMIC; KEEP WEIGHT DOWN TO A MINIMUM

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" Clamp

Summary of Calculations Rectangular Plate Stress Calculations Cover Plate Maxu= 14453.93 psi Design Margin = 1.35 Longer Side Wall (Worst Case) .Alax0=5215.& psi Design Margin = 3.75 Shorter Side Wall (Worst Case) Sall.ow=: 19580 psi Sallow= 19580 psi Maxu= 12327.38-psi Design Margin = 1.59 Sallow 19 580 psi 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* 103 psi Spqie-=(1.71 d04 ) 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 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

Complete Calculation fJi; Dominion 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 CEM-0231 0 N/A 000 Record? 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 I Addendum

Title:

N/A Station(s) and Unit(s): NAO 1 02 0 ISFSI SU O 1 l2 ISFSI MP O 1 02 03 0 ISFSI 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 (1l l3l Reviewer (Qual. Required): Printed Name (1J Approver: Printed Name Note: Physical or electronic signatures are acceptable. Type of Review: (2J Independent Sig Signature: Signature: {J - I Date: (1l (3l JFJ& _., 11 Date: I 1-Z - J9 Date: 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 ,;,# Energy* Complete Calculation CM-AA-CLC-301 ATT AC HM ENT 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-131 C1 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)

f;, Dominion

iii" Energy(!

Complete Calculation 5. Identification of Computer Inputs and Outputs NUPIPE 119025464 (Reference3. 7) NUPIPE 119121703 (Reference3. 7) NUPIPE 19263425 (Reference3. 7) 119501858 NUPIPE (Reference3. 7) NUPIPE j 20404614 (Reference3. 7) I 25-Nov-2019I Corr_Seismic.inp I 25-Nov-2019I Corr_DW.inp 25-Nov-2019 DW_ Seismic.inp I25_Nov-2019I DW_Seismic_ 1Line. mp j 25_Nov-20191 DW Seismic_ 1Line_ Box.mp I Corr_Seismic.out I Corr_DW.out DW_Seismic.out CM-AA-CLC-301 ATTACHMENT 7 Page 4 of 11 Calculation # CEM-0231 Rev. 0 Correlation Run 1 - Correlation to CE-0581 Run AAAEPEM I Dated 7-29-86 (Seismic Pipe Stress Run, Tload =17) See Attachment I Correlation Run 2 - Correlation to CE-0581 Run AAAEDCB I 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 `eadweigat, Thermal, Seismic Pipe Stress Analysis (Tload = 3) of piping in correlation runs See Index 4 for the input and output files. Study Run 2 - Results for use in Calculation CEM-0232 (Reference 3.9) I DW_Seismic_1Line. out I Dea.dweight, Thbrmal, Seismic Pipe Stress Analysis (Tload = 3) with add1t1on of the 1' Bypass line off of 4"-SHP-127-601 See Attachment H Study Run 3 -To determine if support is required. I DW_Seismic_ 1 Line_ 1 Dea_dweight, Thermal, Seismic Pipe Stress Analysis (Tload = 3) with Box.out add1t1on of the 1" Bypass line off of 4"-SHP-127-601 and a seal enclosure device See Index 4 for the input and output files. 731234 (Feb 2019)

r.- Dominion

.;iii"' Energy0 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 j 20385315 I 25_Nov-2019 I DW_Seisr:nic_1Line_ I DW_Seismic_1Line_ 1 Deadweight, Thermal, Seismic Pipe Stress Analysis (Tload = 3) with (Reference3. 7) Box_Sup.inp Box_Sup.out addition of the 1" Bypass line off of 4"-SHP-127-601, seal enclosure device, and new support on 1" bypass line See Attachment G Study Run 5 -Sensitivity Run for Insulation NUPIPE 18153800 26-Nov-2019 DW_Seismic_ 1Line - DW_Seismic_ 1 Line_ Uses Study Run 4 with a change to the weight per foot for the 1" Bypass (Reference3. 7) Box_Sup_lns.inp Box_Sup_lns.out line as described in Assumptions/Comments Section. See Index 4 for the input and output files. Study Run 6 -Sensitivity Run for Insulation NUPIPE 111423936 I 26_Nov-2019 I DWPSeismic_1Line_ I DW_Seismic_ 1 Line_ Uses Study Run 2 with a change to the weight per foot for the 1" Bypass (Reference3. 7) lns.1np Ins.out line as described in Assumptions/Comments Section. See Index 4 for the input and output files. 731234 (Feb 2019)

f£': o.. om. inion p Energy(g

===6. Background=== Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Page 6 of 11 Calculation # CEM-0231 Rev. 0 Condition Report CR 1136592 (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 CR 1136592: 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 i 548-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 NU PIPE 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 NU PIPE 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)

Dominion j# Energy* 7. Design Inputs Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Page 7 of 11 Calculation # CEM-0231 Rev. 0 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 NU PIPE 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 Data log (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)

9. Methodology Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Page 8 of 11 Calculation # CEM-0231 Rev. 0 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)

f,$ D. om***.inion p Energy Complete Calculation 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)

(3) (4) (5) (2) (3) (4) 400 260 100 100 2,830 + 3,311 = 6,141 2,830 + 13,232 = 16,062 2,376 + 19363 = 21,739 24,244 2,376 + 2,778 + 24,244 = 29,398 15,000 18,000 27,000 22,500

37,500 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 NU PIPE Input File: DW_Seismic_ 1 Line_Box_Sup.inp NUPIPE Run ID: 20385315 NUPIPE Run Date: 25-Nov-2019 PQJnt(s) 6000 6010 6000 6110 psi) 2,830 + 2,780 = 5,610 1,222 + 13,529 = 14,751 2,830 + 16155 = 18,985 7,669 15,000 18,000 27,000 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)

Dominion 'I)# Energy" Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Page 10 of 11 (1) (2) (3) (4) 12.4 Review of the Pipe Support Loads Calculation # CEM-0231 Rev. 0 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) 1335 2,830 + 1,602 = 4,432 15,000 S1p + (Sdl + Sobei

B + Sobea) < 1.2Sh 1335 2,830 + 6,883 = 9,713 18,000 1335 2,830 + 9253 = 12,083 27,000 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; Dom. in.ion p, 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 p Energy Complete Calculation 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. ':;:g'ijti.ftt5!-=

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,.,.. '>,\\'t' :< :,::e:.,.,:,*,:.,:.. :;

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.:f,;,- ii..,..,,,.:. '*'"',:;);::;.'F'>':\\,!"i(ti'::'-:,:-::':'.;::*.:"',:,. /-':!/'a'-::,_, ... f,-,;:s,1,. '/'.. ' :;1 :.. n,::.;:: 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] [ ] I i I 10. Have all exceptions to station design basis criteria and regulatory requirements been identified [ X l I and justified in accordance with NQA-1-1994? [ ] 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)

!"9:; Dominion p Energym Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 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)

i1' Dominion p, Energy Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. O Page 82 of 83 731234 (Feb 2019)

fJ$ Dominion Energy Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. O Attachment B Page 83 of 83 731234 (Feb 2019)

Attachment C - Math Models Complete Calculation CM-AA-CLC-301 ATTACHMENT 7 Calculation # CEM-0231 Rev. 0 Attachment C Page C1 of C3 Note the following Math Models shown on Pages C1 and C2 are from CE-0581 Rev. O

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. .l*,1:-1'1\\$*1'1. J'1'f.ffl'r ir:-.. UN11" - 'lft-111 ---. 3 (, <Cl'i*c'.l: ,s -bl, f'1'n- .-*i-<<.. ,:t,.,,14'4"1,l"\\ ----

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f=- Dom.in i*on p Energy(9 Complete Calculation 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. - 1"-SHP- -601 2-MS-158 Location of the Seal Enclosure Device 160301 II I'/.t ocation I !604ol I L Naw 1upport !60701 2-MS-377,. 2 ,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 SURRY POWER STATION SUPPORT NO. RUN ID. 20385315 RUN DATE 11/25/19 LINE NO. PROB NO. STRESS POINT NO. [ 5 SUPPORT TYPE: [ COL 1 2 3 4 5 6 7 8 9 10 0 C C LOAD TYPE LARGEST POSITIVE LARGEST NEGATIVE EARTHQUAKE OBEI + OBEA (+ OR -) EARTHQUAKE DBE (NOTEl) (+ OR -) DEADLOAD T (+)NORMAL H Fx (lb) 0 0 115 209 31 0 M (-)NORMAL -227 DESIGN + 146 LOADl DESIGN LOAD2 DESIGN LOAD3 - 311 + 31 - 196 + 240 - 178 (Fx) Fy (lb) 0 0 118 140 228 0 -320 + 346 - 210 + 228 - 92 + 368 - 0 (Fy) Fz (lb) 0 0 83 153 51 279 0 + 413 - 32 + 330 - 0 + 204 - 102 (Fz) Mx (in-lb) 0 0 286 295 -949 0 -5389 + 0 - 6624 + 0 - 6338 + 0 - 1244 My (in-lb) 0 0 1136 2066 762 2064 0 + 3962 - 374 + 2826 - 0 + 2828 - 1304 Mz (in-lb) 0 0 1680 1962 1506 11260 0 + 14446 - 174 + 12766 - 0 + 3468 - 456 11 THERMAL MVMTS (Global-in.) + 0 .058 +.036 0 +.045 - 0 (Positive) (Negative) +Fx = East DESIGN LOAD 1 DESIGN LOAD 2 DESIGN LOAD 3 DL + THERMAL + SRSS[(OBEI+OBEA),OCCASIONAL] DL + THERMAL DL + DBE +Fx = East : +Fy = Vertical (UP) : +Fz = South NOTES: +Fy Vertical (up) +Fz = South

1) DBEA MUST BE INCLUDED WITH DBEI WHEN N411 CURVES ARE USED

2) REFER TO STD-CEN-0023