Text

Alternative Request IR-4-03 for Use of an Alternative Non-Code Methodology to Demonstrate Structural Integrity of Class 3 Moderate-Energy Piping
	ML20076A549
Person / Time
Site:	Millstone
Issue date:	03/14/2020
From:	Mark D. Sartain; Dominion Energy Nuclear Connecticut
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	20-103
	Download: ML20076A549 (41)
	v • d • e

Dominion Energy Nuclear Connecticut, Inc.

~ Dominion 5000 Dominion Boulevard, Glen Allen, VA 23060 DominionEnergy.com March 14, 2020 =--' Energy U.S. Nuclear Regulatory Commission Serial No.20-103 Attention: Document Control Desk NLOS/MLC RO Washington, DC 20555 Docket No . 50-423 License No . NPF-49 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 ALTERNATIVE REQUEST IR-4-03 FOR USE OF AN ALTERNATIVE NON-CODE METHODOLOGY TO DEMONSTRATE STRUCTURAL INTEGRITY OF CLASS 3 MODERATE-ENERGY PIPING Pursuant to 10 CFR 50.55a(z)(2) , Dominion Energy Nuclear Connecticut, Inc. (DENC) requests Nuclear Regulatory Commission (NRC) approval to use a non-code methodology in lieu of a repair allowed by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI , IWA-4000, to address a through -wall leak in a reinforced branch connection of the seNice water system at Millstone Power Station Unit 3 (MPS3). DENC has evaluated the branch connection structural reinforcing pad and the underlying ASME pipe and welds to demonstrate structural integrity of the Class 3 moderate energy service water line, 3-SWP-'19-2-7-3.

NRC 's acceptance of DENC's alternate methodology to establish structural integrity will allow continued operation of the unit until a repair is completed no later than the end of the next scheduled MPS3 refueling outage in the fall 2020.

The basis for this request is provided in Attachment 1. A copy of the structural integrity evaluation for 3-SWP-19-2-7-3 supporting this request is provided in Attachment 2. A schematic of ASME Branch Reinforcement Weld Details is provided in Attachment 3.

DENC is requesting NRC verbal approval of this alternate method for evaluating structural integrity of the through-wall leak condition identified on the MPS3 'A' train

. service water header. Per MPS3 Technical Specification (TS) 3.7.4 , an inoperable service water loop must be restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or the plant must be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Repair of this leak would require a unit shutdown and cooldown to Mode 5 to remove the affected header from service . The unit would need to be maintained in Mode 5 with limited decay heat removal and backup on-site emergency power availability for the duration of the repair.

Therefore, DENC has determined that repairing the leak at this time would represent a hardship without a compensating increase in_the level of quality and safety.

Approval of this alternate method for evaluating structural integrity will allow deferral of the required repair to no later than the end of the fall 2020 MPS3 refueling outage .

Verbal approval is requested by 1113 hours0.0129 days 0.309 hours 0.00184 weeks 4.234965e-4 months on March 17, 2020 to allow the 'A' train of the service water system to be declared OPERABLE and avoid an unplanned unit

Serial No.20-103 Docket No. 50-423 Page 2 of 2 shutdown. The duration of the proposed alternative is requested to be until completion of the next MPS3 refueling outage.

Should you have any questions regarding this submittal, please contact Shayan Sinha at (804) 273-4687.

Sincerely, Mark D. Sartain Vice President Nuclear Engineering & Fleet Support Attachments:

1. Alternative Request IR-4-03, Use of an Alternative Non-Code Methodology to Demonstrate Structural Integrity of Class 3 Moderate-Energy Piping

2. Engineering Technical Evaluation (ETE-MP-2020-1027) Structural Integrity Evaluation of Degraded Service Water Line 3-SWP-19-2-7-3, Service Water Header.

3. Schematic of ASME Branch Reinforcement Weld Details Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman Senior Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 C2 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

Serial No.20-103 Docket No. 50-423 ATTACHMENT 1 ALTERNATIVE REQUEST IR-4-03 USE OF AN ALTERNATIVE NON-CODE METHODOLOGY TO DEMONSTRATE STRUCTURAL INTEGRITY OF CLASS 3 MODERATE-ENERGY PIPING MILLSTONE POWER STATION UNIT 3 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

Serial No.20-103 Docket No. 50-423 Attachment 1, Page 1 of 8 Alternative Request IR-4-03 In Accordance with 10 CFR 50.55a(z)(2)

Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality and Safety

1. ASME Code Component(s) Affected ASME Code Class: 3

References:

American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, IWA-4000.

Components: Moderate-energy (i.e., :5 200°F (93°C) and :5 275 psig (1.9 MPa) maximum operating conditions) Service Water System Piping, line designation 3-SWP-19-2-7-3.

The subject piping segment is carbon steel seam welded pipe with a non-pressure retaining Cu-Ni roll clad interior lining provided for corrosion resistance.

2. Applicable Code Edition and Addenda

The current Code of record for Millstone Power Station Unit 3 (MPS3) is the ASME Section XI, 2013 Edition, no Addenda. MPS3 is in its fourth 10-year inservice inspection (ISi) interval which began on April 23, 2019 and will end on April 22, 2029.

3. Applicable Code Requirements

ASME Section XI, Article IWD-3132, Acceptance

A component whose examination detects relevant conditions described in the standards of Table IWD-3410-1 shall be unacceptable for continued service unless such components meet the requirements of IWD-3132.1, IWD-3132.2, or IWD-3132.3.

ASME Section XI, Article IWD-3132.2, Acceptance by Corrective Measure or Repair/Replacement Activity

A component containing relevant conditions is acceptable for continued service if the relevant conditions are corrected by a repair/replacement activity or by corrective measures to the extent necessary to nieet the acceptance standards of Table IWD-3410-1.

ASME Section XI, Article IWD-3133, Repair/Replacement Activity and Reexamination

Serial No.20-103 Docket No. 50-423 Attachment 1, Page 2 of 8

The repair/replacement activity and reexamination shall comply with the requirements of Article IWA-4000.

ASME Code,Section XI, IWA-4400 of the 2013 Edition provides requirements for welding, brazing, metal removal, and installation of repair/replacement activities.

ASME Section XI, Paragraph IWA-4422, Defect Evaluation and Examination states, a defect is considered removed when it has been reduced to an acceptable size. If the resulting section thickness is less than the minimum required thickness, the component shall be corrected by repair/replacement activities in accordance with this article.

Alternatively, the defect removal area and any remaining portion of the defect may be evaluated, and the component accepted in accordance with the appropriate flaw evaluation provisions of Section XI, or the design provisions of the owner's Requirements and either the Construction Code or Section 111.

4. Reason for Request

On March 11, 2020, water was found dripping from the weep hole in a reinforcing pad (also referred to as a branch reinforcement by the Code or as a saddle plate in Attachment 2) on a 30-inch diameter section of service water (SW) supply piping (i.e., 3-SWP-19-2-7-3) in the 'A' SW train at MPS3. The presence of the reinforcing pad precludes identifying and characterizing the flaw as required by ASME Section XI.

Implementation of the applicable ASME Section XI requirements necessitates removal of the defect through an appropriate repair process. Such a repair would require removing the system from service and performing a major disassembly for access to the flaw. Other alternative repair methods such as local weld overlays are not practicable because of the configuration of the joint and the presence of the reinforcing pad.

Repair of the degraded piping will require significant time for evaluation, design, material procurement, planning, scheduling, and implementation and would necessitate a unit shutdown and removal of the 'A' SW train from service. This would render one train of decay heat removal and one emergency diesel generator inoperable. In cold shutdown, loss of the remaining operable train of decay heat removal would result in an uncontrolled temperature increase and mode change until decay heat removal from the steam generators could be established. During a refueling outage, the repair could be performed with the refueling cavity flooded, providing additional defense-in-depth against a loss of the train of decay heat removal. The proposed alternative method demonstrates that structural integrity is maintained, with margin. Therefore, complying with the requirements of the Code and affecting a repair now will present an undue hardship without a compensating increase in the level of quality and safety of the

Serial No.20-103 Docket No. 50-423 Attachment 1, Page 3 of 8 unit. Until a repair is complete, the leakage will be managed by implementation of compensatory monitoring actions described below.

NRC approval is needed since the methodology used to establish structural integrity has not been previously approved by the NRC. Although the alternate methodology utilizes code equations to assess the capacity of the load path through the branch reinforcement, the Code does not provide a direct means of crediting a fabricated tee for structural design loading without a full penetration weld between the branch and the main pipe run.

5. Proposed Alternative and Basis for Use

Dominion Energy Nuclear Connecticut (DENC) proposes to use an alternative, non-Code methodology to evaluate structural integrity of the affected section of piping. Leakage will be monitored on a daily basis and the leak rate trended. UT examination of the piping and reinforcing pad will be performed monthly (30 days

+/- 25%) and in response to an increase in leakage that indicates further degradation of the underlying flaw.

The affected piping (3-SWP-19-2-7-3) is the common line of the 'A' train of SW located downstream of 3SWP*MOV102A and 3SWP*MOV102C. The affected piping is located in the 'A' SW cubicle in the intake structure.

The leak has the potential to affect the following systems, structures, and components:

'A' train of SW

SW piping spool 3-SWP-19-2-7-3

Safety related heat exchangers cooled by the 'A' train of SW

SW pumps P1A & P1 C hydraulic performance

Intake structure equipment susceptible to spray or flooding damage Leak

Description:

The leak is coming from a weep hole on the upper reinforcing pad which is welded to the intersection of two 30-inch pipes to provide structural support for the piping joint (fabricated tee). The reinforcing pad has a drilled weep hole from which water is being discharged at a rate of about 1 drop every 40 seconds with one 'A' header SW pump running. The rate changes to 1 drop every 20 seconds with both 'A' header SW pumps running (based on field observation). The reinforcing pad is 60 inches long and % inch thick with a 69 % degree arc rolled to a 30-inch inside diameter.

The location and size of the flaw under the reinforcing pad cannot be determined.

Serial No.20-103 Docket No. 50-423 Attachment 1, Page 4 of 8 Structural Integrity:

DENC's structural integrity evaluation is provided in Attachment 2. In summary, the structural integrity load path is from the reinforcing pad fillet weld on the branch piping (immediately downstream of 3SWP*MOV102A) and across the reinforcing pad to the reinforcing pad fillet weld on the run piping (immediately downstream of 3SWP*MOV102C). No credit for structural integrity is taken for the full penetration butt weld, which connects the two 30-inch pipe pieces into a fabricated tee. Based on the low leak rate (1 drop in 40 seconds), and previous large bore SW leaks at MPS3, it is possible that SW penetrated the Cu-Ni clad and epoxy coating on the piping via a pinhole defect, and began to corrode the underlying carbon steel (SA-516) piping resulting in a leak path. Pinhole degradation of the butt weld resulting in a leak path under the reinforcing pad is also a possible cause.

Documentation was reviewed to confirm that the subject p1p1ng spool was fabricated and inspected to the appropriate Code. A review of the inservice conditions of this spool concluded that inservice degradation of the spool components needed for structural integrity is not likely based on the following conditions:

The installed configuration of the piping spool results in primary applied stresses that are below the Code allowable stresses by a factor of approximately 3.

There is substantial margin in the weld capacity (0.215 inch weld required versus 0.500 inch weld nominal).

Thermal and dead load stresses are approximately 50% of the Code allowable stresses. The number of thermal cycles on this spool are low.

Thus, the potential for thermal induced fatigue is low.

The spool is isolated from pump vibrations by an installed strainer and expansion joint, resulting in minimal high cycle fatigue.

Additionally, inspections of the inservice spool were performed to confirm that the condition of the spool will support the continued structural integrity of the spool.

NOE inspections are documented on pages 8 through 17 of Attachment 2 (Note:

inspections were subject to geometric limitations as specified in the NOE reports).

These inspections included:

UT measurements of accessible pipe wall thickness adjacent to the reinforcing pad welds and of accessible areas of the pipe directly under the welds using shear wave UT.

UT measurements of the reinforcing pad thickness adjacent to the reinforcing pad welds and at selected locations across the reinforcing pad.

A visual exam of the reinforcing pad welds.

Serial No.20-103 Docket No. 50-423 Attachment 1, Page 5 of 8 Based on these considerations, there is reasonable expectation that the inservice condition of the reinforcing pad and the piping that can be examined are, and will remain, in a condition to support their intended use for maintaining structural integrity of this piping spool. The confirmed integrity of these components provides a sound load carrying path between the branch and main run of the piping.

Flow Concerns:

The effects on SW system hydraulic performance due to a leak at the junction between pumps 3SWP*P1A and 3SWP*P1 C was evaluated using the PROTO-FLO model of the system (Reference 5). This evaluation assumed a 60 gpm leak rate to bound the capacity of the SW pump cubicle floor drain capacity of 56 gpm documented in an internal flooding calculation (Reference 6). Delivered flows to the various heat exchangers cooled by the SW system during system operation with 60 gpm of leakage out of the header were compared to delivered flows during system operation with no leakage. This was evaluated for the normal and design accident cases (i.e., Cases 1 through 9 of Reference 5). It was determined that the impact on delivered flows due to a 60 gpm leak rate is negligible and will not have an adverse impact on system operation. Minimum required flow rates to all heat exchangers are maintained for the design basis alignments.

These accident configurations are consistent with the system design requirements and conservative to minimize delivered flow to the safety related heat exchangers.

Thus, there are no concerns with adequate flow from the SW system to the safety related heat exchangers with the existing leak or increases in leakage up to 60 gpm.

Spray Concerns:

Spraying adjacent components is not a concern based upon the location of the leak. The leak is through the pipe wall at an unknown location under the reinforcing pad and is thus inherently limited in its flow capacity due to the probable tortuous path to the atmosphere. A daily visual inspection to monitor leakage will be performed. No components susceptible to spray damage are in the immediate vicinity of the leak. With respect to spray from a bounding leak, the nearest electrical target is the conduit and flex conduit for the 4160 VAC line for the 'A' SW Pump. These conduits are rated for spray without damage. With respect to both spray and flooding from a bounding leak, the nearest electrical target is safety related MCC 3EHS*MCC1A5 (32-5T). The MCC stands on a 5-inch high concrete pedestal and is 25 feet away from the leak. Daily checks of the leak will identify a worsening leak well before these targets would be exposed to spray.

Flooding Concerns:

Flooding concerns were evaluated for safety related components within the 'A' SW pump cubicle. Based on the structural integrity evaluation of the leak,

Serial No.20-103 Docket No. 50-423 Attachment 1, Page 6 of 8 catastrophic failure of the pipe or reinforcing pad is considered unlikely.

Compensatory measures as discussed below, have been established to ensure that the capability of existing room flood control systems will not be challenged.

Each SW pump cubicle has two SW pumps with a sump to collect pump seal leak off, which is typically 1-2 gpm. Seal leak off water and water issuing from the weep hole in the reinforcing pad is gravity drained to the intake structure pump bay via a 1-1/2" line under normal conditions.

During hurricane scenarios (or other conditions when high tidal surges are experienced or expected), the normal sump drain lines are isolated by Operators per AOP 3569 (Reference 8) and the 'A' header SW cubicle sump is drained using sump pump 3PBS-P1A. Sump pump will pass approximately 20 gpm at 30 feet of head (PDCR MP3-92-091) which exceeds the maximum acceptable leak rate of 5 gpm and other expected leakage such as pump and strainer seal leakage which is typically 2-3 gpm per pump.

Compensatory Actions:

For the duration for the proposed alternative, DENC will perform the following actions:

Daily observation and recording of leak rate by Operators. Maximum acceptable leak rate is 5 gpm.

Periodically (every 30 days +/- 25%) or upon identification of an increase of 100 drops/min (10 ml/min) over the previous 7 days, UT verification that degradation of the piping base metal adjacent to and under the reinforcement pad fillet weld, and reinforcing pad base metal is within the bounds of the structural integrity determination provided in Attachment 2.

Multiple alarms, including low discharge pressure, and low flow to cooled components, are available to alert operators should a gross failure of the pipe occur. Indication of pressure is also available to the operators both on the main control board as well as the plant process computer. Operators would respond to such a condition as directed by applicable Alarm Response Procedures and Abnormal Operating Procedure AOP 3560, Loss of Service Water (Reference 7).

Serial No.20-103 Docket No. 50-423 Attachment 1, Page 7 of 8 Extent of Condition:

SW piping in the 'A' train SW cubicle was walked down with no signs of exterior piping leakage noted besides the leakage from the weep hole on the upper reinforcing pad.

The weep hole on lower reinforcing pad was verified to have no leakage.

Inspection robotic videos and inspection results from the last two inspections (3R16 - October 2014 and 3R18 - October 2017) were reviewed for the 'A' train SW header in the intake to determine if any piping problems had been identified. No corrosion problems were evident from the video and no corrosion or coating problems were noted on the inspection forms. The previous robotic camera inspections from 3R 17 (April 2016) and 3R 19 (April 2019) of the corresponding spool piece with the 30-inch fabricated tee on the

'B' train of MPS3 SW were also reviewed. No corrosion problems were evident from the video and no corrosion problems or coating problems were noted on the inspection forms.

Conclusion:

Although a regulatory-approved methodology for demonstrating structural integrity is not available for use in this case, structural integrity of the 30-inch fabricated tee on service water line 3-SWP-19-2-7-3 has been demonstrated using an alternate analysis methodology detailed in Attachment 2. The safety function of the 'A' train SW header is unaffected by the identified leakage and the leak rate is within the capabilities of the floor drain system in the 'A' SW pump train cubicle. Therefore, there is no potential adverse impact on neighboring equipment due to either spray or flooding.

Leakage will be monitored on a daily basis and the leak rate trended. UT examination of the piping and reinforcing pad will be performed monthly (30 days

+/- 25%) and in response to an increase in the leakage that indicates further degradation of the underlying flaw.

A Code-compliant repair will be completed no later than the next MPS3 refueling outage, which is scheduled for fall 2020.

6. Duration of Proposed Alternative

The duration of the proposed alternative for SW piping, 3-SWP-19-2-7-3, is requested to be until the end of the fall 2020 refueling outage.

7. Precedents

No precedents were found.

Serial No.20-103 Docket No. 50-423 Attachment 1, Page 8 of 8

8. References

1. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 2013 Edition.

2. American Society of Mechanical Engineers (ASME) Section Ill, 1971 Edition through Winter 1973 Addenda, Class 3.

3. ETE-MP-2020-1027, Structural Integrity Evaluation of MP3 Service Water Spool 3-SWP-19-2-7-3.

4. Operability Determination for CR1142973, as reviewed by FSRC on 3/14/2020.

5. Calculation 96-001, Empirical Adjustment MP3 SW Model to 1995 Flow Test Data and Incorporation of Latest Service Water Design Change Notice

6. Calculation 01-ENG-01884M3, MP3 Service Water Pump Cubicle Internal Flooding Evaluation, Rev 0, CCN 1

7. AOP 3560, Loss of Service Water, Rev 012

8. AOP 3569, Severe Weather Conditions, Rev 026

Serial No.20-103 Docket No. 50-423 ATTACHMENT 2 ENGINEERING TECHNICAL EVALUATION (ETE-MP-2020-1027) STRUCTURAL INTEGRITY EVALUATION OF DEGRADED SERVICE WATER LINE 3-SWP-19-2-7-3, SERVICE WATER HEADER MILLSTONE POWER STATION UNIT 3 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

ETE-MP-2020-1027 Rev. 0 Report Generated on 3/14/2020 9:05:26 PM Page 1 of 27 Engineering Technical Evaluation Cover Sheet and Body CM-AA-ETE-101 Attachment 2 Page 1 of 7

1. Stations: 2. Doc Type: 3. Sub Type: 4. Document Number: 5. Rev.: 6. Add: 7. Decomm?:

181 MP D SU DNA ETE 000 ETE-MP-2020-1027 0 N/A D Yes~ No 8.

Title:

Structural lnte rit Evaluation of MP3 Service Water S ool 3-SWP-19-2-7-3

9. ETE Level: 10. Unit(s): 11. Quality Classification: 12. FSRC Approval: 13. Risk Assessment:

~ Level 1 D Level 2 D Unit 1 D Unit 2 ~ SR D NS D NSQ D Yes ~ No D Low D Medium

~ Unit 3 0 ISFSI D High 0 N/A Prepared by/Affiliation Mechanical Calculations: (Print)

Digitally Signed by ~-

Signature: Date:

03/13/2020 06:04:17 PM Reviewed by/Affiliation IND Mechanical Calculations: (Print)

Digitally Signed by

[gj IND O PEER Signature: Date:

03/13/2020 06:05:21 PM Supervisor Approval/Affiliation Mech/ Electrical: (Print) Signature: Date:

03/13/2020 Digitally Signed by 06:08:41 PM StandariiAttachments Attachment # of Reviewed/No Not Req.

Pa es Im act

15. Design Effects and Considerations D (ON ES-AA-GN-1003)

16. Document Impact Summary (DRUL)

(DNES-AA-GN-1002)

17. Considerations and Conditions for Document Updates (check N/A ~ if no document updates are noted on the DRUL)

D All Document updates noted on the DRUL can be initiated immediately D Document updates noted on the DRUL are delayed until the following documents/actions are completed:

__ (e.g., WO, CR etc.) (See DRUL Remarks section)

of Pa es No.tRe

18. 10CFRS0.59/72.48 applicability review forms (CM-AA-400)

19. 10CFRS0.59/72.48 screen form (CM-AA-400)

20. 10CFRS0.59/72.48 evaluation form (CM-AA-400)

21. Additional.Attachments Attachment # of Pa Attachment 1 10 Attachment 2 2 Attachment 3 2 Alternate Structural Evaluation - Area Reinforcement evaluation Attachment 4 3 Attachment 5 2 Attachment 6 S ool 3-SWP-19-2-7-3 Certificate of Desi n

22. Distribution Form 730801 (Sep 2018)

ETE-MP-2020-1027 Rev. 0 Report Generated on 3/14/2020 9:05:26 PM Page 2 of 27 Engineering Technical Evaluation Cover Sheet and Body CM-AA-ETE-101 Attachment 2 Page 2 of 7 Primarv Recipient(s):

Copy Other Recipient/ Department or Copy To? I Other Recipient/ Department or Location To? Location D Preparer D Reviewer D Supervisor D Site Design Engineering Designee D Affected Organization D Program Owners D System Engineer D Nuclear Document Manaqement Source Document

1. CR1142973 "Water coming from under insulation from common discharge piping SW' Purpose The purpose of this ETE is to document the structural integrity evaluation of the fabricated tee in Millstone Unit 3 service water pipe spool 3-SWP-19-2-7-3 to support a service water train Operability Determination and Alternative Request in response to the reference 1 CR. This ETE is prepared as a Level 1 ETE in accordance with CM-AA-ETE-101 Step 2.4.a "Document a technical position in cases where more rigorous documentation is required to support the position" and Step 2.4.c. "Document technical basis supporting responses to INPO, NRC ... ". Note the current version of the ETE cover page (form 730801) is dated Apr 2019 while the version in CMIS is dated Sep 2018. The difference between the two versions has been reviewed and is administrative (administrative note have been included in the latest version). This difference has no impact on the development or quality of this ETE. A formal risk assessment has not been performed within this ETE.

Engineering technical risk is addressed through the follow on operability determination and relief request process. A challenge review has been performed on 3/13/2020 including members of Millstone site engineering management, site licensing management, Dominion corporate engineering and Dominion corporate licensing.

Discussion The Reference 1 CR documents a degraded condition (evidence of through wall pipe leakage) on Millstone Unit 3 moderate energy service water line 3-SWP-030-15-3(A-), spool 3-SWP-19-2-7-3 as shown on fabrication installation drawing reference 2.2. This spool is a 30 inch OD, 0.500 inch nominal wall thickness pipe class 158 with a design pressure of 100 psig and a maximum operating pressure of 92 psig and a design temperature of 80°F. The pipe material is SA-516 Gr 70 base metal with 0.100 inch minimum thick clad of SB-402 #706 Cu-Ni. The CR indicates water is emanating from the weep hole in the fabricated tee reinforcing pad of this spool. Note that reference 2.1 refers to the reinforcement as a reinforcing pad and reference 2.3 refers to the reinforcement as a reinforcing pad. The water emanating from the weep hole is indicative of a through wall hole in the pipe and or weld material that is obscured by the reinforcing pad. The presence of the reinforcing pad precludes the use of NOE to locate and characterize flaw(s) at this location. NOE has been Form 730801 (Sep 2018)

ETE-MP-2020-1027 Rev. O Report Generated on 3/14/2020 9:05:26 PM Page 3 of 27 Engineering Technical Evaluation Cover Sheet and Body CM-AA-ETE-101 Attachment 2 Page 3 of 7 used to assess the condition of the reinforcing pad, the reinforcing pad fillet weld and the pipe and branch run base material immediately under the reinforcing pad fillet welds (see attachment 1 for inspection results). The reinforcing pad design is shown on the spool drawing (reference 2.1) item G. The reinforcing pad is designed in accordance with the shop fabrication specification reference 7 and the construction code reference 4, ASME Code Section Ill, ND-3600, NC-3600 as supplemented by Winter 1972 Addenda. The reinforcing pad is fabricated from SA-516-70 % inch rolled plate per reference 2.1.

To ensure that in the current condition of the spool will support the structural analysis, the following has been performed (see attachment 1 for inspection reports):

Confirmed that the reinforced opening of the piping spool was fabricated to the appropriate Code NC 3643.3 and reviewed the certificate of inspection.

A review of the in-service conditions of this piping spool concluded that in-service degradation of the spool components needed for structural integrity is not likely based on the following conditions:

The installed configuration of the piping spool results in primary applied stresses that are well below allowable stresses by a factor of greater than 3.

The stresses at this location result in approximately 50%of allowable stress due to thermal and dead load. The Code allowables are based on 7000 thermal cycles. This pipe spool has experienced significantly less than 7000 cycles based on seasonal temperature fluctuations of the seawater and any maintenance activities (i.e., draining of the pipe). Thus, the potential for thermally induced fatigue is low.

The spool is isolated from pump vibrations by an installed strainer and expansion joint. Thus, the installed configuration of this spool results in minimal high cycle fatigue.

Additionally, inspections of the in-service spool were performed to confirm that the conditions of the spool will support the continued structural integrity of the spool. These inspections included:

UT measurements of pipe wall thickness adjacent to the reinforcing pad welds and of the area of the pipe directly under the welds using shear wave UT UT measurements of the reinforcing pad thickness adjacent to the reinforcing pad welds and at selected locations across the reinforcing pad.

A visual exam of the reinforcing pad welds.

Relative to the welds, there is substantial margin in the weld capacity (0.215 inch weld required versus 0.500 inch weld nominal - see attachment 2).

Based on these considerations there is reasonable expectation that the in service condition of the reinforcing pad and the piping that can be examined are and will remain in a condition to support their intended use for maintaining structural integrity of this piping spool.

The confirmed integrity of these components provides a sound load carrying path between the branch and main run of the piping.

Form 730801 (Sep 2018)

ETE-MP-2020-1027 Rev. O Report Generated on 3/14/2020 9:05:26 PM Page 4 of 27 Engineering Technical Evaluation Cover Sheet and Body CM-AA-ETE-101 Attachment 2 Page 4 of 7 The approach of this evaluation is to assess the capability of the reinforcing pad to carry the mechanical loads present at this location without credit of the load carrying capacity of the underlying branch to run pipe weld connection. The load carrying capability of the reinforcing pad is assessed by comparing the design margin between the calculated design stress (extracted from the pipe stress analysis of record, reference 3) and the allowable stress for the applicable ASME Code load combinations. This comparison is performed for both reinforced and unreinforced tee designs. The comparison of stress for the reinforced and unreinforced tee configurations provides an assessment of the load carrying capability provided by the reinforcing pad.

The pipe stress calculation (reference 1) work sketch indicates this tee connection is located at node 215 of the pipe stress model. The associated as built drawing (reference 2.3) shows the pipe support configuration. The support nomenclature is defined as follows. VC indicates vertical constraint (ie restrains up and down vertical motion) and PSA indicates pipe support anchor. The NUPIPE computer model run of record is R1884E01 dated 2/19/93. Referring to the NUPIPE run table of intersection stresses shown on pages 414 (normal/ upset) and 422 (faulted) the following maximum stresses for Code equations and stress intensification values are extracted for both a reinforced and unreinforced tee configuration. The associated code allowable stress values< 1l are also extracted from the Maximum Stress Levels & Allowables table from pages 56 and 57 of reference 3. The Millstone Unit 3 Piping Operability Manual section 5.1.3 Piping Acceptance Criteria (reference

5) indicates Level A normal loads (equation 8) and Level D faulted loads (equation 9F) are applicable for this assessment.

To make a comparison of the moment carrying capability of the reinforcing pad it is reasonable to compare the moment terms of the above load combinations. The longitudinal pressure term (P*d/4t = 1500 psi)< 2l is removed from the ASME Code (reference 4) Section NC-3652 Equation 8 and Equation 9 faulted values to obtain stress due to deadweight S0 and stress due to seismic inertia SE. Code Equation 9 also includes stresses due to occasional loads other than seismic such as water hammer, opening and closing of safety relief valves, etc. In the pipe stress calculation reference 4 there are no occasional loads other than seismic to be considered.

Pipe Stress Calculation NP(B) X1901 Node 215 Stresses Stress Eq 8 Eq 9F Deadweight Seismic+ Eq 8 / Eq 9F /

Intensification stress psi stress psi longitudinal Deadweight Allowable Allowable Factor stress S0 longitudinal psi Stress So+

SE psi Reinforced 4.375 3539 7676 2039 6176 0.202 0.183 Tee Unreinforced 8.602 5509 13644 4009 12144 0.315 0.325 Tee Allowable 17500 42000 Stress psi Form 730801 (Sep 2018)

ETE-MP-2020-1027 Rev. 0 Report Generated on 3/14/2020 9:05:26 PM Page 5 of 27 Engineering Technical Evaluation Cover Sheet and Body CM-AA-ETE-101 Attachment 2 Page 5 of 7 Based on the above table the presence of a reinforcing pad reduces the deadweight and seismic stress levels by a factor of 1.97, which corresponds to the ratio of the reinforced to unreinforced SIFs of (8.602/4.375).

Based on the principle of superposition it is therefore reasonable to consider the reinforcing pad as having a similar mechanical load carrying capacity as an unreinforced branch tee connection. As shown in the table above, the mechanical load carrying capability of an unreinforced tee configuration at this location has a margin of approximately 3 (1/0.325) to the original Equation 9 faulted allowable stress. This provides reasonable assurance the reinforcing pad also has considerable margin to the Code stress allowables for carrying the mechanical deadweight and seismic loads described above.

It is recognized this evaluation does not consider the reinforcing pad to provide pressure retaining capability.

As noted above, the reinforcing pad has an approximately 3/8 inch diameter weep hole to preclude the development of full system pressure internal to the reinforcing pad. If the reinforcing pad were to be subject to the full internal design pressure of 100 psig (if the weephole were plugged) the corresponding longitudinal stress would be approximately 1050psi = 100psig

31.5 inch /4*0.750 inch (Design Pressure*Outside Diameter/4*nominal wall thickness). As demonstrated above there is a large margin between the stress resulting from applied mechanical loads and the allowable stress. The potential longitudinal pressure stress of 1050psi is small compared to the available margin of approximately 12000psi.

In addition to the review of pipe stress analysis ASME Section Ill Code equations (i.e., Equations 8 and 9) performed above, two additional checks were performed as an alternate evaluation of the design margin available at this location. These checks are included in attachment 2 and attachment 3. The first evaluation is the required weld size for the applied loads at the branch connection for the worst combined design loads. The second check is a Code area reinforcement evaluation (i.e., area that can be credited to compensate for the material removed by the hole for the branch connection and still meet Code requirements for area reinforcement).

Results of the weld size evaluation performed in attachment 2 show that the required weld size is 0.215 inches, which is less than the actual weld size of nominally at least 0.500 inches on average (see attachment 1).

Additionally, the area reinforcement evaluation provided in attachment 3 for a run and branch line nominal wall thickness of 0.500 inches indicates that significant wall loss from 0.500 inches to 0.205 inches could be accommodated and still meet the minimum required area reinforcement for internal pressure considerations.

These two independent assessments provide additional assurance that structural integrity will be maintained with the load path provided by the reinforcing pad alone, with adequate margins of safety for the subject branch connection.

The next refueling outage is scheduled for Fall of 2020. Relative to corrosion considerations, the low corrosion rate expected for this condition (approximately 0.0006 inches/ month (see attachment 5) for the carbon steel reinforcing pad) and the time to the next refueling outage (approximately 8 months which assumes a 30 day mission time beginning the day the outage is scheduled to start), results in a wall loss of approximately 0.0048 inches. The material thickness considering this corrosion material loss at the end of 8 months is still sufficient to provide adequate margin to maintain structural integrity based on the above evaluations.

Note 1: ASME Section Ill Appendix F of the Code and reference 5 allow the use of higher Level D allowables for all load combinations however use of these higher allowables was not necessary to demonstrate acceptable results.

Form 730801 (Sep 2018)

ETE-MP-2020-1027 Rev. 0 Report Generated on 3/14/2020 9:05:26 PM Page 6 of 27 Engineering Technical Evaluation Cover Sheet and Body CM-AA-ETE-101 Attachment 2 Page 6 of 7 Note 2: P=Design Pressure (psig), d=Pipe Outside Diameter (inches), t=Pipe Wall Thickness (inches).

Note 3: Use of an increased ASME Code design stress intensity value (Sm) of 20,000 psi for SA-516 Grade 70 material would also be acceptable based on a code reconciliation review of the construction code to later code editions, which would provide an additional 14% margin to the evaluations performed in this ETE (Ref. 4, 8 & 9).

Conclusions This ETE has documented the acceptable structural integrity evaluation of the subject service water spool with consideration of the degraded condition documented in the reference 1 CR. Reasonable assurance has been demonstrated that the reinforcing pad of the subject fabricated tee has considerable margin to the Code stress allowables (and can accommodate expected reinforcing pad material wall loss) for carrying the mechanical deadweight and seismic loads required to support an Operability Assessment and Alternative Request. While structural integrity has been demonstrated this condition is not Code compliant since the Code does not provide for the design of a fabricated tee using only a reinforcing pad and not having a full penetration weld between the branch and the main pipe run.

References

1. CR1142973 "Water coming from under insulation from common discharge piping SW'

2. Drawings (See attachment 4) 2.1. Spool Drawing 3-SWP-19-2-7-3 Revision 4 (attachment 4) 2.2. 25212-21041 Sh 16 (12179-CI-SWP-19 Sh 1) Rev 17 "Fabrication Installation Control Drawing" (attachment 4) 2.3. 25212-21041 Sh 18 Rev 17 "Fabrication Installation Control Drawing Stress Reconciliation Piping Location Isometric" (attachment 7)

3. Calculation 12179-NP(B)-X1901 Rev 03 through Addendum 12, "Pipe Stress Analysis: Service Water Piping - CW Pump House to Turbine Building"

4. ASME Code Section Ill, 1971 edition through Summer 1973 Addenda

5. Piping Operability Determination Manual, Millstone Unit 3, Rev. 1

6. Work Order 53203264267 "Insulation removal on Service Water Pipe 2-SWP-030-415-3"

7. Specification 2280.000-450, Revision 3 through Addendum 4, "Shop Fabricated Piping, ASME Code Section Ill, Classes 1, 2 & 3, and ANSI 831.1, Class 4"

8. ASME Code Section 11-D 2007 Edition through 2009 Addenda

9. Corporate Standard DNES-VA-ME-0023 "Code Reconciliation" Attachments

1. NDE Inspection Report for Work Order 53203264267

2. Alternate Structural Evaluation - Required weld size at the branch connection Form 730801 (Sep 2018)

ETE-MP-2020-1027 Rev. O Report Generated on 3/14/2020 9:05:26 PM Page 7 of 27 Engineering Technical Evaluation Cover Sheet and Body CM-AA-ETE-101 Attachment 2 Page 7 of 7

3. Alternate Structural Evaluation - Area Reinforcement evaluation with nominal wall thickness (i.e. 0.5") of run and branch lines and with 0.25" wall thickness of run and branch lines

4. Piping Drawings (Spool and Fabrication)

5. Corporate Engineering Corrosion Rate

6. Certificate of Shop Inspection for Spool 3-SWP-19-2-7-3

7. Drawing 25212-21041 Sh 18 Rev 17 "Fabrication Installation Control Drawing Stress Reconciliation Piping Location Isometric" Form 730801 (Sep 2018)

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Comments: Utilized angle beam transducer.

0 I Date Reviewer Signature Date a 3/12/2020 N/A N

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Description:

30" Saddle Reinforced Tee(Fish Mouth)

System ID:

Component ID: Line# 3-SWP-030-18..S(A} OS of 3SWP*MOV102C Size/Length: N/A Thickness/Diameter. .500" & .750"130" Limitations: From TDC, 16.25" to 32.25" obstructed due to flange joint US of main run. Start Time: 14:00 Finish Time: 17:30 2

a.. Instrument Settings Search Unit CD Cal. Time Date Axial Oriented Search Unit U) Serial No.: 021D9Y Serial No.: 57462-9687 Checks 0 Calibration Signal Sweep Depth cri Manufacturer: GE Manufacturer: KB-Aerotech Initial Cal. 14:00 3/12/2020 Reflector Amplitude% Division 0

N Model: USN60SW Linearity: MP-L-20-007 Size: 3.5mm x 10mm Model: NIA Inter. Cal. NIA 0 .250" Step 80% 2.5 .250"

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0. Shape: 2 Contour: NIA Reflector Amplitude% Division Depth Ql Mfg.: Sonotech, Inc.

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Percent Of Coverage Obtained > 90%: N/A Reviewed Previous Data: NIA

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Attachment #1 Page 4 of 1o ETE-MP-2020-1027 Rev. 0 Report Generated on 3/14/2020 9:05:26 PM Page 11 of 27 Supplemental Report Report No.: BOP-UT-20-059 Page: 2 of 2 Summary No.: NIA Examiner: Level: IIL Reviewer: NIA Date: t-.J/A, Examiner: NIA Level: NIA Site Review: Date: 3J\'-/w Other: N/A Level: NIA ANH Review: NIA Date: rvjA Comments:

0 degree UT scan of the pipe has an overall average thickness of .660" with a low UT reading of .600".

0 degree UT scan of the plate has an average of .750" to .780" with a low UT reading of .730".

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Comments: NIA 0

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Description:

30" Saddle reinforced, Tee.

System ID: sws Component ID: 3-SWP-030-18~, OS of 3SWP*MOV102C Size/Length: N/A Thickness/Diameter. .500"/30" Limitations: From TDC, 16.25" to 32.25" Obstructed due to flange joint US of main run. Start Time: 1400 Finish Time: 1730 2

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Squint Angle:

N/A N/A Inter. Cal. N/A C

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w Comp. Temp.

- 44 Temp. Tool:

Exam Surface: OD

- - Type: cs 43 NSDH 80% 3.6 .830" N/A tu Surface Condition: Smooth (s} D 0 p Comments: Performed 70 deg exam of weld base material adjacent Results: NRI 0 Rl D Geom D to saddle weld for evidence of material degradation.

Percent Of Coverage Obtained > 90%: NIA Reviewed Previous Data: N/A *Maintained apprx.10%-20% ID roll.

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Attachment #1 Page 7 of 1O ETE-MP-2020-1027 Rev. 0 Report Generated on 3/14/2020 9:05:26 PM Page 14 of 27 Supplemental Report Report No.: BOP-UT-20-060 Page: 2 of 2 Summary No.: N/A .

E x a m i n e r : - Level: II Reviewer: N/A Date: r-J/ A Examiner: N/A Level: N/A Site Review: Date: }Ln..£2-0 0th er:

N/A Level: N/A ANII Review: N/A Date: N}A Comments:

ER-AA-NDE-UT-801 used as a guideline.

- Cal block temperature was ambient. Component temperature was 44 degrees per plant computer potnt T47A.

ISi performed UT scan of pipe adjacent to saddle weld/relnfocement plate on the main run and the branch welds. Scanning was performed perpendicular to the weld, covering approximately 2" of piping under the plate. ISi also scanned paralell to the saddle weld In both directions. No pipe material degradation was observed.

Attachment #1 Page 8 of 10 ETE-MP-2020-1027 Rev. 0 Report Generated on 311412020 9:05:26 PM Page 15 of 27 Attachment 1 Exam Data Sheet JMillstone Power Station ULTRASONIC EXAMINATION STRAIGHT BEAM MEASUREMENTS Plant Millstone Unit 3 Page 1 of 3 System & Zone No. SWP Exam Data Sheet No. NIA Component ID 3-SWP-030-15-3 AWO Number 53203264267 Component Description Saddle/Reinforcement 12late Drawing No. 25212-21041 Sh. !8 Examination Purpose Engineering Information Line No. 3-SWP-030-15-3 Instrument & Settings Calibration Block(s) Component Data Manufacturer Olympus Type Serial No. Material Component Tnom NIA Model No. 38 DLPlus Step Block 95-5768 cs Component Dia. NIA Serial No. 120497309 NIA NIA NIA Attachments. NIA Range 1.000" Velocity .2336 Calibration Checks Block Thickness Instrument Reading Delay NIA Type Time Min. Max. Min. Max.

Zero Value 28460 Initial 1400 .250" 1.000" .250" 1.000

Cal Tolerance +I- .002" Intermediate NIA NIA NIA NIA NIA Intermediate NIA NIA NIA NIA NIA Search Unit Data Final 1505 .250" 1.000" .250" 1.000" Manufacturer Panametrics Type No. D791-R.M Couplant Data Temperature Data Serial No. 833197 Brand Ultragel II Cal. BJ.le. Temp. NIA Frequency 5MHZ Batch No. 19A039 Component Temp NIA Size .312" SAP Batch Mgmt. No. NIA Thermometer SIN NIA ISI Performed a 4" grid and UT of saddle/Reinforcement plate on pipe 3-SWP-030-15-3.

See attached photo and UT data.

NOTE: 4" grid did not stay on pipe due to excessive condensation.

6'Dual Cable

_ _ _.Level II Date 03/1312020 Reviewer (sign _ _ _ _ _ _ _ _ _ _ _.Level IIL Date 0311312020 ANI/ANII If Required (Sign) _ _ _ _ _ _~ N = / A ~ - - - - - - - - - - - - - Date _ __,N"""/~A-.._ __

Level of Use ER-AA-NDE-UT-701 Rev. 7 Reference

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a, 10 0.000 0.000 0.752 0.759

0.7,61 .. 0.000 0:762 0.000 0.000 0.000 0.000 0.000 0.000 . lJi7S6 0.760 0.761 0.758 0.763 0.000

('.) .. Not Used t 11 0.000 0.000 0.000 0.743* ,d.760 **o,762* 0.761 0.7~2.. 0.764. -*o,tii!i cL'.768 o:zilf 0,759 Q:762 *0.760 .0.761 0.765 0.000 0.000 0

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13 0.000 0.000 0.000 0.000 0.000 0.000 0.760 0,7155 0.765 QJ68 0:7~- ,ciq:~ 0.760 0;76!:. l*q1zeyr g;z.63 0.000 0.000 0.000 0

14 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.771 0.760 0.764 ,.0.764 0,762 0.755 0.000 0.000 0.000 0.000 0.000 0.000 NotiJsed a, ~.000 0::

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Mytherm := max MY:ther.m33 ,MYtherm75 ,MYtliermLG11 ,MYther-mLC12) = llil..7~9 lb' ft * *\

Mztherm~;;;:.maf'IMZtherm3S ,.Nfztherm'f5, ' M'Ztlu!rm:£e1-1-,.Mztherrh,£G12 I . ) _;;::::_7876. lb' i f.L. *

' i I I . I I I i I i Combine deadioad, seismic, occasional, and max t:hermal as bounding lo~d condition: *;-*** .. .

. . .. . . : - ....... : . . .. *r ..... . . *. . . .T....... ************ -+--*- . .

.Extotal .

=.FXDri+/-FxssEtotal

-'-'I

+/-.fxocc

+Extherr)i*;;;;;.2832.l I ... lb !

. . . ...... ,:- ..... .. ' ,., .... 11 """""* . . . . . . . . : . .

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~ f Fzxtot~l := 1:2i~xL F+/-zMs~total 1tMocxc +F~+/-tMhermxF 224~310*Z9b0,..,2 i1b .

.M . total**:::;:..1,v.1 Dir* - *""SSEtrtt. al T . eoo*.. . r*herm*;::;.., . . L i" .*..in

.. . . . . !11 ****** . . 11

.Myto~az.:=.:MyJL+/-MYssEtotal+MYooc+..Mytherm*;;::,192933$ lb.* in. . ... +**** . . . . . .. . . . . . .

~~~~+~_"_~t~:~~tm~~J~~t~:~---~1~----- i_

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1 .. ~--~*-=:.~~-- .* -.-*r* ** * *- * * --

Attachment #2 Page 2 of 2 ETE-MP-2020-1027 Rev. o Report Generated on 3/14/2020 9:05:26 PM Page19of27

..)

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F2 := Fxtotdl, 1 M2 :=M:xtotal-I

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Attachment #3 Page 1 of 2 ETE-MP-2020-1027 Rev. O Report Generated on 3/14/2020 9:05:26 PM Page 20 of 27 Branch Reinforcement Area Check Component test Line line Station .. ls-'PS-*2======='" I US Main DSMaio Branch Main Branch US Main DSMaln I Branch O.D., in 30.000 30.000 30.000 Design Pressure, psi 100 100 Evaluate to Cod! Tm. In ....

Nominal I.D., in 29.000 29.000 29.000 Design Temperaturei °F 100 200 Code Tm, in 0.100 0.1001 0.100 Design Tn in I 0.500 0.500 0.500 Allowable Stress, Sh, psi 17500 17500 USER Tmi111 in 0.100 0.1001 0.100 Actual T~ in 0.250 0.250 0.250 Allowable Stress, Sc, psi 17500 17500 Req'd Reinforcement, in2 3.116 3.116 Wear Rate, in/yr 0.025 0.025 0.025 Design Pressure Stress, SLP, psi 1425.42 1425.42

'"--~.. """"--'-'

Pad Thickness Te, in 0.000 Alpha, deg 90 Width of Reinforcing Ring in

- ~,... "

/,,-

1"~~'.:r

.. US Main

'** *USMaln "DSMain* Branch .IH ** ** ' '!US Main DSMiiiri ,,* inUSMaiii DSMain

DSMainlil USMain ... : (',. , :DSMain

1***.*d2 .. * }L . **.A2 **. ,*_*A4.

. f . /'

(years)******/* ..

AchialT: Actual'I',

.'.*;(i~J\. *"It", ~t * ~z *,

"-'""' *,(in*

'l-: :Al

- l) * (In') -.(in') (ln2) 2

\ .

Req'dArea Al+AZ+A4 Req'dArea

(in'*'

I (ln1Y (lii1 0.00 0.250 0.250 0. 29.500 29.500 29.500 4.425 4.425 0.188 0.000 0 4.613 3.157 4.613 3.157 0.20 0.245 0.245 o. 29.510 29.510 29.510 4.279 4.279 0.178 0.000 0 4.457 3.158 0.40 0.240 0.240 o. 29.520 29.520 29.520 4.133 4.133 0.168 0.000 0 4 301 3.159 4.301 3.159 0.60 0.235 0.235 0. 29.530 29.530 29.530 3.987 3.987 0.159 0.000 0 4.145 3.160 4.145 3.160 0.80 0.230 0.230 o: 29.540 29.540 29.540 3.840 3.840 0.150 0.000 0 3.990 3.161 3.990 3.161 I.DO 0.225 0.225 0.22 29.550 29.550 29.550 3.694 3.694 0.141 0.000 0.000 3.834 3.162 3.834 3.162 1.20 0.220 0.220 0.220 29.560 29.560 29.560 0.5H 3.547 3.547 0.132 0.000 0.000. 3.679 3.163 3.679 3.163 1.40 0.215 0.215 0.215 29.570 29.570 29.570 0,531 3.401 3.401 0.124 0.000 0.000 3.524 3.164 3.524 3.164 1.60 0.210 0.210 0.210 29.580 29.580 29.580 0.525 3.254 3.254 0.116 0.000 0.000 3.369 3.165 3.369 3.165 I.BO 0.205 0.205 0.205 29.590 29.S90 29.590 0.513 3.107 3.107 0.108 0.000 0.000, 3.215 3.166 3.215 3.166 2.00 0.200 0.200 0.200 29.600 29.600 29.600 0.500 2.960 2.960 0.100 0.000 0.000 3.060 3.167 3.060 3.167 2.20 0.195 0.19S D.19S 29.610 29.610 29.610 0.488 2.813 2.813 0.093 0.000 0.000, 2.906 3.168 2.906 3.168 2.40 0.190 0.190 0.190 29.620 29.620 29.620 0.475 2.666 2.666 O.OB6 0.000 0.000 2.751 3.169 2.751 3.169 2.60 0.185 0.185 0.185 29.630 29.630 29.630 0.463 2.519 2.519 0.079 0.000 0.000. 2.597 3.170 2.597 3.170 2.80 0.180 0.180 0.180 29.640 29.640 29.640 0.450 2.371 2.371 0.072 0.000 0.000 2.443 3.171 2.443 3.171 3.00 0.175 0.175 0.175 29.650 29.650 29.650 0.438 2.224 2.224 0.066 0.000 0.000 I 2.289 3.173 2.289 3.173 3.20 0.170 0.170 0.170 29.660 29.660 29.660 0.425 2.076 2.076 0.060 0.000 0.000 .. 2.136 3.174 2.136 3.174 3.40 0.165 0.165 0.165 29.670 29.670 29.670 0.413 1.929 J.929 0.054 0.000 0.000 1.982 3.175 1.982 3.175 3.60

' 0.160 0.160 0.160 29.680 29.680 29.680 0.400 1.781 1.781 0.048 0.000 0.000 1.829 3.176 1.829 3.176 3.80 0.155 0.155 0.155 29.690 29.690 29.690 0.388 J.633 1.633 0.043 0.000 0.000 I 1.676 3.177 1.676 3.177 4.00 0.150 0.150 0.150' 29.700 29.700 29.700 0.375 1.485 1.485 0.038 0.000 0.000

1.523 3.178 1.523 3.178 4.20 0.145 0.145 0.145 29.710 29.710 29.710 0.363 1.337 1.337 0.033 0.000 0.000 *!.370 3.179 1.370 3.179 4.40 0.140 0.140 0.140 29.720 29.720 29.720 0 1.189 1.189 0.028 0.000 0.000 I *.

' 1.217 3.180

1.217 3.180 4.60 0.135 0.135 0.135 29.730 29.730 29.730 1.041 1.041 0.024 0.000 0.000 . 1.064 3.181 1.064 3.181 4.80 0.130 0.130 0.130 29.740 29.740 29.740 0.892 0.892 0.020 0.000 0.000 0.912 3.182 0.912 3.182 5.00 0.125 0.125 0.125 29.750 29.750 29.750 0. 0.744 0.744 0.016 0.000 0.000 0.759 3.183 0.759 3.183

5.20 0.120 0.120 0.120 29.760 29.760 29.760 0. 0.595 0.595 0.012 0.000 0.000 0.607 3.184 0.607 3.184 5.40 0.115 O.l!S 0.115 29.770 29.770 29.770 0.288 0.447 0.447 0.009 0.000 0.000 I*. 0.455 3.185 0.455 3.185 5.60 0.110 0.110 0.110 29.780 29.780 29.780 0.275 0.298 0.298 0.006 0.000 0.000 !

0.303 3.186 0.303 3.186 5.80 0.105 0.105 0.105 29.790 29.790 29.790 0 0.149 0.149 0.003 0.000 0.000. 0.152 3.188 0.152 3.188 6.00 , FAIL FAIL FAIL FAIL FAIL FAIL 0 0.000 0.000 0.000 0.000 0.000 0.000 FAIL 0.000 FAIL 6.20 ; FAIL FAIL FAIL FAIL FAIL FAIL 0.000 0.000 0,000 0.000 0.000 0.000 FAIL 0.000 FAIL 6.40 FAIL FAIL FAIL fFAil.. FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0.000 FAIL 0.000 FAIL 6.60 FAIL FAIL FAIL FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0,000, 0.000 FAIL .. 0.000 FAIL 6.80 ; FAIL FAIL FAIL FAD. FAIL FAIL 0.00( 0.000 0.000 0.000 0.000 0.000 I 0.000 FAJL 0.000 FAIL 7.00 'FAIL FAIL FAIL l FAIL FAD. FAIL 0.00( 0.000 0.000 0.000 0.000 0.000 0.000 FAIL 0.000 FAIL 7.20 JFAil.. FAIL FAIL I FAIL FAIL FAIL 0.00( 0.000 0.000 0.000 0.000 0.000 0.000 FAIL 0.000 FAIL 7.40 I FAIL FAIL FAIL iFAIL FAIL FAIL o.onr 0.000 0.000 0.000 0.000 0.000 i 0.000 FAJL 0.000 FAIL 7.60 :FAIL FAIL FAIL FAIL FAIL FAIL o.onr 0.000 0.000 0.000 0.000 0,000 1 0.000 FAIL 0.000 FAIL 7.80 :FAIL FAIL FAIL FAIL FAIL FAIL 0.00( 0.000 0.000 0.000 0.000 0.000, 0.000 FAIL 0.000 FAIL 8.00 FAIL FAD. FAIL FAIL FAIL FAIL om, 0.000 0.000 0.000 0.000 0.000 i 0.000 FAIL 0.000 FAIL 8.20 ; FAIL FAIL FAIL FAIL FAIL FAIL o.oru 0.000 0.000 0.000 0.000 0.000 0.000 FAIL 0.000 FAIL 8.40 !FAIL FAIL FAIL FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 FAIL 0.000 FAIL B.60 , FAIL FAIL FAIL FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 FAIL * *o.ooo FAIL 8.80 FAIL FAIL FAIL FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0,000 0.000 FAIL 0.000 FAIL 9.00 ,FAIL FAIL FAIL 'FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 FAIL 0.000 FAIL 9.20 !FAIL FAIL FAIL , FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0.000 j 0.000 FAIL 0.000 FAIL 9.40 'FAIL FAIL FAIL FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 FAIL 0.000 FAIL 9.60 Ii FAIL FAIL FAIL !FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 FAIL 0.000 FAIL 9.80 : FAIL FAIL FAIL FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0.000 '. 0.000 FAIL 0.000 FAIL 10.00 IFAIL FAIL FAIL FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0.000 ! *0.000 FAIL 0.000 FAIL 10.20 (FAIL FAIL FAIL -FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 FAIL 0.000 FAIL 10.40 I FAIL FAIL FAIL !FAIL FAIL FAIL 0.000 0,000 0.000 0,000 0.000 0.000 i 0.000 FAIL 0.000 FAIL 10.60 !FAIL FAIL FAIL FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 FAIL 0.000 FAIL 10.80 FAIL FAIL FAD. FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 FAIL 0.000 FAIL II.DO , FAIL FAIL FAIL FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0.000. 0.000 FAIL 0.000 FAIL 11.20 FAIL FAIL FAIL FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 FAIL *o.ooo FAIL 11.40 ,FAIL FAIL FAIL FAIL FAIL FAIL 0.000 I 0.000 0.000 0.000 0.000 0,000. 0.000 FAIL 0.000 FAIL 11.60 :FAIL FAIL FAIL FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0.000, 0.000 FAIL 0.000 FAIL 11.80 , FAIL FAIL FAIL !FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0,000' 0.000 FAJL 0.000 FAIL 12.00 FAIL FAIL FAIL !FAIL FAIL FAIL 0.000 i 0.000 0.000 0.000 0.000 o.oool 0.000 FAIL 0.000 FAIL 12.20 iFAIL FAIL FAIL FAIL FAIL FAIL 0.000 0.000 0.000 0.000 0.000 0.000 I 0.000 FAIL 0.000 FAJL 12.40 iFAIL FAIL FAIL FAIL FAIL FAIL 0.0001 0.000 0.000 0.000 0.000 0.000 0.000 FAIL 0.000 FAJL 12.60 FAIL FAIL FAIL FAIL FAIL FAIL 0.000' 0.000 0.000 0.000 0.000 0.000 0.000 FAIL 0.000 FAIL 12.80 :FAIL FAIL FAIL 1FAIL FAIL FAIL 0.000! 0.000 0.000 0.000 0.000 0.000 0.000 FAIL 0.000 FAIL 13.00 'FAIL FAIL FAIL FAIL FAIL FAIL 0.000\ 0.000 0.000 0.000 0.000 0.000 0.000 FAIL 0.000 FAIL Page 1 of 8

Attachment #3 Page 2 of 2 ETE-MP-2020-1027 Rev. 0 Report Generated on 3/14/2020 9:05:26 PM Page 21 of 27 Branch Reinforcement Area Check Component test Station !,.,'==*'======="=-!

US Main DSMaln Branch Main Branch USMnin DSMain I Branch O.D.,in 30.000 30.000 30.000 Design Pressure, psi JOO 100 E\li!IUale to USER Tmln, lo ....

Nominal I.D., in 29.000 29.000 29.000 Design Temperature, °F 100 200 Code Tm, in 0.100 0.100! 0.100 Design Tn, in 0.500 0.500 0.500 Allowable Stress, Sh, psi 17500 17500 USER Tmin,in 0.100 0.1001 0.100 Actual T111 in 0.500 0.500 0.500 Allowable Stress, S" psi 17500 17500 Req1d Reinforcement, in2 3.116 3.116 WCBI Rate, in/yr 0.025 0.025 0.025 Design Pressure Stress, SLP I psi 1425.42 1425.42 Pad Thickness T~ in 0.000

_Alpha, d~g Width of Reinforcing Ring, in ___Q

\:J KTime i<\'dt,USMain' ;JJSMain'

,(;liJ;;~l': Actual T, Actpiil BTr i ~

.(In

- : J I U S M a i n DSMain

.ft*ifrt,*** Al (In')

A2 USMabi DS.Main -:\.i'. USMniii, ..**"i' (In') .,.*

',A4

A4

>cfu'i * >c1ri'>

,\l+~\.2+A,4 Il.~q'~;\rei

(in1)

r-~ :<*DSMam*:.. ,

~ltA;2+~4

(!n"l ** * (in1) .'

ReiJ'.d~ca (in')

- ,*-\/in) * . ., - . . . .~ .

0.00 0.500 0.500 29.000 29.000 29.000 1.250 11.600 11.600 1.000 0.000 0.00( 12.600 3.11( , 12.600 3.116 0.20 0.495 0.495 0.495 29.010 29.010 29.010 1.238 11.459 11.459 0.978 0.000 0.000 12.437 3.116 l.t.:."t.J/

0.40 0.490 0.490 0.490 29.020 29.020 29.020 1.225 11.318 11.318 0.956 0.000 0.000 12.273 3.116 12.273 3.116 0.60 0.485 0.485 0.485 29.030 29.030 29.030 1.213 l!.177 11.177 0.934 0.000 0.000 12.110 3.116 12.110 3.116 0.80 0.480 0.480 0.480 29.040 29.040 29.040 1.200 11.035 11.035 0.912 0.000 0.000, 11.947 3.116 11.947 3.116 1.00 0.475 0.475 0.475 29.050 29.050 29.050 1.188 10.894 10.894 0.891 0.000 0.000 11.784 3.116 11.784 3.116 1.20 0.470 0.470 0.470 29.060 29.060 29.060 l.175 10.752 10.752 0.870 0.000 0.000 11.622 3.116 11.622 3.116 1.40 0.465 0.465 0.465 29.070 29.070 29.070 1.163 10.611 10.611 0.849 0.000 0.000 11.459 3.116 11.459 3.116 1.60 0.460 0.460 0.460 29.080 29.080 29.080 l.150 10.469 10.469 0.828 0.000 0.000' 11.297 3.116 11.297 3.116 1.80 0.455 0.455 0.455 29.090 29.090 29.090 1.138 10.327 10.327 0.808 0.000 0.000 11.135 3.116 11.135 3.116 2.00 0.450 0.450 0.450 29.100 29.100 29.100 1.125 10.185 10.185 0.788 0.000 0.000 ! 10.973 3.116 10.973 3.116 2.20 0.445 0.445 0.445 29.110 29.!10 29.110 1.113 10.043 I0.043 0.768 0.000 0.000 10.811 3.116 10.811 3.116 2.40 0.440 0.440 0.440 29.120 29.120 29.120 1.100 9.901 9.901 0.748 0.000 0.000 10.649 3.116 10.649 3.116 2.60 0.435 0.435 0.435 29.130 29.130 29.130 l.088 9.759 9.759 0.729 0.000 0.000 10.487 3.117 10.487 3.117 2.80 0.430 0.430 0.430 29.140 29.140 29.140 1.075 9.616 9.616 0.710 0.000 0.000 10.326 3.118 10.326 3.118 3.00 0.425 0.425 0.425 29.150 29.150 29.150 1.063 9.474 9.474 0.691 0.000 0.000 10.164 3.119 10.164 3.119 3.20 0.420 0.420 0.420 29.160 29.160 29.160 1.050 9.331 9.331 0.672 0.000 0.000 I0.003 3.120 I0.003 3.120 3.40 0.415 0.415 0.415 29.170 29.170 29.170 l.038 9.189 9.189 0.654 0.000 0.000 9.842 3.121 9.842 3.121 3.60 0.410 D.410 0.410 29.180 29.180 29.180 1.025 9.046 9.046 0.636 0.000 0.000 9.681 3.122 9.681 3.122 3.80 0.405 0.405 0.405 29.190 29.190 29.190 1.013 8.903 8.903 0.618 0.000 0.000' 9.521 3.123 9.521 3.123 4.00 0.400 D.400 0.400 29.200 29.200 29.200 l.000 8.760 8.760 0.600 0.000 0,000 9.360 3.124 9.360 3.124 4.20 0.395 0.395 0.395 29.210 29.210 29.210 0.988 8.617 8.617 0.583 0.000 0.000 9.200 3.125 9.200 3.125 4.40 0.390 0.390 0.390 29.220 29.220 29.220 0.975 8.474 8.474 0.566 0.000 9.039 3.127 9.039 3.127 4.60 0.385 0.385 0.385 29.230 29.230 29.230 0.963 8.331 8.331 0,549 0.000 8.879 3.128 8.879 3.128 I

4.80 0.380 0.380 0.380 29.240 29.240 29.240 0.950 8.187 8.187 0.532 0.000 8.719 3,129 8.719 3.129 5.00 0.375 0.375 0.375 29.250 29.250 29.250 0.938 8.044 8.044 0.516 0.000 8.559 3.130 8.559 3.130 5.20 0.370 0.370 29.260 29.260 29.260 0.925 7.900 7.900 0.500 0.000 8.400 3.131 8.400 3.131 5.40 0.365 0.365 29.270 29.270 29.270 0.913 7.757 7.757 0.484 0.000 8.240 3.132 8.240 3.132 5.60 0.360 0,360 29.280 29.280 29.280 0.900 7.613 7.613 0.468 0.000 8.081 3.133 8.081 3.133 5.80 0.355 0.355 0.3 29.290 29.290 29.290 0.888 7.469 7.469 0.453 0.000 7.922 3.134 7.922 3.134 6.00 0.350 0.350 0.3 29.300 29.300 29.300 0.875 7.325 7.325 0.438 0.000 0.000 7.763 3.135 7.763 3.135 6.20 0.345 0.345 0.3 29.310 29.310 29.310 0.863 7.181 7.181 0.423 0.000 0,000 7.604 3.136 7.604 3.136

~

6.40 0.340 0.340 0.340 29.320 29.320 29.320 7.037 7.037 D.408 0.000 0,000 7.445 3.137 7.445 3.137 6.60 0.335 0.335 0.335 29.330 29.330 29.330 6.893 6.893 0.394 0.000 0.000 7.286 3.138 7.286 3.138 6.80 0.330 0.330 0.330 29.340 29.340 29.340 0.825 6.748 6,748 0.380 0.000 0.000. 7.128 3.139 7.128 3.139 7.00 0.325 0.325 0.325 29.350 29.350 29.350 0.813 6.604 6.604 0.366 0.000 0.000 6.969 3.140 6.969 3.140 7.20 0.320 0.320 0.320 29.360 29.360 29.360 0.800 6.459 6.459 0.352 0,000 0.000 6.811 3.142 6.811 3.142 7.40 0.315 0.315 0.315 29.370 29.370 29.370 0.788 6.315 6.315 0.339 0.000 0.000 6.653 3.143 6.653 3.143 7.60 0.310 0.310 0.310 29.380 29.380 29.380 0.775 6.170 6.170 0.326 0.000 0.000 6.495 3.144 6.495 3.144 7.80 0.305 0,305 0.305 29.390 29.390 29.390 0.763 6,025 6.025 0.313 0.000 0.000 ! 6.338 3.145 6.338 3.145 8.00 0.300 0.300 0,300 29.400 29.400 29.400 0.750 5.880 5.880 0.300 0.000 0.000

6.180 3,146 6.180 3.146 ml 8.20 0.295 0.295 0.295 29.410 29.410 29.410 0.738 5.735 5.735 0.288 0.000 6.023 3.147 6.023 3.147 8.40 0.290 0.290 0.290 29.420 29.420 29.420 0.725 5.590 5.590 0.276 0.000 5.865 3.148 5.865 3.148 8.60 0.285 0.285 0.285 29.430 29.430 29.430 0.713 5.445 5.445 0.264 0.000 5.708 3.149 5.708 3.149 I

8.80 0.280 0.280 0.280 29.440 29.440 29.440 5.299 5.299 0.252 0.000 0.0 5.551 3.150 5.551 3.150 9.00 0.275 0.275 0.275 29.450 29.450 29.450 5.154 5.154 0.241 0.000 O,OUl 5.394 3.151 5.394 3.151 9.20 0.270 0.270 0.270 29.460 29.460 29.460 5.008 5.008 0.230 0.000 0.00( 5.238 3.152 5.238 3.152 9.40 0.265 0.265 0.265 29.470 29.470 29.470 4.863 4.863 0.219 0.000 o.ooc 5.081 3.153 5.081 3.153 9.60 0.260 0.260 0.260 29.480 29.480 29.480 0.65( 4.717 4.717 0,208 0.000 0.00[ 4.925 3,154 4.925 3.154 9.80 0.255 0.255 0.255 29.490 29.490 29.490 0.631 4.571 4.571 0.198 0.000 4.769 3.155 4.769 3.155 10.00 10.20 10.40 10.60 10.80 0.250 0.245 0.240 0.235 0.230 0.250 0.245 0.240 0.235 0.230 0.250 ii 29.500 29.510 29.520 29.530 29.540 29.500 29.510 29.520 29.530 29.540 29.500 29.510 29.520 29.530 29.540 0.625 0.613 0.600 0.588 0.575 4.425 4.279 4.133 3.987 3.840 4.425 4.279 4.133 3.987 3.840 0.188 0.178 0.168 0.159 0.150 0.000 0.000 0.000 0.000 0.000

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0.

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4.613 4.457 4.301 4.145 3.990 3.157 3.158 3.159 3.160 3.161 4.613 4.457 4.301 4.145 3.990 3.157 3.158 3.159 3.160 3.161 11.00 0.225 0.225 0.225 29.550 29.550 29.550 0.563 3.694 3.694 0.141 0.000 0.00( 3.834 3.162 3.834 3.162 11.20 0.220 0.220 0.220 29.560 29.560 29.560 0.550 3.547 3.547 0.132 0.000 0.000 1 3.679 3.163 3.679 3.163 11.40 0.215 0.215 0.215 29.570 29.570 29.570 0.538 3.401 3.401 0.124 0.000 0.000 3.524 3.164 3.524 3.164 11.60 0.210 0.210 0.210 29.580 29.580 29.580 0.525 3.254 3.254 0.116 0.000 0.000, 3.369 3.165 3.369 3.165 11.80 0.205 0.205 0.205 29.590 29.590 29.590 0.513 3,107 3.107 0.108 0.000 0.000 i 3.215 3.166 3.215 3.166 12.00 0.200 0.200 0.200 29.600 29.600 29.600 0,500 2.960 2.960 0.100 0.000 0.000' 3.060 3.167 3.060 3.167 12.20 0:195 0.195 0.195 29.610 29.610 29.610 0.488 2.813 2.813 0.093 0.000 0.0001 2.906 3.168 2.906 3.168 12.40 0.190 0.190 0.190 29.620 29.620 29.620 2.666 2.666 0.085 0,000 2.751 3.169 2.751, 3.169 i

0.475 12.60 0.185 0.185 0.185 29.630 29.630 29.630 0.463 2.519 2.519 0.079 0.000 2.597 3.170 2.597 3.170 12.80 0.180 0.180 0.180 29.640 29.640 29.640 0.450 2.371 2.371 0.072 0.000 2.443 3.171 2.443 3.171 13.00 0.175 0.175 0.175 29.650 29.650 29.650 0.438 2.224 2.224 0.066 0.000 2.289 3.173 2.289 3.173 Page 1 of B

Attachment #4 Page 1 of 3 ETE-MP-2020-1027 Rev. 0 Report Generated on 3/14/2020 9:05:26 PM Page 22 of 27 0-,1. SOU"rnWEST FABRICATING AND \IELDING CO ..

0-61 ASME SECT. Ill 1971 WJltt WlfilcR (N&iN. of 11anufacturcr) 1972 AOOENOA-ClASS ) C\HII CLAD 17 .:, . 1. PERM,ONENT IOENTJFICATTOl MAAKltli-LOI S1RESS STll/f'IN: at VIBRD-ETOl *

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Attachment #5 Page 1 of 2 ETE-MP-2020-1027 Rev. 0 Report Generated on 3/14/2020 9:05:26 PM Page 25 of 27

- ( S e r v i c e s - 6)

From: (Services - 6)

Sent: Friday, March 13, 2020 2:17 PM To: Dom En Nuclear CT, Inc. - 4)

Cc:

Subject:

Corrosion Rate Calculation Tom, Here is the complete corrosion rate calculation.

The corrosion rate in terms of current density {1.6e-5 A/cm 2 ) is from EPRI Report "Predictive Model for Galvanic Corrosion," Report Number 1008184, December 2004.

Table 4-2 (Page 4-7}

Table4*2 Ta,fel Parameters Ta.ken from PolarlzatJon Curves ln Sea Water Chemistry Material r. T< l,o:f E.,.

{mV/deeade) (mV/decade} (A/cm') (mV)

Cart:lon Steel 60 110 1.6E-5 -000 31 SL Stainless Steel 13-0 2£0 6.3E-7 +10 Admiralty Brass 30 35 2.5E-6 -245 Copper 50 110 2.0E-5 -220 Titanium 410 680 1.BE-7 +650 AL6XN 280 730 6.3E-7 +210 00:10Cw'Ni 60 85 tBE-5 -250 The polarization plots arc presented in Appendix: A. The plots for titanium and AL6XN were very difficult In interpret, h.,wing a "noisy" tnu..-c with no dear minimum. TI1is was improVL'CI slightly by **sm£mthing" the mcasurcmcm results by an averaging ttx:hniquc for either seven or thirtet*n adjacent points, applied through the result seL Even so, the results for thc.'>c mc1als gi\'cn in Table 4<2 may be subject to large experimental cm1rs. Interpretation of these plots is gencrnlly difficult with several cathodic processes taking place and wilh the possibility that n.'tluction of 0: may be mass-tra°'"for controllt.'CI. The solution was sparg<..'CI with air, and the vessel was well stirrcdlagit11ted to try and minimize mass transfer effects. out lhc cflicicm:y of this procedure cannot be quantified.

Attachment #5 Page 2 of 2 ETE-MP-2020-1027 Rev. 0 Report Generated on 3/14/2020 9:05:26 PM Page 26 of 27 1.6e-s(~)*27.92 (_g__)

cm eq-CR 5.88e-10 cm sec Convert to in/30 days:

1

=5.88e-10 cm* in

3600 sec* 24 hr *30 day 0.0006 sec 2.54 cm hr day month in 30 days Dominion Energy Innsbrook Technical Center Phone: 804-273-4322 Tie-Line: 8-730-4322 2

Attachment #6 Page 1 of 1 ETE-MP-2020-1027 Rev. 0 Report Generated on 3/14/2020 9:05:26 PM Page 27 of 27

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Serial No.20-103 Docket No. 50-423 ATTACHMENT 3 SCHEMATIC OF ASME BRANCH REINFORCEMENT WELD DETAILS MILLSTONE POWER STATION UNIT 3 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

Serial No.20-103 Docket No. 50-423 Attachment 3, Page 1 of 1 FIG. ND-4244(d)-1 SOME ACCEPTABLE TYPES OF WELDED NOZZLES, AND BRANCH AND PIPING CONNECTIONS - For Definition of Symbols, See ND-3352.4(d)

v t e Letter Sequence Request
EPID:L-2020-LLR-0038, Alternative Request IR-4-03 for Use of an Alternative Non-Code Methodology to Demonstrate Structural Integrity of Class 3 Moderate-Energy Piping (Approved, Closed)
Initiation Request Acceptance... Administration Questions 15 March 2020 Answers 16 March 2020 16 March 2020 Results Approval Other: ML20076J372
MONTHYEAR2020-03-15 [Table View]

ML20076A549

Text

References:

2. Applicable Code Edition and Addenda

3. Applicable Code Requirements

4. Reason for Request

5. Proposed Alternative and Basis for Use

Description:

Conclusion:

6. Duration of Proposed Alternative

7. Precedents

Title:

Description:

Description:

Description:

Subject:

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