ML11234A077

Relief Request RR-04-12 for the Temporary Non-Code Compliant Condition of the Class 3 Service Water System 10 Inch Emergency Diesel Generator Supply Piping Flange

ML11234A077
Person / Time
Site:	Millstone
Issue date:	08/19/2011
From:	Price J Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML11234A077 (193)

Text

Dominion Nudear Connecticut, Inc.

5000 Dominion Boulevard, Glen Allen, Virginia 23060 "om inion° Web Address: www.dom.com August 19, 2011 U.S. Nuclear Regulatory Commission Serial No.11-476 Attention: Document Control Desk NLOSNVEB RO Washington, DC 20555 Docket No. 50-336 License No. DPR-65 DOMINION NUCLEAR CONNECTICUT. INC.

MILLSTONE POWER STATION UNIT 2 RELIEF REQUEST RR-04-12 FOR THE TEMPORARY NON-CODE COMPLIANT CONDITION OF THE CLASS 3 SERVICE WATER SYSTEM 10 INCH EMERGENCY DIESEL GENERATOR SUPPLY PIPING FLANGE Pursuant to IOCFR50.55a(a)(3)(ii), Dominion Nuclear Connecticut, Inc. (DNC) requests relief from the Section XI requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. This request is based on the hardship of performing required ASME code repair/replacement activities to a piping flange in the 10 inch service water (SW) supply line to the Facility 1 emergency diesel generator (EDG) heat exchangers which has developed a through-wall leak. In accordance with 10CFR50.55a(g)(1), safety-related piping must meet the requirements applicable to components which are classified as ASME Code Class 3.

Options for a code repair include shutting down to replace the piping flange or performing the same repair online. Given the limited risk associated with the present condition, both of these options are considered a hardship without a compensating increase in the level of quality and safety. An alternative of continued operation with compensatory actions is proposed until the flange is replaced at the next refueling outage. Attachment 1 to this letter describes the temporary compensatory actions taken by DNC and the technical basis for the proposed relief request for this 10 inch moderate energy SW flange. A permanent code replacement for the identified 10 inch SW flange will be completed no later than the end of the next refueling outage currently scheduled to start in October 2012.

If you have any questions regarding this submittal, please contact Wanda Craft at (804) 273-4687.

Sincerely, p* '-.- Q,-'

rice - , -

Vic esident -Nuclear Engineering O \

A01+1

Serial No.11-476 Docket Nos, 50-336 Relief Request RR-04-12 Page 2 of 2 Attachments:

1. Relief Request RR-04-12 for the Temporary Non-Code Compliant Condition of the Class 3 Service Water System 10 Inch Emergency Diesel Generator Supply Piping Flange

2. Excerpts From Pipe Stress Analysis Calculation Number MP58B-001 38EM, Revision 4, Addendum B, Service Water Supply to Diesel Engine Coolers - Problem 118

3. ETE-CME-2011-1005, Structural Integrity and System Performance Evaluation of Degraded Flange in "A" Service Water Pipe to EDG Spool SK-2952 Commiiments made in this letter:

1. Replace the downstream flange on Spool Piece 2952 (Facility I SW supply piping to the Facility 1 EDG HXs) no later than the end of the next refueling outage scheduled for October 2012.

2. Leakage monitoring will be performed. UT monitoring will be performed on an approximate 30-day interval. UT examination of the pipe flange, as was done to identify the degraded area, will be done on a monthly basis to track the progression of the corrosion damage.

cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 C. J. Sanders Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop O-8B3 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

Serial No.11-476 Relief Request RR-04-12 Docket No. 50-336 ATTACHMENT 1 RELIEF REQUEST RR-04-12 FOR THE TEMPORARY NON-CODE COMPLIANT CONDITION OF THE CLASS 3 SERVICE WATER SYSTEM 10 INCH EMERGENCY DIESEL GENERATOR SUPPLY PIPING FLANGE DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

Serial No.11-476 Docket No. 50-336 Relief Request RR-04-12 Attachment 1, Page 1 of 9 RELIEF REQUEST RR-04-12 Relief Request In Accordance with 10 CFR50.55a(a)(3)(ii)

-- Code Repair Hardship/No Compensating Increase in Safety --

1.0 ASME Code Component(s) Affected ASME Code Class: Code Class 3

Reference:

ASME Section XI, IWA-4000

Description:

Repair/Replacement Activities Component: Service Water (SW) System 10 inch Light Weight Slip-on Flange Material Coated Carbon Steel

2.0 Applicable Code Edition and Addenda

Millstone Power Station Unit 2 (MPS2) is currently in the fourth 10-year inservice inspection (ISI) interval, which began on April 1, 2010. American Society of Mechanical Engineers (ASME)Section XI, 2004 Edition, No Addenda (Reference 8.1) applies to the ISI program and is used as the primary ASME code edition for Section XI repair/replacement activities. The SW system piping design code (code of construction) is ANSI B31.1, 1967 Edition through the summer of 1973 Addendum (Reference 8.4).

3.0 Applicable Code Requirement ASME Code Section XI, 2004 Edition, No Addenda, Article IWA-4000, Repair/Replacement Activities.

4.0 Reason For The Request On August 17, 2011, an operator on rounds observed a yellow salty stain on the floor near the spent fuel pool purification pumps in the auxiliary building (Reference 8.5). There was water and a salt build-up on the I-beam above the stain on the floor. The operator found water dripping at a rate of 10 drops per minute coming from the "A" SW header to the "A" emergency diesel generator (EDG), Water was observed dripping from the outlet side flange on spool SK2952. The leak was confirmed to be on the flange body.

Serial No.11-476 Docket No. 50-336 Relief Request RR-04-12 Attachment 1, Page 2 of 9 Ultrasonic test (UT) examinations determined the area of degradation on the flange is localized and is currently contained in a radial alignment between two of the twelve flange bolts.

Enclosure 1 to this attachment contains UT inspection results for the observed flaw area of the flange.

Options for a code repair include shutting down to replace the piping flange or performing the same repair online. Given the limited risk associated with the present condition, both of these options are considered a hardship without a compensating increase in the level of quality and safety. In the case of an online repair, it would require entry into abnormal operating procedures (i.e., OP 2326C, Off-Normal Service Water System Operations) including the following actions and/or conditions to effect a Code repair.

1. Ensure that SW temperature is less than 58°F (currently SW

-temperature is approximately 71'F and normally remains above 58'F well into October).

2. Align vital switchgear room coolers and chillers to the B train (or establish compensatory cooling).

3. Disable the A EDG.

4. Align the swing reactor building closed cooling water (RBCCW) heat exchanger (HX) to the B train on the SW side and the A train on the RBCCW side and ensure swing RBCCW HX can provide adequate A train cooling with SW flow less than 1500 gpm.

5. Align the swing SW pump mechanically to the B train and electrically to the A train and start the pump.

6. Align two turbine building component cooling water (TBCCW) HXs to the B train on the SW side (this may require a reactor down power to provide sufficient cooling).

Once in this configuration, completion of the work activities for the spool replacement within the remaining time of the limiting condition for operation of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> will not be possible. Therefore a transition to Mode 5 (a hardship) would be required to perform this repair. Further, there is no compensating increase in plant safety by performing the repair during the operating cycle.

Serial No.11-476 Docket No. 50-336 Relief Request RR-04-12 Attachment 1, Page 3 of 9 This temporary condition of the leaking 10 inch light weight slip on flange is not in compliance with ASME Section XI, 2004 Edition, IWA-4000, nor does it meet the accepted analysis methods contained in NRC Generic Letter (GL) 90-05 (Reference 8.2). Additionally, Code Case N-513-3 (Reference 8.3) is not applicable for use in structural evaluations because the degradation is in a component (10 inch light weight slip-on flange) which is specifically excluded from the scope of the code case. However, the current pipe stress analysis of record has been reviewed and the pipe stress levels adjacent to the flange (for the non-degraded condition) have been determined to be less than 10% of applicable Code allowables. The current corrosion damage to the flange is characterized through UT evaluations as limited (contained radially between two of twelve bolt holes). Because the observed damage is limited, it is considered that adequate margin is available to accommodate the corrosion that is anticipated to occur during the remaining 14 months of operation until the next refueling outage.

5.0 Proposed Alternative and Basis for Use 5.1 Flaw Characterization - Based on the UT results of the current condition and experience from other similar lining failures discovered during normal inspection on carbon steel piping components in SW, the flaw is characterized to be a localized area corrosion rather than a crack-like flaw.

Dominion procedure ER-AA-NDE-UT-701 (included as Enclosure 2 to Attachment 1) contains additional details on the nondestructive examination process used.

The examination process used identified symptoms of localized area corrosion which is consistent with prior experience from other lining failures on this system. The flange in question was not designed to permit a complete volumetric examination once installed. However, the UT examination process used is capable of identifying localized area corrosion in the flange. There is no history of crack-like flaws in this system and it is not considered credible that such a flaw exists in the small area that did not receive a volumetric examination.

The coating on SW spool SK2952, where the leakage is occurring on the outlet flange, is inspected every other refueling cycle to ensure that the pressure boundary of the SW pipe remains intact and that the tube sheets of safety-related heat exchangers (HXs) do not become clogged by coating material. This every other refueling outage inspection is based upon the inspection of one train of SW every outage. This inspection scheme has been used for over ten years. Numerous defects have been detected by these inspections and repaired before a through-wall leak occurred.

Serial No.11-476 Docket No. 50-336 Relief Request RR-04-12 Attachment 1, Page 4 of 9 Galvanic Corrosion Mechanism The typical corrosion encountered in this carbon steel lined pipe, used for MPS2 SW, comes from a break or perforation (holiday) in the coating or lining. This most often is a result of mechanical assembly, disassembly or handling of the spool pieces.

The flaws in the coating most often occur in or around the inner diameter (ID) corners of the flanged joints. Once the coating is damaged, seawater gets into the coating and eventually through to the carbon steel. Once the seawater electrolyte makes contact with the carbon steel, galvanic corrosion occurs. The carbon steel is anodic to the surrounding coated carbon steel and any uncoated alloy surfaces. This creates an electrical current and metal ions are released into solution creating a cavity. The cavity grows from the initial point outwards in a radial shape in all directions and takes on the concave appearance, resembling what could be pictured if the carbon steel was scooped out with an ice cream scoop.

As the cavity grows, this electrical current creates a charged electrical field that actually cathodically protects the surrounding area at the sacrifice of the growing anodically charged cavity.

When the fit-up line between the slip-on flange ID and pipe outer diameter (OD) is exposed, this narrow space is flooded and exposed to seawater which then becomes subject to corrosion. However, the geometry of this gap is not favorable for the mass exchange (movement of negatively charged chloride and free oxygen atoms in and positively charged metal ions out) required for rapid corrosion. The free oxygen within the gap is quickly depleted and the rate of corrosion diminishes to a substantially lower amount compared to that in the active cavity. Thus, significant corrosion of the flange hub or attachment weld beyond the active cavity is not expected.

Starting in 2005, sections of the piping have been replaced with super austenitic stainless steel, AL6XN, designed for seawater service. Dominion has planned a programmatic replacement of the safety-related portion of the SW piping. Spool SK2952 is scheduled for replacement in the next refueling outage (fall 2012).

The coating on the outlet flange was visually inspected by a qualified linings engineer during 2R19 (October 2009). Lining engineers receive specific training in the inspection of linings to recognize coating defects, The epoxy lining on the flange face and ID of the pipe had no evidence of damage at that time. A typical refueling outage inspection has found 10 to 15 areas where the coating has failed and some corrosion has occurred. These

Serial No.11-476 Docket No. 50-336 Relief Request RR-04-12 Attachment 1, Page 5 of 9 areas are repaired during the outage. Based upon past experience, more areas of coating damage and corrosion will be found in the next refueling outage, but the chances of another leak are small.

It is probable that the lining on the leaking flange was damaged when re-installing the upstream spool. However, a conservative corrosion rate was chosen by assuming the lining defect initiated 11 months ago (one-half the duration since the last inspection occurred) and that the observed damage has occurred in the past 11 months. Based upon UT measurements, the damaged area is about 3 inches long on the ID of the flange (which is approximately 34 inches in circumference and 3/4 inch thick). Past experience has shown that the corrosion from this type of lining defect grows radially from a point on the ID of the flange face. Hence, the 3 inches represents twice the actual growth. Therefore the corrosion rate can be conservatively estimated as 1.5 inches/1I months = 0.136 inches/month.

The extent of the damage to this outlet flange is limited to the one area noted. UT measurements around the circumference of the flange did not identify any similar areas.

5.2 Structural Integrity - Per MPS2 Technical Requirements Manual (TRM) 3.4.10, the structural integrity of an ASME component is determined in accordance with either the original construction code or the ASME Section X1 Code, approved code cases or regulatory-approved methods of evaluation. No NRC approved methodology could be identified (i.e., GL 90-05 and Code Case N-513-3) applicable to flanges. Engineering Technical Evaluation ETE-CME-2011-1005, Revision 0 (Reference 8.5) is a structural integrity assessment of the degraded flange. Pipe stress levels for the Code equations for the adjoining pipe are less than 10% of their associated allowables. The area of degradation is currently confined to an area radially aligned between two bolt holes on one carbon steel flange. The area of degradation is assumed to be as large as 33% of the flange circumference (or the area between four bolt holes of a twelve bolt hole pattern) for the purpose of the structural integrity assessment. Based on experience with other similar situations (seawater/exposed carbon steel), this magnitude of corrosion is larger than the magnitude currently predicted by Materials Engineering personnel. Materials Engineering predicts a radial flaw size of approximately 7 inches at the end of the current operating cycle (i.e., 6.8 inches = 3 inches + 2 x 0.136 inches/month x 14 months, this is approximately 22% of the inside circumference = 7/(10 x Tr")). Since the limiting case assumes that a 33% maximum wall loss is experienced (to be confirmed periodically by UT) and the adjoining pipe element has 90%

margin in the stress equations, stiructural integrity of the flange joint will be maintained for the loading conditions (i.e., dead load, thermal and seismic).

The flaw is not crack-like and thus will remain stable under the postulated

Serial No.11-476 Docket No. 50-336 Relief Request RR-04-12 Attachment 1, Page 6 of 9 design loading conditions since a large structural capability margin exists in the worst case degraded flange.

5.3 Flow Margin - SW flow loss from this leak location will not adversely affect the capability of the SW system to provide adequate cooling to the EDG HXs and to the other essential safety-related HXs. A leakage limit of 1 gallon per minute (gpm) is applied as the maximum acceptable leakage rate (currently the leakage rate is approximately 10 drops/min). A detailed system hydraulic analysis has been performed (Reference 8.6). This analysis demonstrates that a margin of at least 50 times is available (i.e., >

50 gpm can be tolerated and all essential safety-related HXs receive adequate SW flow for the limiting accident condition).

5.4 Spray Concerns - A walkdown has been performed by System Engineering. The walkdown included components within an approximate 30 foot envelope of the current leak. Primary water system components are located within this area including the non-safety related refueling water purification pumps P14A & B, safety related spent fuel pool cooling pumps P13A &B and heat exchangers X20A & B, and'associated piping.

Additionally, the non-safety related 480V Motor Control Center.Bus (MCC-B31A) is located approximately 25 feet from the leak. Due to the existing leak location on the flange, the most likely spray direction is toward the concrete building wall at the -5 elevation of the auxiliary building located east of the leak. This wall is approximately 1 foot from the leak location.

There are no components between the east wall and the leak location (the most probable spray direction) and no active component within a 15 foot envelope. The entire inspected area is further protected by a concrete block house on the south side (4 feet from the leak location). All active components are further protected from spray. due to physical obstructions (walls, piping, hangers, etc.). Based on this review, there are no spray concerns affecting any area components for the worst projected leak.

5.5 Flooding - The flooding from an assumed 2 gpm leak (this is two times the action level of I gpm and allows for a leakage rate increase over the 30-day mission time) would result in a total leak volume of approximately 86,400 gallons. This volume is based on a 30-day mission time. The 30-day mission time is based on the GSI-191 containment emergency sump strainer design that has a 30-day mission time. Cooling over the 30-day mission time is provided by SW.

As a compensatory measure, leakage will be collected and directed to appropriate drains during normal plant operation, facilitating the ability to

Serial No.11-476 Docket No. 50-336 Relief Request RR-04-12 Attachment 1, Page 7 of 9 monitor for degradation. These drains may not be available/functional or credited following a design basis accident.

If the compensatory drain collection system is unavailable/nonfunctional, then operators will be alerted to any pooling of water. in the auxiliary building basement by existing auxiliary building sump system indication. A water volume of approximately 120,000 gallons can be accommodated by the auxiliary building basement (Reference 8.7) without impacting safety-related equipment. Therefore, the flooding for 30 days can be accommodated without operator action.

5.6 Extent of Condition - An on-going capital project has replaced much of the carbon steel lined/coated carbon steel piping. However, many similar coated carbon steel flange joints (to the current leaking joint) remain in service. Recent experience (within the last ten years) with the SW system inspections reveals that through-wall coated component failures are rare.

Since the initiator for the current condition is presumed to be damage to the coating system upon reinstallation into the system, no other coated carbon steel component through-wall leaks are expected in the current operating cycle. No other SW system flange leaks are present in the MPS2 SW system. Because the degradation of similar coated carbon steel components has been previously evaluated and is the impetus for the ongoing piping replacement project, no scope expansion to examine additional components is warranted based on the identified degradation of the subject flange. Operators on rounds and system engineering walkdowns will continue to identify future instances of this type in a timely manner, just as this one was discovered.

5.7 Compensatory Monitoring Plan - Leakage monitoring will be performed.

UT monitoring will be performed on an approximate 30-day interval. UT examination of the pipe flange, as was done to identify the degraded area, will be done on a monthly basis to track the progression of the corrosion damage. The estimated -0.150" increase in the damaged area between examinations should be detected. Monitoring on a more frequent basis would not lend itself to revealing the very small changes which would be expected to occur between frequent examinations and any variability in the measurements may under represent or over represent the actual increase in the damaged area over time. An approximate 30 day interval is adequate and sufficient to detect increases in the damaged area in a timely manner based on the nature of degradation mechanism. Changes in the area of corrosion will be assessed by Engineering on the presumed corrosion rate and for impact to the structural integrity of the affected flange / flange joint.

Leakage rate will be trended by System Engineering on an approximate weekly basis. Operations will qualitatively monitor leakage once per shift. If

Serial No.11-476 Docket No. 50-336 Relief Request RR-04-12 Attachment 1, Page 8 of 9 any of the limits outlined within the relief request are challenged (e.g., the leakage rate of 1 gpm or the flaw size (33% of the flange inside circumference)), the A Train SW system will be declared inoperable.

5,8 Conclusion - Although the structural integrity of the leaking flange cannot be demonstrated in accordance with a regulatory-approved methodology, it is concluded the integrity and functional requirements of the flange will be maintained. Thus, SW will continue to be capable of providing required cooling water flow to meet the required cooling loads including the EDG HXs. There will be no adverse impact on neighboring equipment due to either spray or flooding. DNC will implement the compensatory monitoring plan above to ensure any growth of the flaw is identified and assessed for its impact on structural integrity.

6.0 Duration of Proposed Alternative The affected spool piece was already scheduled to be replaced in October 2012 during 2R21. Therefore, the duration of the proposed alternative is requested until October 2012 or until the limits described above are challenged.

7.0 Precedents None 8.0 References 8.1 ASME Code Section Xl, Division 1, 2004 Edition (No Addenda) 8.2 NRC Generic Letter GL 90-05, "Guidelines for Performing Temporary Non-

-Code Repair of ASME Code Class 1, 2, and 3 Piping," June 15, 1990 8.3 Code Case N-513-3, "Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping," Section Xl, Division 1, January 26, 2009 8.4 American National Standards Institute (ANSI) B31.1, Power Piping Code, 1967 Edition through the Summer 1973 Addendum (Note: The MPS2 Pipe Stress Analysis Criteria Document allows the use of ASME II1, 1974 Edition to demonstrate pipe stress acceptability) 8.5 Condition Report CR 438193, Possible Through Hole Leak in the "A" Service Water Header To The "A" EDG

Serial No,11-476 Docket No. 50-336 Relief Request RR-04-12 Attachment 1, Page 9 of 9 8.6 Engineering Technical Evaluation ETE-CME-2011-1005, Revision 0, Structural Integrity and System Performance Evaluation of Degraded Flange in "A" Service Water Line to EDG Spool SK-2952 8.7 Millstone Power Station Unit 2, Probabilistic Risk Assessment Model Notebook, Part III PRA Model Development, Volume IF.1, Internal Flooding Analysis, Partitioning and Source Identification *& Characterization, Revision 0

Serial No.11-476 Relief Request RR-04-12 Docket No. 50-336 Enclosure I (of Attachment 1)

Ultrasonic Test Results DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

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ri .. Date 08/17/2011 Reviewer (sign) Si A4, N/_. ... L.el Date _1-/1 ANVAN'II If Required (Sign) NIA, Date N/A..

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AM'I / Date -N/A ER-AA-NDE-UJT-70 I

Serial No.11-476 Relief Request RR-04-12 Docket No. 50-336 Enclosure 2 (of Attachment 1)

Dominion Procedure MP-PROC-000-ER-AA-NDE-UT-701, "Nondestructive Examination Procedure"

W01h Nuclear5.1Fleet 7ErOD Nondestructive Examination Procedure

Title:

Ultrasonic Thickness Measurement Procedure Procedure Number Revision Number NPQR Number ER-AA-NDE-UT-701 5 ER-AA-NDE-UT-701 -NPQR, Revision 0 Approval signatures on file with approval documentation for this procedure revision.

R. T. Stack 02/26/2011 Independent Level III Review Date K. J. Hacker 02/26/2011 Corporate Level III Approval Date J.W. Niemerg 02126/2011 ANII Date Level of Use: Reference

DOMINION ER-AA-NDE-UT-701 Revision 5 Page: 2 of 11 Record of Revision Rev. Page # Paragraph# Summary of Revision 0 All All New issue as Dominion Nuclear Fleet Procedure.

1 4 2.3 Added "couplant" 4 5.1.1 Added the option for using other gauges/scopes with Level III approval.

5 5.2.4 Deleted requirements for using dual element transducers for measuring through coatings.

6 6.2.2 Deleted requirements for using the multi-echo technique.

6 7.1 Deleted reference to multi-echo technique.

6 7.2 Deleted limitation of single-echo technique for non-coated surfaces.

6 7.3 Deleted (multi-echo requirements) 6 7.3.1 Deleted (multi-echo requirements) 7 8.5 Deleted (multi-echo requirements) 8 9.8 Added new paragraph for guidance for evaluating thickness results for coated surfaces.

2 4 5.1 Added new paragraph for'equipment to comply with ER-AA-NDE-130 requirements, 5 5.6.1 Provide allowance for using the component being examined as the reference standard for calibration.

6 8.4 Clarified the guidance for selecting the calibration points for calibration.

10 10.2 Added new paragraph for data records to be processed in accordance with ER-AA-NDE-140 requirements.

3 4 3.1 Updated reference to the 2004 Edition.

4 4 1.1 Updated the type of UT equipment displays to include A-scan and direct thickness readout.

4 2.1 Reduced the minimum thickness range from 0.050" to 0.025".

Allowed the examination of components outside the specified range provided demonstrated through the calibration process and Level IlI approval.

4 4.1 Clarified the Level 11-L qualifications by adding straight beam qualification.

5 5.2.1 Identified the ultrasonic instrument requirements based on display.

5 5.3.1 Increased the upper range of search unit frequency from 10 MHz to 20 MHz to address thinner limits of the procedure, 5 5.3.4 Included the use of delay lines for high temperature or improved near surface resolution is required.

6 5.7.1 Changed to require the use of temperature measurements only for high temperature components.

8 8.7 Changed to require the use of temperature measurements only for high temperature components.

9 9.7 Included additional guidance for addressing areas of laminations with lower frequency search units.

DOMINION ER-AA-NDE-UT-701 Revision 5 Page: 3 of 11 Rev. I Pace # Paraqraph # Summary of Revision 5 6 5.3.2 Modified the search unit size to "should" and added criteria for resolution capabilities when using smaller search units.

DOMINION ER-AA-NDE-UT-701 Revision 5 Page: 4 of 11 Table of Contents 1 .0 P u rp os e ........................................................................................................................... 5 2 .0 Sc o p e .............................................................................................................................. 5 3.0 Reference Docum ents ................................................................................................. 5 4.0 Personnel Qualifications ............................................................................................. 5 5.0 Equipm ent and Material Requirements ...................................................................... 5 6.0 Examination Requirements ........................................................................................ 7 7.0 Thickness Measurement Technique ........................................................................... 7 8 .0 C a lib ra tio n ....................................................................................................................... 7 9.0 Exam ination ..................................................................................................................... 9 10.0 Data Recording .............................................................................................................. 10

DOMINION ER-AA-NDE-UT-701 Revision 5 Page: 5 of 11 1.0 Purpose 1.1 The purpose of this procedure is to provide a process for the calibration and application of straight beam ultrasonic techniques for performing thickness measurements utilizing equipment with A-scan display or direct thickness readout with A-scan displays.

2.0 Scope 2.1 This procedure is applicable to the manual, pulse echo, straight-beam, longitudinal wave, contact ultrasonic technique for performing thickness measurements of ferritic or austenitic tubing, piping, vessels, and components in the nominal thickness range of 0.025 to 20.00 inches. Thickness measurements may be taken outside of the specified nominal thickness ranges provided the equipment capabilities is demonstrated through the calibration process and Level III approval is documented on the examination record.

2.2 Examinations may be conducted from the inside (ID) or outside (OD) surfaces.

2.3 The temperature of the component being examined should not exceed the manufacturer's maximum temperature for the search unit or couplant being used.

3.0 Reference Documents 3.1 ASME Boiler & Pressure Vessel Code,Section V, 1989 Edition through the 2004 Edition, Article 23, SE-797, Standard Practice for Measuring Thickness by Manual Ultrasonic Pulse-echo Contact Method.

4.0 Personnel Qualifications 4.1 The examiner shall be certified to, Level 11-L (limited to straight beam or thickness measurements), Level II, or Level III in the ultrasonic method in accordance with Dominion's written certification practice. The examiner shall be responsible for and shall accept the results of the examination.

4.2 An assistant qualified to at least a Level I in the ultrasonic method in accordance with Dominion's written certification practice may assist the examiner. The Level I shall work under the direct supervision of the examiner and shall not evaluate or accept the examination results.

5.0 Equipment and Material Requirements 5.1 All equipment and materials used to implement this procedure shall comply with the requirements of ER-AA-NDE-130, "Storage and Control of Calibrated NDE Equipment, Calibration Standards, and Consumable NDE Materials".

DOMINION ER-AA-NDE-UT-701 Revision 5 Page: 6 of 11 5.2 Ultrasonic Instruments 5.2.1 Approved pulse echo ultrasonic instruments shall provide either a direct A-scan display or a combination of an A-scan display with direct thickness readout. An acceptable calibration in accordance with this procedure demonstrates acceptable ultrasonic instrument selection for use.

5.3 Search Units 5.3.1 Search units with a nominal central frequency in the range of 5.0 to 20.0 MHz should be selected for performing thickness measurements.

For thicknesses 0.050" and less the search unit frequency shall be 10.0 MHz or higher. Other frequencies between 1.0 and 5.0 MHz may be used when their properties (i.e., sensitivity, penetration, resolution, etc.)

provide superior results.

5.3.2 The search unit active element size should be between 0.10" and 1.00" square inches, however smaller search units may be used provided the resolution capabilities of 5.3.5 are maintained.

5.3.3 The search unit elements shall be round.

5.3.4 Either single or dual element search units may be used. Delay lines may be used for high temperature components or when improved near surface resolution is required.

5,3.5 Proper search unit selection (size, shape, configuration, frequency) will be indicated by the systems ability to properly display and resolve the calibration standard's reflections throughout the range of the expected thickness measurements for the component to be examined.

5.4 Cabling 5.4.1 The interconnecting cable between the search unit and the ultrasonic instrument shall be RG-58 or RG-174 type coaxial cable (or equivalent) with lengths not to exceed 20 feet.

5.5 Couplant 5.5.1 A suitable liquid couplant medium shall be applied to the examination surface for the examination. The couplant shall be approved for use at the site prior to use. The same couplant used for calibration shall be used to perform the examination.

DOMINION ER-AA-NDE-UT-701 Revision 5 Page: 7 of 11 5.6 Reference Blocks 5.6.1 Reference blocks used for screen distance calibration and verification shall be of the same material as the component material being examined (e.g. carbon steel or stainless steel). As an alternative, the component being examined may be used for calibration. The reference block or component used for calibration must be of known thickness to allow for accurate calibration.

5.7 Thermometer 5.7.1 When required (high temperature components > 1250 F), a calibrated surface thermometer shall be used to document the surface temperature of the reference block and component prior to the examination.

6.0 Examination Requirements 6.1 Examination Area 6.1.1 The extent of the area to be examined and the criteria, by which the ultrasonic measurements and part acceptability will be evaluated, shall be determined by the parties requesting that the examination be performed.

6.2 Surface Condition Requirements 6.2.1 The examination surface shall be free of irregularities, loose material, or loose coatings which interfere with the ultrasonic wave transmission.

Areas where ultrasonic contact is inadequate shall be documented as limitations.

7.0 Thickness Measurement Technique I

7.1 Thickness measurements shall be taken using the single echo measurement technique.

7.2 The single echo technique measures the total thickness of the part using a single backwall reflection. This measurement includes any coating which may be present on the surface, leading to an error in the actual base material thickness, 8.0 Calibration 8.1 Calibration shall include the complete UT system. Any change in search units, couplant, cables, instruments, or any other part of the system shall be cause for calibration verification.

DOMINION ER-AA-NDE-UT-701 Revision 5 Page: 8 of 11 8.2 The calibration shall be performed with a reference block meeting the requirements of section 5.6.

8.3 System setup and calibration (zero, velocity, gain, time base, etc.) shall be performed in accordance with the operating manual for the ultrasonic instrument being used for the examination based upon the selected parameters of the examination (i.e., measurement technique, material, thickness ranges, search units, etc.).

8.4 The calibration shall utilize two points of known thickness. The calibration points may be single backwall reflections or backwall multiples of known thicknesses.

When available, the calibration points should be equal to or greater than the nominal thickness being examined and a thickness less than the nominal thickness being examined.

8.5 Upon completion of the system setup and calibration, couple the search unit to each of the thickness steps of the reference block used for calibration and verify that the readings are within +/-0.002 inches of the as-built thickness dimension.

8.6 Calibration Verification 8.6.1 System calibration shall be checked using the appropriate reference block. Thickness reading of the calibration points shall be recorded during the initial calibration and shall be verified at the following intervals:.

8.6.1.1 At the start and finish of each examination; 8.6.1.2 With any change in examination personnel; 8.6.1.3 Whenever the instrument has been turned off and then turned on; 8.6.1.4 When there is a change in search unit, cable, or couplant; 8.6.1.5 At intervals not to exceed four hours; 8.6.1.6 Whenever the validity of the calibration is in doubt.

8.6.2 If any calibration thickness point changes by more than 0.005 inches, the following shall be performed:

8.6.2.1 Void all examinations referring to the calibration in question and performed after the last valid calibration check; 8.6.2.2 Conduct a new calibration;

DOMINION ER-AA-NDE-UT-701 Revision 5 Page: 9 of 11 8.6.2.3 Reexamine all areas for which the examinations have been voided, 8.7 For thickness measurements on high temperature components (2: 1250 F) the examination surface shall be within 25' F of the reference block used for calibration. The thermometer identification and surface temperatures shall be documented on the data sheets.

9.0 Examination 9,1 The examination shall be performed using a 100 percent scan, partial scan, or spot check scanning technique. The type of scan required for each component shall be defined by the parties requesting that the examination be performed. The types of scans are defined as follows:

9.1.1 100 Percent Scan - This examination will encompass the complete component. It is a detection, as well as a measuring technique, and should be utilized to detect the thickest and thinnest areas or when encountering inclusions, laminations, or rapidly changing thickness (i.e.,

erosion/corrosion).

9.1.2 Partial Scan - This examination covers only a percentage of the component being examined. The percentage should be based on the requirements of the examination. This technique should not be utilized if finding the thickest or thinnest area of the component is required.

9.1.3 Spot Check - This examination is a point-to-point technique which measures the thickness of the component at predetermined grid locations. It should not be utilized to detect the thickest or thinnest area of the component being examined.

9.2 Thickness readings should be taken using similar couplant thickness and search unit pressure as used for the calibration.

9.3 For dual element search units ensure that the acoustic barrier between the search unit elements is aligned perpendicular to the axis of the pipe to eliminate the effects of the curvature on the UT measurements, 9.4 Thickness readings shall be recorded as required (manually or data logger/recorder).

9.5 The thickness readings taken during an examination should be reviewed at the conclusion of the examination to ensure that no unusual readings exist and that the examination is complete. If there are any erroneous or missing readings, those areas should be reexamined to ensure accurate examination results.

DOMINION ER-AA-NDE-UT-701 Revision 5 Page: 10 of 11 9.6 Where available, the digital readout should be utilized as the primary source for thickness readings. The A-Scan display should be monitored to ensure that thickness readings taken are 'true" readings and not the result of couplant readings, inclusions, laminations, etc.

9.7 If inclusions or laminations are encountered, the area should be scanned and marked to properly bound the region. The depth(s) of the inclusion(s) or lamination(s) should also be recorded and documented, as necessary. When areas of laminations are identified, the area of lamination should be examined with a lower frequency search unit to reduce the limited area examined. Lower frequency search units will often penetrate thin/tight laminations due to the increased penetrating power of the longer wave length.

9.8 For components examined through coatings, the coating thickness will cause a slight increase in the recorded thickness from the actual thickness of the component. Although this increase is small, coating with reported thicknesses near the minimum wall thickness (minimum wall +0.015") should be evaluated to determine ifthe coating should be removed and the actual thickness verified.

9.9 Upon completion of the examination the excess couplant shall be removed.

Supplies and equipment shall also be removed from the examination area.

10.0 Data Recording 10.1 Calibration and examination data shall be recorded on data sheets and as a minimum shall include the following:

10.1.1 Calibration sheet identification.

10.1.2 Names and certification levels of examination personnel.

10.1.3 Examination procedure number and revision.

10.1.4 Reference block identification.

10.1.5 Ultrasonic instrument serial number, manufacturer, and model identification.

10.1.6 Ultrasonic instrument settings.

10.1.7 Search unit manufacturer, model, and manufacturer's serial number.

10.1.8 Search unit nominal frequency, size, shape, and number of elements.

10.1.9 Special search units, wedges, shoe type, or saddle's identification, delay line, if used.

10.1.10 Search unit cable type, length, and number of intermediate connectors.

DOMINION ER-AA-NDE-UT-701 Revision 5 Page: 11 of 11 10.1.11 Times and dates of initial calibration and subsequent calibration checks including the thickness measurements of the calibration points.

10.1.12 Signal response amplitudes and sweep positions obtained from the calibration reflectors.

10.1.13 Couplant type and batch number.

10.1.14 Identification and location of the component scanned.

10.1.15 Surface from which the examination is conducted.

10.1.16 When applicable, the temperature of the reference block and component along with the thermometer manufacturer, model, and serial number.

10.1.17 The type of scan completed, i.e. 100 percent scan, partial scan, or spot check. For partial scans, record the approximate percentage of each section examined.

10.1.18 Examination results (thickness readings) including limitations of the area scanned. When using data loggers/recorders the data printout may be attached to document the thickness measurements.

10.1.19 A drawing or photograph of the component should be included with the examination records when possible.

10.2 All data records shall be reviewed and processed in accordance with ER-AA-NDE-140, "Processing of Dominion NDE Data".

Serial No.11-476 Relief Request RR-04-12 Docket No. 50-336 ATTACHMENT 2 Excerpts From Pipe Stress Analysis Calculation Number MP58B-00138EM, Revision 4. Addendum B, Service Water Supply to Diesel Engine Coolers -

Problem 118 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

Calculation Cover Sheet

/ Dominion" Page 1 of 407 (induding 347 attachment pages)

Calculation Number: Revision: Addendum:

MP5BB-0013BEM 4 B Calculation Quality Class: Z Safety Related El NSQ El Non-Safety Related Installation Verification Required? 0 Yes E] No El N/A Note: Not anlicable for Virginia Plants Name: R. E. DeConto, Signature:*,.. < ý - (.1,.

i Subject (Calculation Title):

Service Water Supply to Diesel Engine Coolers - Stress Problem 118 Addendum Title (if applicable):

N/A Station(s) and Unit(s): Affected System(s), Structure(s), or Component(s):

Millstone Unit 2 SWS; AB, DG

Purpose:

The purpose of this addendum (Addendum B to Revision 4) is to incorporate the changes documented in DCN DM2-02-0198-09 in support of emergent 2R20 service water system improvements. These improvements include: 410 1)z0)1

1. Replacement of valve 2-SW-8AI with material fabricated from stainless steel (AL-6XN) material.

2. Replacement of carbon steel piping spools SK-894 and SK-895 with material fabricated from stainless steel (AL-6XN).

This addendum was prepared in accordance with CM-AA-CLC-301, Revision 3. Screening (50.59, programs, etc...) is not required for this addendum as this addendum supports a parent process (i.e., DCN DM2 0198-09). Screening will be performed under the aforementioned DCN.

Originator: Provide printed name and signature (Qual. Required): Date:

R. E. DeConto 6Z, f,ý 4- 3 Independent Reviewer: Provide printed name and signature (Qual. Date:

Required):-

Z. A. Withrow */s/I Approval: Provide paintedam~e and signature: Date:

M, F, Marino 16 I -5 II REC'OW Form No.731189 (Apr 2009) 1)CI

, Dominion, MPS TransitionalSite-Specific Guidance PassPort DATABASE INPUTS CHANGE Page 2 Calculation Number: vPf59 B-00138EM Revision: 4 Vendor Calculation Number/Other N/A Revision: N/A ADD/CCN#: B Cale Voided: Yes 0 No

~,nl~r'~eded Rv' N/A Stinerseded Rv- W/A "I.Ur zer-se9e W!A CHANGE (C hange Codes [ CC]: "A" = Add; "D" = Delete)

Discipline (Up to 10) CC [ ]:

CC Unit Project Reference Component Id Computer Code Rev. No]

M1, M2, (EWA) Level No.

M3 A DCN DM2-02-0198-09 MEL CODES* _____________

CC Structure.System ComponentI Reference Calculation Rev No. ADD/CCN.

• The codes required must be alpha codes designed for structure, system and component.

NOTE: Avoid multiple item references on a line, e.g., LT 1210 A-D requires four separate lines.

IfCC ]Reference Drawing ¶ Sheet Rev. No.

Comments:

Pipe support calculations with loads that exhibit a load increase of 5% or more will be formally revised (via a revision, an addendum or a CCN). See Attachment E for the summary of load changes based on this'addendum., n addition, seismic I nonseismic supports will be revised to document the change related to the seismic / nonseismic supports Referenced By Calculation Impact mpact AR Reference/Calc Change Ref.

Y N 327160-00149EM ___ x PROBLEM 121 . o X PROBLEM 122 X FormNo. 731189 (Apr2009)

MPS TransitionalSite-Specific Guidance WPDOininOi PassPort DATABASE INPUTs CHANGE Page 3 Calculation Number: MP5813-00138BM Revision: 04 Vendor Calculation Number/Other: N/A Revision: .N/A ADD/CCN # B Cale Voided: [] Yes ]No 6unersen~Li M. I Referenced By Calculation Impact Impact AR Reference/Calc Change Ref.

Y N 327012-00144EM X 327013-00145EM X 327122-00 146EM X 327123-00147EM X 327124-00148EM X 327125-00150EM X 327138-00154EM X 327141-00153EM X 327145-00155EM X 327147-00156EM X 327148-00157EM X 327149-00158EM x 327150-00159EM "_ X 327157-00151EM x 327165-00160EM X 380352-00161EM X 427026-00162EM X 427031-00163EM X 427030-00164EM X 427055-0016SEM X 427067-00168EM X 427069-00170EM X 427080-00173EM X 427083-00175EM X 427085-00177EM X 427089-00178EM X 427090-00179EM x 427092-00181EM X Forn No, 731189 (Apr 2009)

MPS TransitionalSite-Specific Guidance OFDominion-All PassPort DATABASE INPUTs CHANGE Page 4 Calculation Number: MP58B-00138EM Revision: 04 Vendor Calculation Number/Other: N/A Revision: N/A ADD/CCN # B Calc Voided: LIYes Z No Superseded By: N/A Supersedes Cale: N/A Referenced By Calculation Impact Impact AR Reference/talc Change Ref.

Y N 427093-00182EM x 427094-00183EM X "

427104-00184EM X 527009-00185EM X 60469-00193EM X 60492-00192EM X 60493-00191EM X 527010-00199EM X 527012-00189EM X 527017-00190EM x 527019-00198EM x 327002-01005M2 X 427113-01006M2 X Rev. 3, Addendum B 427063-01007M2 X 327098-01 008M2 X 427114-01011 M2 X Rev. 2,Addendum B 427079-01012M2 X 427076-010133M2 X 527027-01014M2 X 60214-01017M2 X 60216-01018M2 X 60221-01022M2 x 60223-01023M2 X Rev. 2, Addendum B 60228-01024M2 X 97-11 8C-02027C2 X 97-118C-0206IC2 x 97-11 8C-02062C2 X Rev,. 2, Addendum A 427074-01004M2 X 427075-01009M2 X _

4271 15-01010M2 X Form No. 731189 (Apr 20O)

MPS TransitionalSite-Specific Guidance SIpDominion-PassPort DATABASE INPUTs CHANGE All Page 5 Calculation Number: MP58B-00138EM Revision: 04 Vendor Calculation Number/Other: ýN/A Revision: N/A ADD/CCN # B Calc Voided: E] Yes 0 No Superseded By: N/A Supersedes Calc: N/A Referenced By Calculation Impact Impact AR Reference/Calc Change Ref.

Y N 427064-00167EM X 427082-00174EM X 427068-00169EM X 327135-00152EM X 427073-00171EM x_"_'"

427087-00172EM X 60492-00192EM X 427084-00176EM X 427091-01016M2 X 427056-00166M x 527014-00186EM X 527013-00188EM X 527011-00187EM X 60219-01020M2 x 60220-0102IM2 X '

60218-01019M2 X 527028-01015M2 x 60229-01025M2 X 95-ENG-0I 186M2 X MP2-SEIS.RPT X 02-CP-0311 1M2 X 98-209 X Form No.731189 (Apr 2009)

Dominion Resource Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 6 CALCULATION NO, REV NO ADD MP58B-00138EM 04 B Table of Contents Pages Calcujation Cover Sheet ......................................................................................................................................................... I PassPort D ATABA SE INPUTS CHANGE .............................................................................................................................. 2 Table of Contents ................................................................................................................................................................... 6 2.0 Asumpt-o n ................ .................................................

2.0 Assumptions ......................................................................................................................-... ........... ... ......................... 9 3.0 General Notes ................................................................................................................................................................... 10 4.0 M ethods ..................................................................................................................... .................................. ..................... ,I!

5.0 REFEREN CES ................................................................................................................................................................. 12 6.0 DESIGN INPUT .........................................................................................  : .................................................................. 13 6.1 B asic Analytical Data: ...................... ...................................................................................................................... 14 6.2 Piping D ata: ........ . .................................................................................................................................................... 14 6.3 Valve Data .............................................................................................................................................................. 15 6.4 Flange Weight D ata ................................................................................................................................................. 16 6.5 Therm al Operating Conditions ................................................................................................................................. 17 6.6 Therm al Anchor Displacem ents ................................................................................................................................ 18 6.7 Response Spectra .................................................................................................................................................... Is 6.8 Seism ic Anchor M ovements ................................................................................................................................... 19 6.9 Pipe Support Data .................................................................................................................................................... 19 6.10 Special Stress Intensification Factors (SI 's) .................................................................................................. 19 6.11 W orksketch ........................................................................................................................................................... 20 7.0 Sumr m ary of Results ........................................................................................................................................................ 29 7.1 MA X IM UM STRESS LEV ELS AND ALLOW ABLES ................................................................................. 30 7.2 Equipm ent Nozzle Evaluation ............................................................................................. ............................... 35 7.3 Evaluation of Flange Joints ........................... ...................................................................................................... 38 7.4 Valve Acceleration Evaluation ................................................................................................................................ 39 7.5 Evaluation of pipe local stresses due to Integral W elded Attachm ents (IWA) .................................................. 40 8.0 Conclusions ...................................................................................................................................................................... 52

Dominion Resource Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 7 CALCULATION NO. REV NO ADD MP58B-O0138EM 04 B TABLE OF CONTENTS (continued)

ATTACHMENT Pages Attachment A NUPIPE-I1 Input Echo .......................................................................................... Al - A62 A tff chm en tp E Output E h ........ .................................... ............ .... ......... 5

• Stress Summary Attachment C NUPIPE-1i Output Echo .................................................................................. CI -C15 0 Equipment Loading Summary Attachment D NUPIPE-I Output Echo ........................................................................................... D -D] 84 a Pipe Support Summary Attachment E Pipe Support Design Loads Comparison Table ...................................................... El - E6 Attachment F CD (Nupipe-II Run) ......................................................................................... F1 Attachment G Calculation Review Checklist .............................................................................. G]

Total Attachment Pages 354 Total No. of Pages = 407

Dominion Resource Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 8 CALCULATION NO, REV NO ADD MP58B-00138EM 04 B 1.0 Purpose The overall objective of this addendum is to qualify the Service Water piping (as shown in the Pipe Stress Worksketches in Section 6,11) in accordance with the requirements of the Millstone Unit 2 FSAR (Reference 2), ANSI code (Reference I of the calculation body), and Millstone Pipe Stress and Pipe Support Specification SP-M2-ME-030 (Reference 4).

In accordance with Reference 4, section 3.13.8, identify the seismic / nonseismic interface boundary support(s) for the fire water cross connect line (see worksketch sheet 6).

Additional objectives of this calculation are as follows:

Z Pipe support design loads will be generated and will be compared to the existing pipe support design loads in order to determine acceptability. Seismic / nonseismic boundary support seismic loads will be developed in accordance with Reference 4, section 3.13.8.

[] Valve accelerations will be determined and evaluated for acceptability.

[] Equipment nozzle loadings/stresses will be determined and evaluated for acceptability.

Z Flange loads will be determined and evaluated for acceptability.

Z Evaluation of pipe local stresses due to Integral Welded Attachments (IWA) will be performed to document acceptability.

Dominion Resource Services CALCULATION SHEET

... CALCULATION IDENTIFICATION NUMBER CALCULATION NO. RE\

MP58B-00138EM 2.0 Assumptions None.

Dominion Resource. Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 10 CALCULATION NO. REV NO ADD MP58B-0O138EM 04 B 3.0 General Notes I. The coordinate system for all data expressed in the global system is as follows:

(-X) is plant "called North" per piping drawing.

(+Y) is vertical "up".

(+Z) is accordingto tie right hmnd niI*

The local system is defined as follows:

For straight piping members (X) is along the axis of the pipe, positive in the direction of coding.

(Y) in the plane of the local X-Axis and the global +Y-Axis unless the local X-Axis is aligned withthe global Y-Axis, then the local Y-Axis will be parallel to the global X-Axis.

(Z) according to the right hand rule.

For curved piping members a radial-normal-tangential system is used where X and Y are in the plane of the curve and Z is normal to the plane as follows:

(X) is the tangential component, positive in the direction of coding.

(Y) is the positive (outward) radial component.

(Z) is normal to the X and Y plane according to the right hand rule.

2. Forces and moments on restraints, supports and equipment are those imposed by the piping system (i.e., actions not reactions).

3. Unless otherwise indicated, intersections are considered as unreinforced branch connections.

4. N/A or NA indicated throughout this calculation represents "not applicable."

5. Abbreviations used for pipe support functions as applicable:

CS - Constant Support AC Axial Constraint SH - Spring Hanger VSS Vertical Shock Suppressor VS - Vertical Support NSS North-South Shock Suppressor VC - Vertical Constraint ESS East-West shock suppressor NS - North South Constraint LSS Lateral Shock Suppressor EW - East West constraint ASS Axial shock suppressor LC Lateral Constraint ANC Anchor

Dominion Resource Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 11 CALCULATION NO. REV NO ADD MP58B-00138EM 04 B 4.0 Methods A. NUPIPE-II Model The NUPIPE-Ir computer program (Reference 5) is utilized in this Addendum. The NUPIPE-l1 model is based on the NUPIPE-Il model generated in Revision 4, Addendum A. The following adjustments to the Addendum A NWUIPE-II model were made to evaluate the requested changes (i.e., the replacement of valve 2-SW-8A and pipe .tspools.q-R94*nd SK-895:

I. Points 5 to 35 are now modeled with NOP 2 (stainless steel properties)

2. Points 5 to 15 and 20 to 35 are modeled with XSEction 13 (ss pipe)

3. Valve 2-SW-8A is modeled as stainless steel (points 15, 18, 20 & 22) with XSEctions 14 (valve body) and 31 valve operator. The weight of the replacement valve is 1765 lbs.

4. Valve inlet and out flange weight is 170 lbs each.

Dominion Resource Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 12 CALCULATION NO, REV NO ADD MP58B-00138EM 04 5

5.0 REFERENCES

References I through 23 are from the body of the calculation Revsion 4, pages 18 amd 19.

24. Design Change Notice: DM2-02-0198-09

25. Drawing 25203-29053, Sheet 130, Revision 1, 24 inch Class 150 Tricentric Valve with Limitorque H4BC

26. Crane Catalog Number 61, Welding Fittings Forged Flanges, Crane Company, St Louis Fitting Division, 1450 So. Second Street, St Louis, Missouri 063104. (Calculation Body Reference 9)

27. Grinnell Catalog Pipe Hanger Design and Engineering, Revised 1979, Grinnell Corporation, Cranston, Rhode Island. (Calculation Body Reference 10)

28. AISC Manual of Steel Construction, Eighth Edition, American Institute of Steel Construction, Inc. 400 North Michigan Avenue, Chicago, Illinois 60611, Page 6-9

29. Specification SP-M2-ME-1 093, Revision I, Procurement Specification for MP2 RBCCW Heat Exchanser Channel Heads

30. NUPIPE-fl Computer Program, Version 3.0.0, Serial No. NUJP300 Intel, Copyright 1985 - 1995, Quadrex Energy Services

Dominion Resource Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 13 CALCULATION NO. REV NO ADD MP58B-00138EM 04 B 6.0 DESIGN INPUT The following design input pages consist of data obtained from various sources which is required to perform the stress analysis of this piping system. This data is assembled in a manner which is suitable for input into the NUPIPE-I1 analysis.

Density of Rolled Steel: 490 lbs / ft3 (Reference 28)

Density of Stainless Steel: 500 lbs / ft' or 0.290 lbs / in3 (Reference 28 times 1.02 per Reference 27)

Dominion Resource Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 14 CALCULATION NO. REV NO ADD MP58B-00138EM 04 B 6.0 Design Input 6.1 Basic Analytical Data:

Unchanged in Addendum B.

6.2 Piping Data:

XSEction Card 31 added to model 24 inch stainless steel valve operator)

.wjý A ýCý- 1 -14 ýnl- No. ý1 No.

13a,b LINE NUMBER: 24"-JGD-1, 24"-JGD-3 1CODE CLASS: 3 13a,b LINE CLASS: JGD DESIGN PRESSURE; 150 PSI 13a,b SCHEDULE: 20 CONTENTS: Water 13a,b PIPING MATERIAL: B-675, UNS N08367 10 OUTSIDE DIAMETER: 24.0 In WALLTHICKNESS: 0.375 In 13a,b INSULATION THICKNESS: 1.5 In. INSULATION TYPE: I INSULATION DENSITY *v*: 12 LB/ CUBIC FT INSULATION MATERIAL: Calcium Silicate I 'P' NUMBER (WELDING REF. No.): 8 E COLD: 28.3 x E 06 PSI 10 PIPE WEIGHT:* N/A LB/FT CONTENTS WEIGHT: N/A LB/FT 10 INSULATION WEIGHT:** N/A LB/FT .... .

TOTAL PIPE WEIGHT .0001 LB/FT Note: ***Insulation Density is taken from Section 3.6 of Revision 3 of this calculation.

Xsection 2 includes only Contents and Insulation weights.

Xsection 9 for Valve Operator considers Design Pressure and Total Pipe Weight as Zero.

Ref X SECTION CARD No No.

LINE NUMBER: CODE CLASS:

LINE CLASS: DESIGN PRESSURE: PSI SCHEDULE: CONTENTS:

PIPING MATERIAL:

OUTSIDE DIAMETER: WALL THICKNESS: In INSULATION THICKNESS: INSULATION TYPE:

INSULATION DENSITY *'*k: LB/ CUBIC FT INSULATION MATERIAL: Calcium Silicate

'P' NUMBER (WELDING REF. No.): E COLD: PSI PIPE WEIGHT:* - LB/FT CONTENTS WEIGHT: LB/FT INSULATION WEIGHT:* LB/FT TOTAL PIPE WEIGHT: LB/FT Note: **"Insulation Density is taken from Section 3.6 of Revision 3 of this calculation.

.... ___ Xsection 4 includes only Contents and Insulation weights.

Xsection 10 for Valve Operator considers Design Pressure and Total Pipe Weight as Zero.

Ref. 10 I 0.68t (D-t) For Carbon Steel 10.89t (D-t) For Austenitic Stainless Steel B-675 UNS N08367 0.3405(Di)2 Weight of Water per foot (LB)

'" Insulation weight = 0.0218 d K (D+K) LB / FT d = Insulation Density (LBS /Cubic Foot)

D - Outside Diameter of Pipe (IN)

K = Insulation Thickness (IN) t = Pipe Wall Thickness (IN)

Di = Inside Diameter of Pipe (IN)

Dominion Resource Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 15 CALCULATION NO. REV NO ADD MP58B-00138EM 04 B 6.0 Design Input (Continued) 6.3 Valve Data TABLE 6.3.1 (Valve Data)

Size Type Node C.G. Location (ft.) . Total .Ref:

No. Ix f z1 Weight (Lbs.)

24 2-SW-8A"' 22 -71.10 1765 24,25 Notes:

1. C.G. location ignores the orthogonal offset of approximately I inch in the two remaining orthogonal directions relative to the main axis of the operator.

The 24 inch replacement valve is 7 inches (0.58 ft) long (Reference 25).

The 24 inch replacement valve (Reference 25), is captured between two flanges. Valve 2-SW-8A is captured between two slip-on flanges The weight of a 125# slip-on (SO) flange is 117 lbs [115 lbs (Reference 26) x: 1.02]

The weight of the 20 studs and 40 nuts per valve I flange connection must be considered: The studs are 1 V/ 4 inch diameter (Reference 26). The length will be set equal to 14.5 inches to account for the studs and the nuts.

Thus the total weight of the studs are nuts is: 20 x (x/ 4) x 1.252 x 4.5 x 0.290 lbs / in" = 103 lbs.

SO flange locations: The weight applied to valve end (pipe / valve centerline) with SO flanges is 117 lbs + V2x 103 lbs = 170 lbs Nodes: 15, and 20.

C.G. Location Slip-on Slip-on

Dominion Resource Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 16 CALCULATION NO. REV NO ADD MP58B-00138EM 04 B 6.0 DESIGN INPUT: (continued) 6.4 Flange Weight Data TABLE 6.4.1 (Flange Weight Data) Flange data is based on the information provided above in the valve section but the length of I X inch rod considered to represent the studs and nuts is set equal to 9 inches (studs are 6 Y4 inches long per Addendum Reference 3, therefore 2 Y4 inches of 1 '/ inch rod are considered to account for the nuts on each rod). The weight of two stainless steel 125# SO flanges is 234 lbs (2 x 117 lbs) pius 20 =1 74 inch diameter rods 9 inches long weight approximately 04 lbs: 'l'lerelore, tWe total weight tor two SS 125# SO flanges pius the weight of the studs and nuts is approximately 298 lbs. Note: 317 lbs was conservatively input into the NUPIPE II model.

Pipe Node 125 Lb. Slip on 150 Lb Slip on [50 Lb. Total Flange size No. Flange(Lbs.) Flange (Lbs.) WeldNeck Wt. (Lbs.) inclI.

(in.) Flame (Lbs.) studs / nuts Ref.

24 35 2x 117 298 3,4,5

Dominion Resource Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 17 CALCULATION NO. REV NO ADD MP58B-00138EM 04 B 6.0 Design Input (Continued) 6.5 Thermal Operating Conditions (Unchanged by Addendum B)

PIPE SECTIONS FOR NOP No's:

INj F r- AI UI41 J LU JJ NOTE:

1. For Node No's, refer to the work sketch (Section 6.11).

Dominion Resource Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 18 CALCULATION NO. REV NO ADD MP58B-00138EM 04 B 6.0 Design Input (Continued) 6.6 Thermal Anchor Displacements (Unchanged in Addendum B)

R.BCCW Heat Exchanger X-18A,B,C Movements:

I-4.-

6.7 Response Spectra (Reference 14)

The Response Spectra of Auxiliary Building at Elev. 14'-6", 0.5% Damping (OBE) which is used for X and Z directions and Vertical Accelerations are 2/3 of the gound acceleration (i.e. 2/3 of 0.09gs) or 0.06gs for OBE and 0.1 13gs for DBE.

TABLE 6.7-1 Horizontal Unchanged by Addendum B HORIZONTAL ACCELEARTIONS (X AND Z DIRECTIONS)

T (Seconds) A (g) T(Seconds) A(g) T (Seconds) A (g) 0.02 0,23 0.038 0.23 0,054 0.46 0.089 0.497 0.109 0.914 0.111 0.96 0.116 5.507 0.119 7.86 0.147 7.86 0.156 4.883 0.161 3.562 0.172 1.857 0.179 1.445 0.238 0.757 0.250 0.686 0.333 0.64 0.714 0.368 0.833 0.326 1.00 0.28 2,000 0.17 TABLE 6.7-2 Vertical Accelerations Unchanged in this Addendum (Reference 14)

VERTICAL ACCELEARTIONS (Y DIRECTION) .

T (Seconds) A (g) T(Secods) A (g) T (Seconds) A 0,010 0.06 10.00 0.06 Note:

1. T is for Period (Seconds) and g is for Spectral Acceleration (g's).

Dominion Resource Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 19 CALCULATION NO. REV NO ADD MP58B-00138EM 04 B 6.0 Design Input (Continued) 6.8 Seismic Anchor Movements (Reference 14) Unchanged per Addendum B 6.9 Pipe Support Data Pipe support hanger 60542 (an anchor) was previously identified as the seismic . nonseismic interface support, i nis addendum redefines the seismc / nonseismnc interface zone to be the two vertical / lateral hangers (60541 and 60542 - see worksketch sheet 6) upstream of hanger 60452.

This is consistent with the pipe stress / pipe support criteria (Reference 4), section 3.13.8, The seismic loads for these two hangers will be increased by a factor of three to account for the seismic loads from the unanalyzed side.

6.0 Design Input (continued) 6.10 Special Stress Intensification Factors (SIF's)

Unchanged per Addendum B

Dominion Resource Services 6.0 DesiBn Input (continued) 6.11 Worlaketch NODE, SUPPORT MARK NDMi 40 427074 NS 75 327002 VC 80 427113 VC-I 95 427063 NS 155 327096 VC -104 160 A-427075 E: Ss 215 427115 ESS 220 427114 VC 290 427079 NS 335 427076 NS CARBON STEEL PIPE 145 527027 ANCI HER 280 527028 AICIFOR ) STAINLESS STEEL UNS NO 8367 PIPE RBCCW HEAT EXCHANGER X-18A RBCCV HEAT EXCHANGER X-Ian SERVICE WATER SUPPLY TO DIESEL ENGINE COOLERS MILLSTONE UNIT 2 SHEET 1

6.0 Design Input (continued) 6.11 Worksketcd CONT'D ON CCONT'l ON SCHNEtT3 SHEET 3 NODE. SUPPORT MARK NO 405 427064 EW 410 327012 V.C.

425 427081 NS 130 327013 Vt.C 455 427082 EW 475 427085 NS, Vc 513 A427068 NS 5Po 380352 VC 805 79-14-22 NC, VC 825 427080 NS, EV 865 427083 EW 860 SK-ALW-I02579 VC

>885 427084 NS, VC 920 427069 NS 925 4R7030 Vc (O CARBON STEEL PIPE STAINLESS STEEL UNS NO 8367 PIPE

[.ESOHEEL ENCON O R IE ON 7

SERV[ICE WATER TO DIESEL E*NGINE COOLERS MILLSTONE UNIT 2 SHEET 2

6.0 Design Input (continued) 6,11 Worksketeh NOfEi SUPPORT MARK NO, CONT'lJ SHEET 4 535 427026 VC 570 32713.5 NS, E V 580 427089 VC 610 427073 EW 615 427087 VC 935 427031 VC 955 427091 VC 970 327141 NS. EW 1000 427090 EW 1020 427104 VC (O) CARBON STEEL PIPE QD STAINLESS STEEL UNS NO 8367 PIPE Loq\ Q;y ý N

z SHEET SHEET 2

[SERVICC WATER

Dominion Resource Services 6.0 Design Input (continued) 6.11 Worksketch NODE, SUPPORT MARK NO O STAINLESS STEEL.

UNS NO 8367 PIPE 635 427055 VC 650 327138 VC, EW/

675 4a7092 VC, E, 685 427094 Wis 695 327147 VC. EW 720 327149 VC, EW 1055 427056 "VC 1070 327145 VC, EW IoE;5 427067 NS 1090 427093 VC. EW CONT'l 1115 327148 VC, E..

ON SHEET 5 1135 327150 Vt, EW N z SERVICE WATER SUPPLY TO DIESEL ENGINE COOLERS MILLSTONE UNIT 2 SHEET 4

6.0 Design Input (continued) 6.11 Worksketch NODE, SUPPORT MARK NO-ON 1200 60469 VC, EWI 8 1215 527019 E't4 1270 60469A VC. EW 12e5 527019 NS 1305 60469 VC, EW 1320 527010 NS, EW 1360 60469A VC, Ew CONT'D AT A

( CARBON STEEL PIPE CONT'D AT A 5TAINLESS STEEL UNS NO 9367 PIPE y

N z

CONT'D SHEET ON 4

ON SERVICE WATER TO DIESEL ENGINE COOLERS 4 MILLSTONE UNIT 2 SHEET 5

Dominion Resource Services NODD SUPPORT MARK NO, 7050 60548 ANCHOR 7054 40541 V\CEW 7066 60540 VCEV CONT. ON SHEET 5 x

1B 31 TO CONT.O AT B SERVICE WATER TO DIESEL ENOINE COOLERS MILLSTONE UNIT 2 SHEET 6

Dominlon Resource Services 6.0 Disslgn Input (co~ntinued) 6.11 WorIcsketch NODE, SUPPORT MARK NO-1940 327124 NS. VC O CARBON STEEL PIPE 1950 327123 NS, VC S STAINLESS STEEL 1965 327122 NS, VC UNS NO 8367 PIPE 1980 60220 7A3 NS, VC 2205 60221 NS, EW 2210 60228 4 WAY WITH Rx 2250 60220 4 WAY WITH Rx 1900 327125 NS 1920 527009 EW 2110 60218 NS 2125 60214 ANCHOR 2295 60229 ANCHOR 2310 60223 ANCHOR C

Y CONT. ON SHEET 5 z x

SERVICE WATER SUPPLY TO DIESEL ENGINE COOLERS MILLSTONE UNIT 2 SHEET 7

6.0 Desigu Input (continued) 6.11 Worksketch NODEr SUPPORT MARK NO, 1395 327157 NS CARBON STEEL C PIPE 141Z5 527014 Ev 1435 327160 NS, VC CD.STAINLESS STEEL 1460 527017 VC UNS NO 8367 PIPE 1470 527013 VC 1485 527011 NS 1505 327165 NS. VC 1520 527012 NS.VC 1525 527012 EW 1535 60522 NS. VC Y

N x

CONT. ON SHEET 5 SERVICE WATER SUPPLY TO DIESEL ENGINE COOLERS MILLSTONE UNIT 2 SHEET 9

6.0 Desigii Input (continued) 6.11 Workskeckh NODE, SUPPORT MARK NO-1705 ANCHOR M-7B 60216 1780 60523 M7}3-NS, EW 1785 60525 4WAY WEITH Rx 1825 60525 4WAY WITH Rx 1690 60219 N-S 1885 ANCHOR 60524 1860 ANCHOR 60526 D

Y N

-4 0 CARBEIN STEEL PIPE SERVICE WATER SUPPLY TO OIESEL ENGINE COOLERS STAINLESS STEEL UNS NO 8367 PIPE MILLSTONE UNIT 2 SHEET 9

Dominion Resource Services 7.0 Summary of Results The analytical results were based on the following NUPIPE-SWPC computer runs.

Dominion Resource Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 30 CALCULATION NO. REV NO ADD MP58B-00138EM 04 B 7.0 Summary of Results (cont.)

(Reference Numbers in this section of the Addendum are from the main calculation body, unless otherwise noted-)

7.1 MAXIMUM STRESS LEVELS AND ALLOWABLES MAXIMUM STRESS LEVELS AND ALLOWABLE - ASMIE CLASS 3 PIPING I I Mvatena+/-: tx 'r. i or ,uuo.ur. n Uzxastmg rlpmg)

Design Temperature: 115 0F (Max. Operating Temp. is used)

Max Operating Temperature N/U: 115F S,=15,000 psi @ 33 0 F (Ref. 1)

Sh,=15,000 psi @ 115'F Normal/Upset (Ref. 1)

SA--f (1.25 Se + 0.25 S,1 ) 22,500 psi @ 11 5°F (Ref. 1) f= 1.0 as total number of significant cycles is less than 7,000. (Ref. 1)

Sy= 35,000 psi @ 115'F (Ref. 1)

Table 7.1.1 Normal/ Upset Conditions Condition Allowable Maximum Node Component Reference Stress Stress Number Type Page No. for

_ _ si) (psi) Max. Stress Equation 8 1.0 Sh = 15,000 4,407 1745 Branch B27 Equation 9 1.2 Sh = 18,000 6,532 1745 Branch B27 Equation 10 S= 22,500 17,948 7032 Branch B36 (Note 1) _ _ _ _ BranchB36 Equation 11 Sh + SA - 37,500 19,026 7032 Branch B36 (Note

) 1 Note:

1. Either the requirements of Eq 10 or Eq 1I1 must be satisfied.

Equation 8 Pd + D5 1.0 Sh (Ref. 4)

Equation 9 (Upset) Pp + D + E + H:5 1.2 Sh (Ref. 4)

Equation 10 T+R+A<SA (Ref. 4)

Equation 11 Pd + D + T + R + A:<(Sh + SA) (Ref, 4)

For definition of terms, see page 34.

Dominion Resource Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 31 CALCULATION NO. REV NO ADD MP58B-00138EM 04 B I

7.0 Summary of Results (cont.)

7.1 MAXIMUM STRESS LEVELS AND ALLOWABLE (continued)

MAxIMUM STRESS LEVELS AND ALLOWABLE - ASME CLASS 3 PIPING Material: AL-6XN (UNS NO8367) (Replaced Piping)

I - - I

.esign.l emperaurfe: i (Max. Operating Temp. is used)

Max Operating Temperature N/U: 115°F S,;=20,200 psi @ 33°F (Ref. 5,18)

Sh=20,200 psi @ 115'F Normal/Upset (Ref. 5,18)

SA=f(1. 2 5 S, + 0.25 Sh ) = 30,300 psi @ 1151F (Ref. 1) f= 1.0 as tothtL number of significant cycles is less than 7,000. (Ref. 1)

Sy= 47,000 psi @ 200'F considered (Ref. 18)

Table 7.1.2 Normal/ Upset Conditions Condition Allowable Maximum Node Component Reference Stress Stress Number Type Page No. for S(psi) (psi) N ra Max. eN f Equation 8 1.0 Sh = 20,200 4,742 140 Elbow B4 Equation 9 1.2 Sh = 24,240 6,563 205 Tee B5 Equation 10 SA = 30,300 22,864 2170 Branch B33 (Note 1)

Equation 11 Sh + SA = 50,500 27,086 2170 Branch B33 (Note 1) 1 1 1 Note:

1. Either the requirements of Eq 10 or Eq 11 must be satisfied.

Equation 8 Pd + D _ 1.0 Sh (Ref. 4)

Equation 9 (Upset) Pp + D + E + H*_ 1.2 Sh (Ref. 4)

Equation 10 T + R + A*<_ SA (Ref. 4)

Equation II Pd+ D + T + R + A < (Sh + SA) (Ref. 4)

For definition of terms, see page 34.

Dominion Resource Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 32 CALCULATION NO. REV NO ADD MP56B-001 38EM 04 B 7.0 Summary of Results (cont.)

7.1 MAXIMUM STRESS LEVELS AND ALLOWABLE (continued)

MA.XIMUM STRESS LEVELS AND ALLOWABLE - ASME CLASS 3 PIPING Material: A53 Gr. B or A106 Gr. B (Existing Piping) a I i k -UA. ~JjJ%.AQ11r$ J %"F-ufJ Va.

Max Operating Temperature (Faulted): 115°F Sy-= 35,000 psi @ 115'F (Ref. 1)

Table 7.1.3: Faulted Condition Equation 9 (Faulted) P. + D + E' + H 5 Sy (Ref. 4)

For definition of terms, see page 34.

Dominion Resource Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 33 CALCULATION NO. REV NO ADD MP58B-00138EM 04 B 7.0 Summary of Results ' (cont.)

7.1 MAXIMUM STRESS LEVELS AND ALLOWABLE (continued)

MAXIMUM STRESS LEVELS AND ALLOWABLE - ASME CLASS 3 PIPING Material: AL-6XN (UNS NO8367) (Replaced Piping)

We1 Aý -1 5Oux J pprmiriig Teiii is-use.d).

Max Operating Temperature Faulted: 115 0F Sy= 47,000 psi @ 200'F considered (Ref. 18)

Table 7.1.4: Faulted Condition

'Condition Allowable Maximum Node Component Reference Stress Stress Number Type Page No, for (psi) (psi) Max, Stress Equation 9 Sy = 47,000 8,269 205 Tee B4j Equation 9 (Faulted) Pp + D + P' + H < Sy (Ref. 4)

For definition of terms, see page 34.

Dominion Resource Services CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 34 CALCULATION NO. REV NO ADD MP58B-00138EM 04 B 7.0 Summary of Results (cont.)

7.1 MAXIMUM STRESS LEVELS AND ALLOWABLE (continued)

DEFINITION OF TERMS Sc . *-A-14ewa-b4.e-str w r ~rc

- tw*- ~ tl, 7' , U. litiultutm- ln temp, azure.

St, =Allowable stress for Class 2, 3, and Class 4 piping is based on the higher of maximum operating temperature or ambient temperature.

SA = Allowable stress range for expansion stress f(I.25 S, + 0.25 SO).

D = Stress due to sustained mechanical loads including deadweight of piping, components, contents and insulation.

E = Stresses due to inertia effects of the OBE.

H = Stresses due to occasional loads other than seismic. Examples of these loads would be: water hammer, steam hammer, opening of safety relief valves, etc.

T = Stress due to thermal expansion of the system in response to average fluid temperature.

R = Stresses induced in the piping due to thermal growth of equipment and/or structures to which the piping is connected as a result of plant normal or upset conditions.

A =Stresses induced in the piping due to response of the connected equipment and/or structures to the OBE (commonly referred to as OBE anchor movements).

E'= Stresses due to inertia effects of the SSE.

Pd = Internal pressure loads due to design pressure.

P = Internal pressure loads due to peak pressure.

f = Stress range reduction factor for cyclic conditions (See Reference 1, SubSection NC-361 1, for Class 2, ND-361.1 for Class 3 piping).

6-Mar-2011 NUPIPE-I1 - PIPING ANALYSIS PROGRAM - Version 3.0.0 PJ GE 1760 RUN ID: 12220117 Serial No. NUP300 Intel Licensed to: Virginia Power CALCULATION MP58B-00138EM REV.4, ADDENDUM B *SW TO DIESEL ENGINE COOLERS ASME SECTION III CLASS 2. 3 OR ANSI B31.1.8 sTRESS

SUMMARY

EQUATION 8 EQUATION 9 EQUATION 10 EQUATION 11 SUSTAINED OCCASIONAL EXPANSION SUSTAIN+EXPANS MQ. 9+10 PSI PSI PSI PSI PSI MEMBER NODE SIF ACTUAL ALLOW ACTUAL ALLOW ACTUAL ALLOW ACTUAL ALLOW STATUS RUN 532 1.000 1635. 15000. 2256. 18000. 526. 22500. 2160. 37500. 2782.

535 1.000 1906. 15000. 2134. 18000. .742. 22500. 2647. 37500. 2876, RUN 535 1.000 1906. 15000. 2134. 18000. 742. 22500. 2647. 37500. 2876.

540 1.000 1762. 15000. 2002. 18000. 771. 22500. 2533. 37500. 2772.

ELBOW 540 1.997 2089. 15000. 244B8. 18000. 1539. 22500. 3629. 37500. 3987.

545 1.200 1459. 15000. 1790. 18000. 912. 22500. 2371. 37500. 2702.

RUN 545 1.200 1459. 15000. 1790. 18000. 912. 22500. 2371. 37500. 2702.

550 1.200 1462. 15000. 1793. 18000. 910. 22500. 2372. 37500. 2703. CD 00 RUN 550 1.200 1462. 15000. 1793. 18000. 910. 22500. 2372. 37500. 2103.

555 1.200 1980. 15000. 2371. 18000. 784. 22500. 2764. 37500. 3155.

RUN 555 1.200 1980. 15000. 2371. 18000. 784. 22500. 2764. 37500. 3155.

560 1. 000 1611. 15000. 1934. 18000. 986. 22500. 2597. 37500. 2920. 00 ELBOW 560 2.605 2094. 15000. 2725. 18000. 2568. 22500. 4662. 37500. 52S3.

CO) 565 2.605 L836. 15000. 2256. 18000. 2625. 22500. 4361. 37500. 4881, tn RUN. 565 1.000 1479. 15000, 1,694. 18000. 1008. 22500. 2486, 37500. 2702.

570 1.200 1474. 15000, 1691. 18000. 1178. 22500. 2652. 37500. 2870.

ca RUN 570 1.200 1474. 15000, 1691, 18000. 1178. 22500. 2652. 37500. 2870.

1.7Uu i502. 202oU. 1138. 22500. 2640. 37500.

[ (Loc- om LQk 0-RUN 580 1.200 1502. 20200, 1709.. 24240. 1138. 30300. 2640. 50500. 2847.

585 1.200 1503. 20200. 1710. 24240. 1170. 30300. 2673. 50500. 2880.

ELBOW 585 1.200 1503, 20200. 1710. 24240. 1170. 30300. 2673. 50500. 2880.

590 1.200 1371. 20200. 1591. 24240. 2406. 30300. 3777. 50500. 3997.

(D RUN 590 1.200 1371. 20200. 1591. 24240. 2406. 30300. 3777. 50500. 3997, :n 595 1.200 1369. 20200. 1588. 24240. 2402. 30300. 3771. 50500. 3990.

RUN 595 1.200 1369. 20200. 1588. 24240. 2402. 30300. 3771. 50500. 3990.

600 1.200 1394. 20200, 1626. 24240.. 3718. 30300. 5111. 50500. 5344.

ELBOW 600 1.200 1394. 20200. 1626. 24240. 3718. 30300. 5111. 50500. 5344.

605 1.200 1444. 20200. 1662. 24240. 3207. 30300. 4651. 50500. 4870.

6-Mar-2011 NUPIPE-I1 - PIPING ANALYSIS PROGRAM - Version 3.0.0 PA 3E 1803 RUN ID: 12220117 Serial No. NUP300 Intel Licensed to: Virginia Power FAULTED STRESS CHECK SY=35000 PSI OR SY=47000 PSI ALLOWABLE ASME SECTION III CLASS 2. 3 O ANSI B31.1,B STRESS

SUMMARY

EQUATION 8 EQUATION 9 EQUATION 10 EQUATION 11 SUSTAINED OCCASIONAL EXPANSION SUSTAIN.EXPANS EQ. 9+10 PSI PSI PSI PSI PSI MEMBER NODE SIF ACTUAL ALLOW ACTUAL ALLOW ACTUAL ALLOW ACTUAL ALLOW STATUS RUN 532 1.000 1635. 15000. 2809. 36000. 526. 22500. 2160. 37500. 3335.

535 1.000 1906. 15000. 2337. 36000. 742. 22500. 2647. 37500. 3079.

RUN 535 1.000 1906. 15000. 2331. 36000. 742. 22500. 2647. 37500. 3079.

540 1,000 1762. 15000. 2214. 36000. 771. 22500. 2533. 37500. 2985.

ELBOW 540 1.997 2089. 15000. 2767. 36000. 1539. 22500. 3629. 37500. 4306.

545 1.200 1459. 15000. 2084. 36000. 912. 22S00. 2371. 37500. 2996.

RUN 545 1.200 1459. 15000. 2084. 36000. 912. 22500. 2371. 37500. 2996.

550 1,200 1462. 15000. 2087, 36000. 910. 22500. 2372. 37500. 2997.

RUN 550 1.200 1462. 15000. 2087. 36000. 910. 22500. 2372. 37500. 2993.

555 1.200 1980. 15000. 2719. 36000. 784, 22500. 2764. 37500. 3503.

00 RUN 555 1.200 1980. 15000. 2719. 36000. 784. 22500. 2764. 37500. 3503.

560 1.000 1611. 15000. 2222. 36000. 986. 22500. 2597. 37500. 3207.

ELBOW 560 2,605 2094. 15000. 3287. 36000. 2568. 22500. 4662. 37500. 5855.

Ln 565 2.605 1836. 15000. 2631. 36000. 2625. 22500. 4461. 37500. 5255. S00 00 ul RUN 565 1.000 1479. 15000. 1886. 36000. 1008, 22500. 2486. 37500. 2893. Ln 570 1.200 1474. 15000. 1885. 36000. 1178. 22500. 2652. 37500. 3063.

RUN 570 1.200 1474. 15000. 1885. 3600o. 2178. 22500. 2652. 37500. 3063.

I 580 1.200 1502. 25000, 1893. 3600Ofl 1138. 22500. 2640. 37500. 3031.

RUN 580 585 1.200 1.200 1502.

1503. 20200.

20200. 1893. 48480. 1138. 30300. 2640. 50500. 3031.

1895. 48480. 1170. 30300. 2673. 50500. 3065.

ELSOW 585 1.200 1503. 20200. 1895. 48480. 1170. 30300. 2673. 50500. 3065.

590 1.200 1331. 20200. 1786. 48480. 2406. 30300. 3777. 50500. 4192.

RUN 590 1.200 1371. 20200. 1786. 48480. 2406. 30300. 3777. 50500. 4192.

595 1.200 1369. 20200. 1783. 48480. 2402. 30300. 3771. 50500. 4185.

RUN 595 1.200 1369. 20200. 1783. 48480. 2402. 30300. 3771. 50500. 4185.

600 1.200 3394. 20200. 1833. 48480. 3718. 30300. 5111. 50500. 5550.

ELBOW 600 1.200 1394. 20200, 1833. 48480. 3718. 30300. 5111. 50500. 5550.

605 1.200 1444. 20200. 1857. 48480. 3207. 30300. 4651. 50500. 5064.

Calculation Cover Sheet IPage I of 596 w~Dominion-Calculation Number: Revision: Addendum:

MP585-00138EM 4 N/A Calculation Quality Class: Z Safety Related E NSQO Non-Safety Related Installation Verification Required? 0 Yes [I No E] N/A N te: Not a Ipiý able for Vrgna Plants

. . ... ... .. . .. -h 7))

Subject (Calculation Title):

Service Water Supply to Diesel Engine Coolers - Stress Problem 118 Addendum Title (if applicable):

N/A "Station(s) and Unit(s): "... Affected System(s), Structure(s),' or Component(s):

Millstone Unit 2 SWS; AB, DG

Purpose:

The purpose of Revision 4 is to Incorporate the changes documented in Revision 3 CCN 01 through CCN 24 of this calculation as well as the service water piping replacements being implemented by DCN DM2 0345-08, Originator: Provide printed name and signature (Qual. Required): Date:

R. Sainath 2 -0 io-j Reviewer: Provide printed name and signature (Qual. Required): Date:

P. V. Patel e) V- -1*' (c ) -. 1 D0- i0 Approval: Provide printed name and signature: 0-- 'NW.ee ' Date:

FormNo, 731169 [AprZ00S)

MPS TransitionalSite-Specific Guidance

Pvominion-All PassPort DATABASE INPUTs Page 2 Calculation Number: MP58B-00138EM Revision: 04 Vendor Calculation Number/Other- N/A Revision: N/A ADD/CCN # N/A Cale Voided: El Yes 2No I

...... . upersee .y: .N/A. bupersecles. alc: ,. N /A - -... ... . .

Discipline (Up to 10) L, N, P,V Unit Project Reference Component Id Computer Code Rev. NoJ (M.., M2, M3) DCR or MMD)

(E(2WA, II I Level No, M2 DM2-00-0345-00 RBCCW-X18A NUPIPE-SWPC Q1/00 RBCCW-XI8B NUDL-PC 01/00 RBCCW-XI8C I

.... ... MEL CODES*

Structure System Component Reference Calculation Rev ADD No. CCN AB SWS PIP 98-209 0 N/A DG

• The codes required must be alpha codes designed for structure, system and component.

NOTE: Avoid multipe, item references on a tine, e.g., LT 1210 A-D requires four separate lines.

Reference Drawing " Sheet Rev. No.

25203-20224 00058 25203-20224 00057 3 25203-20224 00056 4 25203-20224 00061 2 25203-20224 00059 7 25203-20224 00060 2 25203-20146 01028 7 25203-20146 01029 8 25203-20150 01014 3 25203-22200 60542 1 25203-22200 60469. 2 25203-22200 427094 6 Comments:

FaimNo. 731189 (Apr200V

MPS TransitionalSite-Specific Guidance Dominion-

'All PassPort DATABASE INPUTs Page 3 Calculation Number: MP5813-00138EM Revision: 04 Vendor Calculation Number/Other: N/A Revision: N/A ADD/CCN # N/A Cale Voided: 7 Yes ZNo

• JA Ck.- 2.rN.V... .

.. . . . - i~upers eu .y.1. . oUpel*eO.est, alc:

Discipline (Up to 10) L, N, P, V Referenced By Calculation Impact Impact AR Reference/Calc Change Ref, Y N 327160-00149EM X Revision 04 PROBLEM 421 _X PROBLEM 122 " X 327012-00144EM X 327013-00145EM X 327122-00146EM ....... X' 327123-00147EM X 327 124-00148EM X Revision 02 327125-00150EM X Revision 04 327138-00154EM X 327141-00153EM X 327145-00155EM X 327147-00156EM X 327148-00157EM X 327149-OOIS8EM X 327150-00159EM X Revision 03 327157-OOISIEM X 327165-00160EM X 380352-00161EM x 427026-00162EM X 427031-00163EM X 427030-00164E.M_ X 427055-00165EM X 427067-0o16EM x 427069-00170EM X ......

427080-00173EM X Revision 02 427083-00175EM X 427085-00177EM X 427089-00178EM x 427090-00179EM X _

427092-00181EM X Revision 03 Fon No, 7311 B9(Apr 2309)

MPS TransitionalSite-Specific Guidance arDominion-All PassPort DATABASE INPUTs Page 4 Calculation Number: MP58B-00!3"8EM Revision: 04 Vendor Calculation Number/Other: N/A Revision: N/A

-I 1,~~r'T4$MIA, Caic Voicieci: I I tes XI -No.

M NO. I -

Cat,WdEd-7--fl 'f.eS Superseded By: N/A Supersedes Calc: N/A Discipline (Up to 10) L, N, P, V Referenced By Calculation Impact Impact AR Reference/Calc Change Ref.

Y N 427093-00182EM X .....

427094-00183EM X Revision 04 427104-00184EM X 527009-00185EM X 60469-00193EM X Revision 03 60492-00192EM x 60493-00191EM X 527010-00199EM X Revision 05 527012-00189EM X 527017-00190EM X 527019-00198EM X Revision 04 327002-01005M2 .. _ X _

427113-01006M2 x Revision 03 427063-007M0 2_ X 327098-0100QM2 x 427114-01011M2 X Revision 02 427079-01012M2 X Revision 01 427076-01013M2 x 527027-01014M2 X _*vision 02 60214-01017M2 x 60216-0101 8M2 X 60221-01022M2 x 60223-01023M2 X Revision 02 60228-01024M2 X Revision 02.

97-11 C-02027C2 X 97-118C-02061 C2 x 97-1 18C-02062C2 X Revision 01 427074-01004M2 x 427075-01009M2 X 427115-01010M2 X ForMNo. 731189 (ApT2009)

MPS TransitionalSite-Specific Guidance

OpDominion.

'All PassPort DATABASE INPUTs Page 5 Calculation Number: MP58B-0013SEM Revision: 04 Vendor Calculation Number/Other: N/A Revision: N/A ADDLCs.ýN a LILA Vaidod; F--i Yes 2ýj D40 i-Superseded By: N/A Supersedes Catc: N/A Discipline (Up to 10) L, N, P, V Referenced By Calculation Impact Impact AR Reference/Calc Change Ref.

Y N 427064-00167EM x 427082-00174EM X 427068-00169EM X 327135-00152EM X Revision 02 427073-00171EM X Revision 02 427087-00172EM X Revision 02 60492-00192EM X Revision 01 427084-00176EM X 427091-01016M2 x 427056-00166M X 527014-00186EM. X 527013-00188EM X .......

527011-00187EM X 60219-01020M2 X 60220-01021M2 X 60218-01019M2 X 527028-01015M2 X Revision 01 60229-01025M2 X ._.

95-ENG-01186M2 x MW2-SEIS.RPT X 02-CP-031] IM2 X 98-209 X _

Fom NO.731189 (Apr 2009)

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 6 CALCULATION NO. REV NO CCN NO MP58B-001 38EM 04 NIA Review Statement for Calculation Review of this calculation was based on the methods below:

1) Review of:

Initial Upon a) Inputs to ensure that they have been oroperty selected C.nmple.tionn _ -

andcorrectlyused in the calculation., (CheckOne)

I) Limited review (provide justification) ii) Line by line review __

b) Assumptions to assure their validity and need for later confirmation. _____

c) Methodology to assure the appropriateness of the overall approach, its implementation, and the correctness of the.

specific equations utilized.

i) Limited review (provide justification) ii Line by line review d) Results to ensure reasonableness and accuracy Z _____

e) Ifalternate calculation Is performed to verify c) and d) check here and attach calculation as an appendix E

2) Check of Calculation (Check One) a) Complete numerical check I,'v b) Numerical check of critical Items _l (state items and justification below)

3) AdmInistrative check of format and content [ ____

4) Comrnm ents/Justification Re_

view Methods Selecjed as Indicated Above P. V. Patel V, C Z-\ ) -)0 Reviewer Date P. V. Patel Z-io-10 Independent Reyvj er Date R.A.aBaInA -'t# 4/ec ,$

Lead concurrence Date

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 7 CALCULATION NO. REV NO CCN NO MP58B-00138EM 04 NIA TABLE OF CONTENTS Pages Calculation Cover Sheet ......................................................................................... .....

PassPort DATABASE INPLU Ts ....................................................................................... 2 Review Statem ent for Calculation ................................................................................. 6 TWbhi ofCent s . . . ..................... ............................

Revision Status.........................................................................................................9............9 1 Purpose ................................................................................................................................. 11

2. A ssumptions ......................................................................................................................... 12 3 General N otes ........................................................................................................................ 13

4. M ethods ............................................................................................................................. 15

5. References ............................................................................................................................. Is

6. D esign Input .......................................................................................................................... 20 6.1 Basic Analytical D ata ................................................................................................ 21 6.2 Piping Data .............................................................................................................. 23 6.3 Valve D ata ................................. 1.................................................... 31 6.4 Flange W eight D ata .................................................................................................. 32 6.5 Thermal Operating Conditions ................................................................................. 38 6.6 Therm al Anchor D isplacements ............................................................................... 40 6.7 Response Spectra-.~......... ....................... ............ 41 6.8 Seism ic Anchor M ovements ................................................................................... 42 6.9 Pipe Support D ata ..................................................................................................... 43 6.10 Special Stress Intensification Factors ...................................................................... 46 6.11 W orksketch .................................................................................................................... 47

7. Summ ary of Results ......................................................................................................... 56 7.1 M axim um Stress Levels and Allowable ................................................................. 57 7.2 Equipm ent N ozzle Evaluations ............................................................................. 62 7.3 Evaluation of Flanged Joints ................................................................................... 63 7.4 Valve A cceleration Evaluations ............................................................................... 64 7.5 Evaluation of local stress due to Integral Welded Attachments ............................. 69

8. Conclusions ................................................................................................................................. 79

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 8 CALCULATION NO. REV NO CON NO MP58B-00138EM 04 NIA TABLE OF CONTENTS (continued)

ATTACHMENT Pages Attachment A NUPIPE-SW PC lnput Echo .................................................................................. Al - A94

• m * ; .._

Attachment B NUfrIPE-SWPC Output Echo .................................. B I - B290

• Stress Summary Piping Displacements

• Equipment Loading Summary

• Valve Accelerations

• Pipe Support Summary

• Free Vibration Analysis Attachment C NUDL-PC Input and Output ................................................................................. Cl - C98 Attachment D M iscellaneous Correspondence ................................................................................. D I -D 24 Attachment E Pipe Support Design Loads Comparison Table ...................................................... El - E9 Attachment F CD (N upipe Run) .............................................................................................. F1 Attachment G Calculation Review Checklist ........................................................................... G1 Total Attachment Pages 517 Total No. of Pages - 596

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 9 CALCULATION NO. REV NO CCN NO MP588-00138EM 04 NIA REVISION STATUS Dt8CRIPTION/REASON FOA CH~ANCE [PAGES-ORIGINAL ISS1YM / TO .NCOIAPORATE PA/ 86-007 SERVICE WATER PIPE REPLACZ29M. IALL I ~.

.T1IS CALC. SUPERSEDES XP2 BECHTEL PIPE STRPESS CALC. FOR PROBLEPMS 118 & 120 SERVICE WATER SUPPLY TO DIESEL WqGINE COOL2S. (SEE INPUT DATA PAGE 13).

1.) INCORPORATED CCN #1 (INC. NEW PIPE SPOOL ALL PIECES AND FLANGES PER AS BUT'ILT) 2,) INCORP-OATED CCN #2 (DCN L02-S-905-92:

ADDS INSTRUMENTATION TAP' FLANGES) 3.) INCORPORATED CCN #3 (SUPERSEDED CALC.

78-883-140-GH REV.1) 4-) INCREASED MAXIMUM TEMPREkT-"E PER MM4;5 SE-93-180.

5.) ADDED 1" SPACER PLATES NEAR' VALVES 2-sW-12A,2-SW--12C ARD 2-SW--2L PgR DCN DX2-P-217-92.

6.) INCLUDED REV.0 TITLE PAGE At PAGE IA.

2 1.) INCORPORATED DCN DM-S-541-93, ADDS VERT

,ND INSTRUMEntATION TUBI:4Ce.

2.) TO UPDATE CALCULATION.:.

ADDED NEW PAGES 1, 2, 3 ADDED PAGE'J OF REVISION I AS PAGE 1B IB DESCJRBEW REVISIONS 7 REVISED INDIVIDUAL PAGES AS INDICATED 4,5,6,9,21

,E 23,53,54 ADDED NgW LOAD TABULATION SHEETS 30 to 52 ADDED ATTACMENT NO. 7 (APPLICABLE Ddi-) kTT. NO 7 ADDED NEW APPENDIX A FOR T'frS ANALYSIS APPEN. A 3 1.) NEW ANALYSIS USING ADLP-'P2 PIPE STRESS ALL COMPUTER PROGRAM.

2.) ADDED ANALYSES FOR TEMPORAlk CONFIG, PER DCN DM2-S-541-93.

No. DESCRIPTION/REASON FOR CHANGE PAGES 3 3.) ADDED ANALYSES FOR TEMPORARY CONFIG. PER CONTD DON DM.2-S-0116-94.

4.) ADDED ANALYSES FOR TEMPORARY CONFIG. VE'R DCN DM2-S-0449-94

Shaw Stone & Webster Nuclear CALCULATION SHEET.

CALCULATION IDENTIFICATION NUMBER PAGE 10 CALCULATION NO. REV NO CCN NO MP58B-00138EM 04 N/A REVISION STATUS (cont.)

Rev, Description/ Reason for Revision Affected Pages No, 4 This revision has incorporated applicable changes ' All described in Calculation Change Notices (CCN0I through 2on3 ofthis calcultioen i ý . I -..-

addimss the~pciential impact of the cumulative effects of these changes, Revision 4 also incorporates the piping replacements implemented by DCN DM2-00-0345-08.

Shaw Stone & Webster Nuclear CALCULlATION SHEP" CALCULATION IDENTIFICATION NUMBER CALCULATION NO, RVN CONO PAGE 11 MP58B-001 38EM 04 MMI1A 10 Purpose .

The overall objective of this calculation is to qualify the Service Water piping (as shown in the Pipe Stress Worksketches in Section 6.11) in accordance with the requirements of the Millstone Unit 2 FSAR (Reference 2), ANSI code (Reference 1) and Millstone Pipe Stress and Pipe Support Specification SP-M2-ME-030 (Reference 4).

_.dit..

.. .iAl t . . a u luwb. ....

,[] Pipe support design loads wilt be generated and will be compared to the existing pipe support design loads in order to determine acceptability.

S Valve accelerations will be determined and evaluated for acceptability.

[ Equipment nozzle loadings/stresses will be determined and evaluated for acceptability.

[ Flange loads will be determined and evaluated for acceptability.

[ Evaluation of pipe local stresses due to Integral Welded Attachments (TWA) wilt be performed to document acceptability.

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER CALCULATION NO. REV MP58B-00138EM 04 2.0 Assumptions None.

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFRCATION NUMBER PAGE 13 CALCULATION NO. REV NO I CCN NO MP58B-00138EM 04 NIA 3.0 General Notes I, The coordinate system for all data expressed in the global system is as follows:

(-X) is plant "called North" per piping drawing.

(+Y) is vertical "up",

______(+Z) is acrmairding to the.-righl-hand rc.le The local system is defined as follows:

For straight piping members (X) is along the axis of the pipe, positive in the direction of coding.

(Y) in the plane of the local X-Axis and the global +Y-Axis unless the local X-Axis is aligned with the global Y-Axis, then the local Y-Axis will be parallel to the global X-Axis.

(Z) according to the right hand rule.

For curved piping members a radial-normal-tangential system is used where X and Y are in the plane of the curve and Z is normal to the plane as follows:

(X) is the tangential component, positive in the direction of coding.

(Y) is the positive (outward) radial component.

(Z) is normal to the X and Y plane according to the right hand rule.

2. Forces and moments on restraints, supports and equipment are those imposed by the piping system (i.e., actions not reactions).

3. Unless otherwise indicated, intersections are considered as unreinforced branch connections.

4. N/A or NA indicated throughout this calculation represents "not applicable."

5. Abbreviations used for pipe support functions as applicable:

CS - Constant Support AC - Axial Constraint SH - Spring Hanger VSS - Vertical Shock Suppressor VS - Vertical Support NSS - North-South Shock Suppressor VC - Vertical Constraint ESS - East-West shock suppressor NS - North South Constraint LSS Lateral Shock Suppressor EW - East West constraint ASS Axial shock suppressor LC - Lateral Constraint ANC Anchor

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 14 REV NO CCN NO CALCULATION NO.

MP58B-00138EM 04 N/A 3.0 General Notes (continued)

6. The following minor modeling discrepancies are contained in the NUPIPE-SWPC coding. The effects of these discrepancies were reviewed and concluded to be insignificant with respect to the calculation results/conclusions.

a V~tlvp nrq fnprt at rvode-1 2 i- r-.ored i-~tcldicinn&~

• Pipe Runs between nodes 7060-7063, 7063-7066 should be in the +X direction to agree with the piping Iso. (Ref. 13.i) instead of-Z direction coded.

• Flange weight of 17 lbs at node 2310 was inadvertently input at node 2285. It should be noted that there is already a CWEIGHT card at node 2285.

• Flange weights of 26 lbs (Node 1740) and 36 Lbs (Node 1941) were inadvertently omitted in the Nupipe input.

7. The Minimum Wall Thickness (t,) calculation shown in Section 5.4 of Revision 3 of this calculation was qualified for a Design Pressure of 100 psig and is included in Attachment D of this calculation.

The calculation sheets included in Attachment D were "marked-up" to show acceptability for a Design Pressure of 150 psig.

S. The Design Input (Piping, Pipe Supports, Valves and Heat Exchanger Drawings) from Section 3.1 of Revision 3 of this calculation are included in Attachment D for information only.

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 15 CALCULATION NO. REV NO CCN NO MP58B-0013SEM 04 NIA 4.0 Methods A. NUPIPE-SWPC Model/ NUDL-PC Computer Program The NUPIPE-SWPC model generated in Revision 4 was developed using the two existing computer models as described below.

ADLPIPE Runs (Thermal, Deadweight and Seismic ,inn ly.sis)- 1 M3.00!, 138E.M.006, 138EM3.002, 138EM3:003 as noted"i Section 5.2 6f Revisioin3 &fthis calciilaion.

Pipestress run based on CCN 08 to the Revision 3 of this calculation. This run include Cross-Tie between Service Water lines (8"-JGD-004) above the existing valves 2SW-12B and 2SW-12D, and the Fire Protection line 6'"-JBD-026 downstream of valve 2-FIRE-258.

The NUPIPE-SWPC model also incorporated the piping changes based on "CCNs/DCNs" summarized in Revision 3 CCN 01 through CCN 24. The following provides a summary of these modeling updates

" DCN DM2-00-0345-08 (Ref. 5a) addresses pipe replacement spool pieces.

• DCN's DM2-00-0225-08, DM2-00-0055-08, DM2-01-0054-08 and DM2-00-0054-08 (Ref. 5) which covers replacement of Service Water pipe spool P-14 with AL-6XN material and the removal of Service Water Inlet Strainers L350B, L350A and replacing these components with spool pieces of AL-6XN material.

" Design Pressure of 150 psi was conservatively considered for the entire stress problem. CCN 10 to Revision 3 of this calculation is qualified for the uprated design pressure of 150 psi to the portions of Service Water to Diesel Engine Coolers. CCN 10 also adds a pair of flanges, a vent and a drain line to Fire Protection line 6"-JBD-26 (analyzed in CCN 08).

" Based on CCN 13 to the Revision 3 of this calculation, the overall valve weight for 2-SW-89A1B is changed from 119 lbs to 135 lbs.

• Based on CCN 15 to the Revision 3 of this calculation, the overall valve weight for 2-SW-12A/B/C/D is changed from 80 lbs to 292 lbs.

Based on CCN 17 to the Revision 3 of this calculation, the overall valve weight for 2-SW-23 lA/B is changed from 156 lbs (noted in CCN 13) to 347 lbs.

Service Water line 6"-JGD-7 (between nodes 1870 and 1875) pipe material including fittings and flanges is replaced with material AL-6XN (UNS N08367) per CCN 19 to the Revision 3 of this calculation.

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 16 CALCULATION NO. REV NO ' CCN NO MP58B-00138EM 04 NIA 4.0 Methods (continued)

The NUPIPE-SWPC model also addressed the piping replacements being implemented by DCN DM2-00-0345-08 (Ref. 5). Additionally, as described in the correspondence contained on page D9 and D10, Pipe Support 60525 (Nodes 1785, 1825) and 60228 (Nodes 2210, 2250) were modeled as 4-way restraints, and Pipe Support 60221 (Node 2205) and 60523 (Node 1780) were modeled as NS/EW restraints. The trunnions related to Anchor 60542 (Node 9755 at Floor and Node 9765 at Wall) were also incluided in the NUIPF-.qWPC model-The NUDL-PC computer program was used to determine the new "Pipe Support Design Loads,"

B. Operating Conditions The operating conditions considered in the NUPIPE-SWPC analysis were based on Section 5.1.1 of Revision 3 of this calculation, except a lower 33* F temperature for SW supply piping to the RB CCW heat exchangers was considered instead of 40' F used in the existing analysis, and 1150 F temperature at the outlet of the Diesel Generator Coolers M-7A AND M-7B was also considered.

The specific thermal operating conditions considered in the NUPIPE-SWPC run are summarized in Section 6.5.

C. Seismic Response Spectra The applicable Amplified Response Spectra Curves are:

Building(s) Location Elevation Damping Auxiliary Building 14'-6" 0.5% Damping (OBE)

(Horizontal Accelerations X and Z Directions)

Vertical Accelerations are 2/3 of the ground acceleration (i.e. 2/3 of 0.O9gs) or 0.06gs for OBE and 0.1 13gs for DBE.

SSE Inertia results are obtained by multiplying OBE Inertia results by 1.89 as noted in Section 5.1 of Revision 3 of this calculation and also in Section 3.6 of Pipe Stress Spec SP-M2-ME-030 (Ref. 4),

D. Seismic Anchor Movements (SAM's)

The Maximum Relative displacements between Auxiliary Building and Warehouse are less than 0.125"and is considered negligible as noted in Section 3.3 of Revision 3 of this calculation.

Therefore SAM's analysis was not performed.

The details extracted from Section 3.3 are documented in Section 6.8 of this calculation.

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATiON NUMBER PAGE 17 CALCULATION NO, REV NO CCN NO MP58B-00138EM 04 NIA 4.0 Methods (continued)

E. Computer ;Programs The NUPIPE-SWPC program (Ref. 6a) is designed to perform analysis in accordance with the ASME Boiler and Pressure Vessel Cod, Section MI Nuclear Power Plant ('oMrpwenLs.and~als; th S ISA ANSI B3 1.l:0 'PowerPiping Code: This progmpffrisaiiie *l*sfanalyis of tre- " .......

dimensional piping systems subjected to various thermal, static and dynamic loading conditions.

The NUDL-PC program (Ref. 6b) is a load combination generator that serves as an aid in the design of pipe support and equipment nozzles. The program reads the pipe support or equipment nozzle loads and global deflections from a file (called CADEPS) created by NUPIPE-SWPC, combine them according to a set of specified combination equations, and outputs to a disk file in a tabular format.

The NUPIPE-SWPC and NUDL-PC analyses were performed on a computer system named "1MV7491" which has been designated as a QS 2.7 machine in accordance with Section 11.5.2 of the Shaw Stone

& Webster Nuclear Quality Standard Number QS 2,7, Rev. F (Ref. 7).

This system is an IBM compatible Personal Computer "DELL" with Pentium 4 CPU, 3.2 GHz with 2.0 GB of RAM, using the Microsoft Windows XP Professional Version 2002, Service Pack 1 Operating System.

F. Support 60542 Design Loads Pipe support anchor 60542 is considered to be the "seismic/non-seismic" boundary anchor isolating the non-seismic portion of the piping system from the safety related seismic portion of the piping system.

To meet the intent of section 3.2 (item c, seismic/non-seismic boundaries) of Specification SP-M2-ME-030 (Reference 4), the design loads for this support will be determined by "doubling" the existing NUDL-PC based design loads in order to account for the effects of the non seismic piping located beyond the NUPIPE-SWPC analytical model. It should also be noted that two additional supports beyond the seismic/non-seismic anchor 60542 (that are part of the computer model) will be designed considering the seismic loads that were determined by the NUPIPE-SWPC analysis.

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 18 CALCULATION NO. REV NO CCN NO MP588.00138EM 04 N/A

5.0 REFERENCES

1. American National Standard Institute Code for Pressure Piping, ANSI B3 1.1, 1967 Edition; All applicable addenda up to and including Summer 1973 Addendum.

2. Millstone Unit 2 FSAR Criteria.

3. No"t rsed. .... .

4. SP-M2-ME-030 Rev. 01 dated 12/13/00 "Specification for Rigorous Piping Stress Analysis and Pipe Support Design."

5. Design Change Notice (DCN) No.;

a. DM2-00-0345-08 "Replace "A" Train Service Water 10" Supply Line to EDG Coolers with AL-6XN Material."

b. DM2-00-0225-08 "Replacement of Service Water Spool P-14 with AL-6XN Material and Ainubar Flow Measuring Connection Replacement to FE-6397."

DM2-00-0055-08 "Removal of "B" Diesel Generator Servioe Water Inlet Strainer (L3SOB)."

S

d. DM2-00-0054-08 "Removal of"A" Diesel'Generator Service Water Inlet Strainer (L350A)."

e. DM2-00-0054-08 "Removal of"A" Diesel Generator Service Water Inlet Strainer (L350A)."

6. Computer Codes:

a. NUTIPE-SWPC, ME-1 10.01, "Stress Analysis of Nuclear Piping," Version 01, Level 00.

b. NUDL-PC, ME-268.01, "Nupipe Support Structural Design Loads," Version 01, Level 00.

7. Shaw Stone & Webster Nuclear Quality Standard, "Computer Software," QS 2.7, Rev. F.

8 Tube Turn Catalog 311, pages 101 -103.

9. Crane Catalog No. 61 - "Welding Fittings Forged Flanges."

10. ITT Grinnell Industrial Piping, Inc. "Pipe Design and Engineering," Fifth Edition, 1976.

11. Specification No. SP-MNE-668 "Millstone Unit 2 Class Sheets," Revision 4.

12. Not Used.

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 19 CALCULATiON NO. REV NO CON NO MP58B-00138EM 04 N/A

5. REFERENCES (continued)

13. Dominion Piping Drawing Number Revision Number

a. 25203-20224 SH 58 4

b. 25203-20224 SH 57 3 C. 25203-20224 SH 56 4

d. 25203-20224 SH 61 2 25203 2022.S.

.. 1 7 2.

f. 25203-20224 SH 60 2

g. 25203-20146 SH 1029 8

h. 25203-20146 SH 1028 7

i. 25203-20150 SH 1014 3

14. Seismic Analysis Input Data Sources:

Millstone Point Building Floor Response Spectra developed by Bechtel Corporation.

Amplified Response Spectra Curves The curves are as noted on Millstone Unit 2, Revision 3 sheet no. 12 of this calculation.

(See Attachment D)

The ARS curves are hand input in NUPIPE-SWPC run.

Building(s) Location Elevation Dampin Auxiliary Building 14'-6" 0.5% (OBE)

(Horizontal Accelerations X and Z Directions)

Vertical Accelerations are 2/3 of the ground acceleration (i.e. 2/3 of 0.09gs) or 0.06gs for OBE and 0.1 13gs for DBE.

A review of ARS indicates that the input ARS"is conservative in the area of the peak through the ZPA relative to the vertical accelerations input.

15. WALWORTH Valve Catalog 130.

16. LADISH Fittings- Catalog No 55.

17. Pipe Support Drawing: Dominion Dwg. No. 25203-22200 SH. 60542 Revision 1.

18. Allegheny Ludlum, "Stainless Steel AL-6XN Alloy (UNS Designation N08367),"

Technical Data Bluesheet B155, 1998.

19. ASME, Procedure for the Evaluation and Design of Rectangular Cross Section Attachments on Class 2 or 3 Piping," B&PV Code, Section M, Division 1, Code Case N-318-3, 1985.

20. Pipe Support Drawing Nos. 25203-22200, SH. 60469A through 60469H, Revision 2.

21. Pipe Support Drawing Nos. 25203-22200, SH. 427094 aud 427094A, Revision 6.

22. Pipe Support Calculations (Refer to table provided in Attachment E for list of pipe support calculations).

23. Calc.98-209, Revision 0, "Determination of Maximum Allowable Moment on a 8" 125# Light Weight Slip-On Flange."

I

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 20 CALCULATION NO. REV NO CCN NO MP58B-00138EM 04 N/A 6.0 DESIGN INPUT The following design input pages consist of data obtained from various sources which is required to perform the stress analysis of this piping system. This data is assembled in a manner which is suitable for input into the NUPIPE-SWPC analysis.

II__I t-r-

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 21 CALCULATION NO. REV NO l CN NO MP58B-00138EM 04 1 NIA 6.0 Design Input 6.1 Basic Analytical Data TABLE 6.1.1 Line ie

• - -- - -4

....E ing (psi) I Pressure Temp. Pressure Temp. of Expansiorl Diameter [Thickness Pipe X 10 8 (psi) (f) (psi) ['F) inif (in) (In) 24"-JGD-1 JGD A53 GR,8 27.9 150 100 150 Note 1 Note 1 24 0,.87 24'-JGD-3 JD A53 GR.8 27.9 150 100 150 Note 1 Note 1 24 0.687 10"-JGD-4 JG0 A53 GR,B 27.9 150 100 150 Note I Note 1 10.75 0.365 8"-JGO-4 JD A53 GR.8 27.9 150 115 150 NoteI Note 1 8.625 0.322 8"-J,£-7 .10 A53 GR.8 27.9 150 115 150 Note 1 Note .1 8.25 0.322 6"-JGD-4 JGD A53 GR8 27.9 150 115 150 Note I Note 1 6.625 0.280 6"-JGD-7 SOD A531.8 27.9 150 11SR, 150 Note 1 Note 1 5.625 0.280 60-JB8D-26 .15 A106 GR.Z 27.9 150 115 150 Note 1 Note 1 6.625 0.280 3/4" Vent, Drain 80 AS3 GR.B 27.9 ISO 115 150 Note I Note 1 1.05 0.154 1 Drain .10 A.53 GR.8 27.9 150 115 160 Note 1 Note 1 1.315 0.179 1.55"-HCD-91 lCD A53011.8 27.9 150 115 150 Note I Note 1 1.9 O0200 2.5"-JGD JGD A53 GR, 27.9 160 100 150 Note 1 Note 1 2.875 020 3/4-HCD Vent HCD A53CR 9 29 180 100 1 N0tel Note 1 1.05 0.113 Reference 1-13= 11, 13 1 Ioe Note See3 Not SSee Note 4 10.9 10 i_

Line Contents Wt. Insulation "Sc-...

Total I (in) I

-Ibsfft (Psi)- ol 24'-JGD-1 Water 355.47 1.5 1 15000 18000 35000 24*-JGD-3 Water 355.47 1.5 I 15000 15000 35000 . .i. . . . .i. . .

1t.t-JGD-4 W ater 79.02 1.5 I 15000 15000 35000 8.JG0-4 Water 83.85 1.5 I 15000 15000 35000_..

8.-JGD-7 Water 50.24 1.5 I 15000 15000 35000 6"-JGD-4 Water 31.48 0 N/A 15000 15000 35000 6"-JGD-7 Water 31,48 0 NIA 15900 15000 35000

'--JBL-26 Water 31.48 0 NIA 15uu0 *5grJO 314" Vent, Drain Water 1,.62 0 NIA 15000 15000 35000 1" Oratn Water 2.483 0 N/A 15000 15000 350D0 1.5"-HCD.91 Water 4.395 0 [ N/A 15000 1500D 35000 2.5'-JGD Water 9.58 0 NIA 16000 16000 35000 3/4-HCD Reference Vent Wa-tor

.109 1.36 0 13 N/A 1 16000 1

15)000 1

35000 C13 1

Notes:

1. For details see system operational modes Section 6.5.

2. Sb and Sy is based on maximum operating temperature of 1150 F.

3. Design Pressure of 150 psi is considered for the entire problem and is conservative.

4. Design Pressure is considered as Maximum Operating Pressure and is conservative.

5. Design Temperature is based on the Maximum of Design or Operating Temperature as noted in Section 3.6 of Revision 3 of this calculation.

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 22 CALCULATION NO. REV NO CCN NO MP58B-00138EM 04 NIA 6.0 Design Input (Continued) 6.1 Basic Analytical Data (continued)

TABLE 6.1.2 (Rellaced Pioe)

Line Pipe Material E.16 I Des n Max. Operating Co-Eff. I Outside Wan

-fpsJ--I -iem~-I

-Pes~re- -ressrr T orixan UFý.-

... arnii eter.-J.WcJtneso X10* ~F)

Pipe (psi) (Ff) (psi) ("F) in/ft I (n) I (n) 24"-JGD-1 JG6 B675UNSN08367 28.3 150 00 150 Note 1 Note 1 24 0,375 24".JGD-3 JGO 8675UNSN08367 28.3 150 100 150 Note 1 Note 1 24 0.375 10".JGD-4 J13 B675UNSN08367 28,3 150 100 150 Note 1 Note 1 10.75 0.365 8"-JGD-4 B675UNSN08367 BJGO 28.3 150 115 150 Note I Note 1 8.525 0,322 8`-JGD-7 JGD 8675UNSN08367 2B3 150 115 150 Note I Note 1 8.625 0.322 6"-JGD,4 JO B675UNSN08367 28.3 150 115 150 Note Note 1 6.625 0,28 6"-JfD-4 .0-0 B675UNSNO8367 28.3 150 115 150 Note 1 Note 1 6.625 1 0,28 1.Y-.C,-91(B*-anch) HCD B6_75UNSNO8367 2 1 1 150 Note 1 Note 1 1. "0.145 Reference 13 11,13 18 See Note See Note SSee Note 41_

Line Contents WI. Insulation1 Designation " Total Thck T Sc Sh . Sy

_______ bs/ft -- (In) _ __ _ _I (psi) (psi 24"-JGD-1 Water 290.81 1.5 [ I " 20200 20200 47000 24"-JGD-3 Waler 290.81 1.5 I 20200 20200 47000

... ..... . . . .. . .J 10"-JGD-4 Water 80,20 1.5 1 20200 20200 47000 B"-JGD-4 Water i 20200 20200 47000 °.

8"-JGD-7 Water 1.5 20200 20200 47000 ............................-. -1 6"-JGD-4 Water 31.86 0 _ NA 20200 20200 47000 _

.. . .. . .. . .. ... .1 6"-JGD-7 Water 31.86 0 1W A 20200 20200 47000 1.5"-HCO-91(Branch) Water 3.653 0 N/A 20200 20200 47000 Reference I I 10, *13" 13 18 18 " 18 1 Notes:

1. For details see system operational modes Section 6.5.

2. Sh is based on maximum operating temperature of 1] 50 F.

Sy, is based on temperature of 200' F to be conservative.

3. Design Pressure of 15 0 psi is considered for the entire problem and is conservative.

4. Design Pressure is considered as Maximum Operating Pressure and is conservative.

5, Design Temperature is based on the Maximum of Design or Operating Temperature as noted in Section 3.6 of Revision 3 of this calculation.

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 23 CALCULATION NO. REV NO CCN NO MP58B-0013BEM 04 NIA 6.0 Design Input (Continued) 6.2 Piping Data Ref. X SECTION CARD No. L2-9 No.

1 . hk T TNP NAP.~Tt* '24".I*VJ.; *4".]Gf%2 CAhIhP ('1 .A£,

T P__ NUBP 24I01- 24.GI CLSS CODE*~*-- 3

..-3a~b. LIN E.CLASS I .... JGD --................ ... ESIG N -.PR ES SU R ,E: .

• .D 150-PSI- ..... . .............................................

1 13a,b SCHEDULE: 40 CONTENTS: Water 13a b PIPING MATERIAL: AS3 Or. B ......... .

10 OUTSIDE DIAMETER: 24.0 In WALL THICKNESS: 0.687 In

.3J b INSULATION THICKNESS: 1.5 in. INSULATION TYPE: I INSULATION DENSITY ***: 12 LB/ CUBIC FT INSULATION MATERIAL: Calcium Silicate I 'P' NUMBER (WELDING REF. No.): I E COLD: 27.9 x E 06 PSI 10 PIPE WEIGHT:-* 171.16 LB/FT.- CONTENTS WEIGHT: 174.10 LB/FT 10 INSULATION WEIGHT:*" 10.21 LB/FT TOTAL PIPE WEIGHT: 355.47 LB/FT, Note: *"Insulation Density is taken from Section 3.6 of Revision 3 of this calculation, Xsection 2 includes only Contents and Insulation weights.

Xsection 9 for Valve Operator considers Design Pressure and Total Pipe Weight as Zero.

Ref. X SECTION CARD No. 3.4.10 .

No.

13b-f LINE NUMBER: I0"-JGD-4 CODE CLASS: 3 13b-f LINE CLASS: JOD DESIGN PRESSURE: 150 PSI 13b-f SCHEDULE: 40 CONTENTS: Water 13b-f PIPING MATERIAL: A53 Gr. B 10 OUTSIDE DIAMETER. 10.75 In WALL THICKNESS: 0.365 In l3b-f INSULATION THICKNESS: 1.5 In. INSULATION TYPE: I INSULATION DENSITY ***; 12 LB/ CUBIC FT INSULATION MATERIAL: Calcium Silicate I 'P' NUMBER (WELDING REF. No.ý: I E COLD: 27.9 x E 06 PSI 10 PIPE WEIGHT:* 40.11 LB/FT CONTENTS WEIGHT: 34.10 LB/FT

.10 INSULATION WEGHT:** 4.81 LB/FT TOTAL PIPE WEIGHT: 79.02 LB/FT .,

Note: ***Insulaaiorn Density is taken from Section 3.6 of Revision 3 of this calculation.

Xsection 4 includes only Contents and Insulation weights.

Xsection 10 for Valve Operator considers Design Pressure and Total Pipe Weight as Zero.

Ref. 10 10.68t (D-t) For Carbon Steel 10.89t (D-t) For Austenitic Stainless Steel B-675 UNS No8367 0.3405(Di)9 Weight of Water per foot (LB)

"* Insulation weight = 0.0218 d K (D+K) LB / FT d - Insulation Density (LBS/Cubic Foot)

D -Outside Diameter ofPipe (IN)

K - Insulation Thickness (lIN) t = Pipe Wall Thickness (IN)

Di - Inside Diameter of Pipe (IN)

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 24 CALCULATION NO, REV NO CCN NO MP58B-001 3SEM 04 N/A 6.0 Design Input (Continued) 6.2 Piping Data (cont.)

Ref. X SECTION CARD No. 5, 6 1I. and 20 No. (Xsection 20 is used for 8"-JGD-7 on Iso.s 1028, 1029 and is not insulated)

I I 1 77 - I I I _

-.1.3eJN1*.N

,-J A..... M. a.dUU-4~ 5'-J(~~IJ-I. -FLULThA:LASS............

13e,g,h LINE CLASS: JOD DESIGN PRESSURE: 150 PSI 13e,g,h SCHEDULE: 40 CONTENTS: Water 13e,g,h PIPING MATERIAL: A53 Gr. B 10 OUTSIDE DIAMETER: 8.625 In WALL THICKNESS: 0.322 In 13eg,h INSULATION THICKNESS: 1.5 In. INSULATION TYPE: I INSULATION DENSITY ***: 12 LB/.CUBIC FT INSULATION MATERIAL: Calcium Silicate I 'P' NUMBER (WELDING REF. No.): I E COLD: 27.9 x E 06 PSI 10 PIPE WEIGHT:* 28.19 LB/FT CONTENTS WEIGHT: 21.69 LB/FT 10 INSULATION WEIGHT:." 3.97 LB/FT TOTAL PIPE WEIGHT: 53.85 LB/FT Note: ***Insulation Density is taken from Section 3.6 of Revision 3 of this calculation.

.. _ Xsection 6 includes only Contents and Insulation weights.

Xsection 1I for Valve Operator considers Design Pressure and Total Pipe Weight as Zero.

Xseetion 20 includes Pipe weight and Contents weight of 50.24 Lbs/ft instead of 49.88 Lbs/ft and is conservative.

Ref. X SECTION CARD No. 7,j*2 No.

13g,hj, LINE NUMBER: 6"-JGD-4, 6"-JGD-7; 6"-JBD-26 CODE CLASS: 3 13g,hi LINE CLASS: JGD; JBD DESIGN PRESSURE: 150 PSI 13g,h,i SCHEDULE: 40 CONTENTS: Water 13g,hi PIPING MATERIAL: A53 Gr, B; A106 Or. B 10 OUTSIDE DIAMETER: 6.625 In WALL THICKNESS: 0.280 In 13g,hLi INSULATION THICKNESS: N/A In. INSULATION TYPE: N(A INSULATION DENSITY ***: N/A INSULATION MATERIAL: NIA I P'NUMBER (WELDING REF. No.): I E COLD- 27.9xE06 PSI 10 PIPE WEIGHT:* 18.97 LBfFT CONTENTS WEIGHT: 12.51 LB/FT INSULATION WEIGHT:** N/A TOTAL PIPE WEIGHT: 31.48 LB/FT Note: Xsection 8 includes only Contents weight.

Xsection 12 for Valve Operator considers Design Pressure and Total Pipe Weight as Zero.

Ref. 10 10.68t (D-t) For Carbon Steel 10.89t (D-t) For Austenitic Stainless Steel B-675 UNS N08367 0.3405(Di)' Weight of Water per foot (LB)

Insulaton weight= 0.0218 d K (D+K) LB/FT d = -Insulation Density (LBS/Cubie Foot)

D = OutsideDiameterofPipe (IN)

K = Insulation Thickness (IN) t - Pipe Wall Thickness (IN)

Di = Inside Diameter of Pipe (IN)

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 25 CALCULATION NO, REV NO CCN NO MP58B0013SEM 04 N/A 6.0 Design Input (Continued) 6.2 Piping Data (cont.)

Re[ X SECTION CARD No. 13.14 No. fFor Rcolaced Spool Piece Pining) 13a,b LINE NUMBER. 24"-JGD-1, 24"-JGD-3 CODE CLASS: 3 13a,b LINE CLASS: JGD DESIGN PRESSURE: 150 PSI 13a,b SCHEDULE: 20 CONTENTS: Water 13a0b PIPING MATEPRAL: B-675, UNS N09367 10 OUTSIDE DIAMETER 24.0 In WALL THICKNESS: 0.375 In 13ab INSULATION THICKNESS: 1.5 In. INSULATION TYPE: I INSULATION DENSITY ***: 12 LB/ CUBIC FT INSULATION MATERIAL: Calcium Silicate I 'P' NUMBER (WELDING REF. No.): 8 E COLD: 28.3 x E 06 PSI l0 PIPE WEIGHT:* 97.00 LB/FT CONTENTS WEIGHT: 183,80 LB/FT 10 INSULATION WEIGHT:** 10.01 LB/FT .....

TOTAL PIPE WEIGHT: 290.81 LB/FT Note: ***Insulation Density is taken from Section 3.6 of Revision 3 of this calculation.

Xsection 14 includes only Contents and Insulation weights.

Ref. X SECTION CARDNo. 15_16 No, (For Replaced Spool Piece Piping) 13b-f LINE NUIABER: I 0"-JGD-4 CODE CLASS: 3 I3b-f LINE CLASS: JGD DESIGN PRESSURE: 150 PSI 13b-f SCHEDULE: 40 CONTENTS: Water 13b-f PIPING MATERIAL: B-675, UNS N08367 10 OUTSIDE DIAMETER: 10.75 In WALL THICKNESS: 0.365 In 13b-f INSULATION THICKNESS: 1.5 In. INSULATION TYPE: I

"" _ INSULATION DENSITY ***: 12 LB/ CUBIC FT INSULATION MATERIAL: Calcium Silicate I 'P' NUMBER (WELDING REF. No,): 8 E COLD: 28.3 x F 06 PSI 10 PIPE WEIGHT:* 41.30 LB/FT CONTENTS WEIGHT: 34.10 LB/FT 10 INSULATION WEIGHT:** 4.80 LB/FrT TOTAL PIPE WEIGHT: 80.20 LB/FT Note: **Insulation Density is taken from Section 3.6 of Revision 3 of this calculation.

.Xsection 16 includes only Contents and Insulation weights and is not used in the calculation.

Ref. 10 I0.68t (D-t) For Carbon Steel lO.89t (D-t) For Austenitie Stainless Steel B-675 UNS N08367 0.3405(Di)ý Weight of Water per foot (LB)

• • Insulation weight - 0.0218 d K (D+K) LB/FT d = Insulation Density (LBS /Cubic Foot)

D = Outside Diameter of Pipe ON)

K = Insulation Thickness (IN) t = Pipe Wall Thickness (IN)

Di - Inside Diameter of Pipe (IN)

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 26 CALCULATION NO. REV NO I CCN NO MP58B-00138EM 04 N/A 6.0 Design Input (Continued) 6.2 Piping Data (cont.)

Ref. X SECTION CARD No. i7_ 18 No. rFor Renlan~d Snool Pece P~nin~'l No. (For Replaced Snaol Piece Pining) 13e,gh LINE NUMBER: 8"-JGD-4, 8"-JGD-7 CODE CLASS: 3 13e,g,h LINE CLASS: JGD DESIGN PRESSURE: 150 PSI 13e,g,h. SCHEDULE: 40 CONTENTS: Water 13e,gh PIPING MATERIAL: B-675, UNS NO8367 10 OUTSIDE DIAMETER: 8.625 In WALL T1-ICKNESS: 0.322 In 13eg,h INSULATION THICKNESS: 1.5 In. INSULATION TYPE: I INSULATION DENSITY ***: 12 LB/ CUBIC FT INSULATION MATERIAL: Calcium Silicate

..I. 'P' NUMBER (WELDING REF. No.): 8 E COLD: 28.3 x E 06 PSI 10 PIPE WEIGHT:* 29.03 LB/FT CONTENTS WEIGHT: 21.69 LB/FT 10 INSULATION WEIGHT:** 3.97 LB/FT TOTAL PIPE WEIGHT: 54.69 LB/FT Note: **"Insulation Density is taken from Section 3.6 of Revision 3 of this calculation.

Xszction 18 includes only Contents and Insulation weights and is not used in the calculation.

Ref. X SECTION CARD No. 19 No. (For Replaced Spool Piece Piping) 13g,h LINE NUMBER, 6"-JGD-4, 6"-JGD-7 CODE CLASS: 3 13g,h LINE CLASS: JGD DESIGN PRESSURE: 150 PSI 13g,h SCHEDULE: 40 CONTENTS: Water 13g,h PIPING MATERIAL: B-675, UNS NO8367 10 OUTSIDE DIAMETER: 6.625 In WALL THICKNESS: 0.280 In

]3g,h INSULATION THICKNESS: N/A INSULATION TYPE: N/A INSULATION DENSITY ***: N/A INSULATION MATERIAL: N/A I 'P' NUMBER (WELDING REF- No.): 8 E COLD: 28.3 xE 06 PSI PIPE WEIGHT:* 19.35 LB/FT CONTENTS WEIGHT: 12.51 LB/FT INSULATION WEIGHT:- N/A TOTAL PIPE WEIGHT: 31.86 LB/FT Ref 10

• I0.68t(D-t) For Carbon Steel 10,89t (D-t) For Austenitic Stainless Steel B-675 UNS N08367 0.3405(Di)2 Weight of Water per foot (LB) iinsulation weight = 0.0218 d K (D+K) LB / FT d - Insulation Density (LBS /Cubic Foot)

D - Outside Diameter of Pipe (IN)

K - Insulation Thickness (IN) t - Pipe Wall Thickness (IN)

Di = InsideDiameter of Pipe(IN)

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 27 REV NO CCN NO CALCULATION NO.

IMP55B-00138EM 04 N/A 6.0 Design Input (Continued) 6.2 Piping Data (cont.)

Ref. X SECTION CARD No. 2122 No.

I i i . i 1. 13i LINE NUMBER: 3/4 Inch Vent and Drain Lines CODE CLASS; 3 13i LINE CLASS: JBD DESIGN PRESSURE: 150 PSI 13i SCHEDULE" 80 CONTENTS: Water 13i PIPING MATERIAL: A106 Gr..B 9 OUTSIDE DIAMETER- 1.050 In WALL THICKNESS: 0,154 In 13i INSULATION THICKNESS: N/A INSULATION TYPE: N/A INSULATION DENSITY : N/A INSULATION MATERIAL: N/A I 'P' NUMBER (WELDING REF. No,): I E COLD: 27.9 x E 06 PSI 9 PIPE WEIGHT:* 1.474 LB/FT CONTENTS WEIGHT: 0.188 LB/FT INSULATION WEIGHT:** N/A ......

TOTAL PIPE WEIGHT: 1.662 LB/FT ....

Note: Xsection 22 includes only Contents waight.

Ref. X SECTION CARD No. 23,24 No.

13i LINE NUMBER: I Inch Drain Line CODE CLASS: 3 13i LINE CLASS: 181 DESIGN PRESSURE: 150 PSI 13i SCHEDULE: 80 CONTENTS: Water 13i PIPING MATERIAL: A106 Gr. B 10 OUTSIDE DIAMETER 1.315 In WALL THICKNESS: 0.179 In 13i INSULATION THICKNESS: N/A INSULATION TYPE: N/A INSULATION DENSITY ***: N/A INSULATION MATERIAL: N/A I 'P' NUMBER (WELDING REF. No.): I E COLD: 27,9 x E 06 PSI 10 PIPE WEIGHTT:, 2.172 LB/FT CONTENTS WEIGHT: 0.311 LBfFT' INSULATION WEIGHT:" N/A TOTAL PIPE WEIGHT: . 2,483 LB/FT Note:

Xseetion 24 includes only Contents weight.

Ref. 10 I0.68t (D-t) For Carbon Steel 10.89t (D-t) For Austenitic Stainless Steel B-675 UNS NO8367 0.3405(Di)2 Weight of Water per foot (LB)

• '* Insulation weight= 0.0218 d K (D+K) LB 1 FT d = Insulation Density (LBS (Cubic Foot)

D = Outside Diameter of Pipe (IN)

K = Insulation Thickness (IN) t = Pipe Wall Thickness (IN)

Di - Inside Diameter of Pipe (IN)

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 28 CALCULATION NO, REV NO I CCN NO MP58B-00138EM 04 N/A 6.0 Design Input (Continued) 6.2 Piping Data (cont.)

Rerf X SECTION CARD No. 25.26 I No.

I - I-- -... I f. -. I7tT77 [

13Rh LINE NUMBER: I.5"-HCD-91 CODE CLASS: 3 3Rh LINE CLA.SS: HCD DDESIGN PRESSURE: 150 PSI 13,h -SCHEDULE: 8D CONTENTS: Water 13g-h PIPING MATERJAL: A53 Gr. B ....

10 OUTSIDE DIAMETER: 1.900 In WALLTHIICKNESS: 0.200 In 1.3gh INSULATION THICKNESS: N/A INSULATION TYPE: N/A INSULATION DENSITY ***" N/A INSULATION MATERIAL: N/A I 'P' NUMBER (WELDING REF. No,): I E COLD: 27.9 x E 06 PSI t0 PIPE WEIGHT:* 3.631 LB/FT CONTENTS WEIGHT: 0.765 LB/FT INSULATION WEIGHT:"* N/A

_____.... TOTAL PIPE WEIGHT: 4.396 LBIFT Note: XseCtion 26 includes only Contents weight.

Ref. X SECTION CARD No. 2*

No.

13g,h LINE NUMBER: 1.5"-HCD-91 (Between nodes 9455- 9460) CODE CLASS: 3 13g,h LINE CLASS: HCD DESIGN PRESSURE: 150 PSI 13g.h SCHFDULE: 40 CONTENTS: Water 13g,h PIPING MATERIAL: B.675, UNS N08367 10 OUTSIDE DIAMETERP 1.900 in WALL THICKNESS: 0.145 In 13g0 INSULATION THICKNESS: NIA INSULATION TYPE: N/A INSULATION. DENSITY ***:. N/A INUAINMTRAN/A I ...'P'NU.MBER (WELDING *RE. No.):' 8 E COLD- 28.3 x E 06 PSI" 10 PIPE WEIGHT:* 2,771 LBIPT., CONTENTS WEIGHT: 0.8_82 ,LBfFT.

INSULATION WEIGHT.-** N/A

'TOTAL PIPE WEIGHT. 3,653 LBtFT.....=

Ref. 10 10.68t (D-t) For Carbon Steel 10.89t (D-t) For Austenitic Stainless Steel B-675 UNS NO8367 0.3405(Di)2 Weight of Water per foot (LB)

• Insulation weight - 0.0218 d K (D+K) LB / FT d = Insulation Density (LBS /Cubic Foot)

D = Outside Diameter of Pipe (IN)

K - Insulation Thickness (IN) t - Pipe Wa)l Thickness (IN)

Di - Inside Diameter of Pipe (tN)

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 29 CALCULATION NO. REV NlO CCN NO MP58B-00138EM 04 N/A 6.0 Design Input (Continued) 6.2 Piping Data (cont.)

Ref.___ X SECTION CARD No. 28 3

Nn. (Ccn~n~t~ to 3/4 HCD Vent I n~ in ih~ Valve.r 2.~W-1OOA rn No___ (Cnnct to31 DVet ie o heVlvs -W- AB 13e LINE NUMBER: 2,5 Inch-IGD Line CODE CLASS: 3 B3e LINE CLASS: JOD DESIGN PRESSURE: 150 PSI 13e' SCHEDULE, 40 CONTENTS: Water 13e PIPING MATERIAL: A53 Or. B 10 OUTSIDE DIAMETER: 2.875 In WALL THICKNESS: 0.203 In 13e INSULATION THICKNESS: 1.5 In. INSULATION TYPE: N/A INSULATION DENSITY ***: 12 LB/ CUBIC FT INSULATION MATERIAL: Calcium Silicate I 'P 'NUMBER (WELDING REF. No.): I E COLD: 27.9 x E 06 PSI 10 PIPE WEIGHT:* 5.79 LB/FT CONTENTS WEIGHT: 2.07 LB/FT 10 INSULATION WEIGHT:-* 1.72 LB/FT TOTAL PIPE WEIGHT: 9.58 LB/FT .... .._ _ .

Note: **1Insulntion Density is taken from Section 3.6 of Revision 3 of th is calculation.

Ref. X SECTION CARD No. 2 No. (3/4 HCD Vent Line to the Valves 2-S W-I00A, B)

I3e LINE NUMBER. 3/4 Inch CODE CLASS: 3 l3e LINE CLASS: HCD DESIGN PRESSURE: 150 PSI 13e SCHEDULE: 40 CONTENTS: Water 13e PIPING MATERIAL: A53 Or, B t0o OUTSIDE DIAMETER: 1.050 In WALL THICKNESS: 0.113 In 13c INSULATION THICKNESS: N/A INSULATION TYPE: N/A INSULATION DENSITY ***: N/A INSULATION MATERIAL: N/A 1 P'"NUMBER (WELDING REF. No,):. I E COLD: 27.9 xE 06 PSI t0 PIPE WEIGHT:* 1.13 LB/FT CONTENTS WEIGHT: 0,230 LB/FT INSULATION WEIGHT:-"* NA TOTALPIPE WEIGHT: 1.360 LB/FT__

Ref. 10 10.68t (D-t) For Carbon Steel 10.89t (D-t) For Austenitic Stainless Steel B-675 UNS N08367 0.3405(Di)2 Weight of Water per foot (LB)

Insulation weight 0.0218 d K (D4+K) LB I FT d = Insulation Density (LBS /Cubic Foot)

D = Outside Diameter of Pipe (IN)

K = Insulation Thickness (IN) t = Pipe'Wall Thickness (IN)

Di = Inside Diameter of Pipe (IN)

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 30 CALCULATION NO, REV NO CCON NO MP58B-0O0138EM 04 N/A 6.0 Design Input (Continued) 6.2 Piping Data (cont.)

Ref. X SECTION CARD Nc. 30 SECTION X Anr~hor CARD No. 30 No. (Trunnions are used for Mod& (Mar-k No~ 60S42~ n~N~d~ 7050\

No (Tunin ar usdfr nhr oe (akNo6S2)a od 00 131 LINE NUMBER: 3 inch Trunnion CODE CLASS: 3 LINE CLASS: DESIGN PRESSURE: 0 PSI I0 .. SCHEDULE: 40 CONTENTS: Water 10 PIPING MATERIAL: A53 Gr. B 10 OUTSIDE DIAMETER: 3.500 In WALL THICKNESS: 0.216 In INSULATION THICKNESS: N/A INSULATION TYPE: N/A INSULATION DENSITY ***: N/A INSULATION MATERIAL: N/A I 'P' NUMBER (WELDING REF, No.): I E COLD: 27.9 x E 06 PSI 10 PIPE WEIGHT:" 7.58 LB/FT CONTENTS WEIGHT: NIA INSULATION WEIGHiT:** N/A .. .....

TOTAL PIPE WEIGHT: 7.58 LB/FT ...........

Ref. X SECTION CARD No. N/A No,

'__ LINE NLUMBER: CODE CLASS:

LINE CLASS: DESIGN PRESSURE: PSI SCHEDULE: CONTENTS: r PIPING MATERIAL:

OUTSIDE DIAMETER: in WALLTHICKNESS: In INSULATION THICKNESS: In. INSULATION TYPE:

INSULATION DENSITY "**: LB/ CUBIC FT INSULATION MATERIAL:

'F' NUMBER (WELDING REF. No.): Z COLD: PSI PIPE WEIGHT:* LB/FT CONTENTS WEIGHT: LB/FT INSULATION WEIGHT:," LB/FT

.. TOTAL PIPE WEIGHT: LB/FT ' _"'_ .. _ .

Ref. 10 . . .. ,, ,.,,.....,

10.68t (D-t) For Carbon Steel 10.89t (D.t) For Austenitic Stainless Steel B-675 IJNS N08367 2

0.3405(Di) Weight of Water per foot (LB)

"* Insulation weight= 0.0218 d K (D+K) LB / FT d = Insulation Density (LBS/Cubic Foot)

D = OutsideDiameterofPipe ON)

K = Insulation Thickness (IN) t = Pipe Wall Thickness (IN)

Di = Inside Diameter of Pipe (IN)

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 31 CALCULATION NO. REV NO CCN NO MP58B-00138EM 04 NIA 6.0 Design Input (Continued) 6.3 Valve Data TABLE 6.3,1 (Valve Data)

Size Type Node C.G. Location (ft.) otal Rf, Pl_

NX (Lbs.)

24 2-SW-8A 22 3.15 ' ,, 925 13.a 2-SW-31A 92 -2.64 975 M3.a 2-SW-7B 166 3.15 925 13.a 2-SW-7A 192 3.15 (2) 925 131a 2-SW-3.1B 226 -2.64 975 13.a 2-SW-SB 312 . 3.15 " 925 13.a 2-SW-SC 352 3.15 925 13.a 8 2-SW-12A 1206 0.252 -0.173 292(3) 13.e 2-SW-12B 1282 . . 0.31. 292(3) 3.e 2-SW-12C 1316 0.31 292(3) 13.e 2-SW-12D 1366 -0.31 292(3) 13.e 8 2-SW-231B 1576 -0.15 0.16 -1.07 347(4) 13.g 8 2-SW-231A 2022 -0.15 0,16 -1.07 347(4) 13.h 6 2-SW-89B 1736 0.97 -0.19 -0.26 135(5) 13.&

6 2-SW-89A 2162 0-97 -0.19 -0.26 135(5) 13.h1 6 2-SW-297 7006 124(6) 13.i 6 2-SW-296 7026 .. 124(6) 13Mi 3/4 2-FIRE-560 9008 2(.7) 13.i 1 2-FIRE-559 9108 3(7) 13.i 3/4 2-FIRE-259 9208 2(7) 13Ji W12 2-SW-241 9430 12(8) 13.h 1,"[ 2-SW-242 9330 12(8) 13.g 3/4 2-SW-100B 9515 __2(9) 13.e 3/4 2-SW-100A 9615 2(9) 13.e Notes;

1. C,G. locations are taken from Section 3.4 (sheet 14) of Revision 3 of this calculation and weights from the piping iso's or from the applicable Revision 3 Calculation Change Notices (CCN).

2. C.G. direction coded in NUPIPE-SWPC as +Y direction. Seismic results (Eq. 9) being low, the results of this analysis should be still acceptable.

3. Valve weight is revised from 80 lbs to 292 lbs per CCN 15 to Rev. 3 of this calculation.

4. C.G. location and valve weight revised per CCN 17 to Rev. 3 of this calculation.

5. Actuator wt. of 16 lbs is added to the existing valve wt. of 119 lbs per CON 13 to Rev. 3 of this calculation.

6. Valve Wt. is from Attachment B of CCN 8 to Rev. 3 of this calculation.

7. Valve Wt's are taken from sheet 10 of CON 10 to Rev. 3 of this calculation.

8. Valve Wt. is considered as 12 lbs (9.5 Lbs from page 76 of Walworth Catalog (Ref. 15)).

9. Valve Wt, is considered same as sheet 10 ofCCN 10 to Rev. 3 of this calculation.

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER CALCULATION NO. REV NO CCN NO PAGE 32 MP588-00138EM 04 N/A 6.0 DESIGN INPUT: (continued) 6.4 Flange Weight f Data TABLE 6.4.1 (Flange Weight Data)

I I - - -. - _7 I Pipe Node 125 Lb. Slip on 150 T-....--

Lb Slip I -

on 150 Lb. Total Flange Ref I , !Z7 , .. L WJ4MU4------------

4 -.

,UAWWV.---- i-F-41444.g9,%f------------ 4- -~r~r 4 W'4S-------

W64-699.-

....... (i.. - . .... F lii.*-I ...... ..... ........!.... . . .

24 15 268 268 16 25 113 113 8 35 113 204 317 8,16 70 2(204) 408 16 8 76 _96_(_.) ........ 16 24 77 2(204) 408 16 85 204 204 16 95 204 204 16 105 2(113) 226 8 115 204 268 472 16 145 268. 268 16 162 204 204 16 170 268 268 16 182 113 204 317 8,16 8 183 96(1) 16 24 185 204 204 16 195 268 268 16 210 204 268 472 16 222 204 204 16 230 204 204 16 242 2(204) 408 16 250 204 268 472 16 280 204 204 16 295 2(113) 226 8 308 113 113 8 315 268 268 16 325 113 113 8 340 2(204) 408 16 348 204 204 1.6 355 268 268 16 370 204 204 16 Note:

I. Wt. of 2 Blind Flanges from Ladish Catalog (Ref 16).

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER T PAGE 33 CALCULATION NO. REV NO CON NO MP58B-00138EM 04 N/A 6.0 DESIGN INPUT: (continued) 6.4 Flange Weight Data (continued)

TABLE 6.4.1 (Flange Weight Data) (continued)

Pipe --- Node 125 Lb Slip on 150 Lb Slip on 150 Lb. Total Flange Rcf

.... e------

...................... .... ................. i~;U~~)...............-g .-Wt-(s.))

10 380 , _ 2(40) 80 16 403 2(40) 80 1 430 26 40 66 8,16 445 2(26) 52 8 460 2(26) 52 8 485 2(26) 52 8 490 26 40 66 8,16 512 26 40 66 8,16 525 2(26) 52 8 550 2(26) _ " .... 58 52 . ....

580 26 40 66 8,16 595 .2(40) .... 80 16 610 2(40) 80 16 630 .. 2(40) 80 16 640 2(40) 80 16 645 2(40) _ 80 16 660 2(40) 80 16 665 2(40.)' ... 80 16 670 2(40) 80 16 685 2(40)., 80 16 690 2.(40,) ,,_ 80 16 705 2(40) . 80 16 710 _ 2(40), 80 16 715 2(40) ...... 80 16 730 , 80 92(40) 16 735 2(40) 80 16 750 2(40) 80 16 765 2(40) 80 16 785 26 40 66 8,16 800 26 40 66 8,16 835 26 40 66 8,16 855 2(26) .... . 52 8 870 2(26) .. .. _ 52 8 893 2(26) ........ . . [ ..... 52 8 895 2(26) 52 8 920 2(26) 52 8

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER RPAGE 34 CALCULATION NO, REV NO CCNNO MP58B-00138EM 04 N/A 6.0 DESIGN INPUT: (continued) 6.4 Flange Weight Data (continued)

TABLE 6.4.1 (Flange Weigbt Data) (contiuued)

Pipe Node 125 Lb. Slip on 150 Lb Slip on 150 Lb. Total Flange Ref.

",1,*I .

Q ~ ang k =-wPtFAu

'(in:) ... ... I, Fliang-e (L b s:) .. .. ........................... .......... ....... .......

I t 10 930 52 8 950 2(26) 52 8 980 2(26).. 52 8 995 2(26) 52 8 1015 26 40 66 8,16 1035

• _ 2(40) 80 16 1050 2(40) 80 16 1060 2(40) 80 16 1065 2(40) 80 16 1080 2(40) 80 16 1085 2(40) 80 16 1100 2L40) 80 16 1105 2(40) 80 16 1110 2(40) 80 16 1125 .2(40) 80 16 1130 J 2(40) 80 16 1145 2(40) .80 16 1150 2(40) 1 80 16 1155 40 54 94 16 8 1190 2(28)) 56 16 1195 2(28) 56 16 1202 28 28 16 1210 28 28 16 1220 2(28) 56 16 1265 .. 2(28) 56 16 1267 __ 2(28) 56 16 1275 28 28 16 1284 28 28 16 1290 28 42 70 16 1300 28 42 70 16 1302 2(28) 56 16 1310 28 28 16 1318 28 28 16 1325 2(28) 56 16 56_____ J- 16

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 35 CALCULATION NO. REV NO CCN NO MP58B-00138EM 04 N/A 6.0 DESIGN INPUT: (continued) 6.4 Flange Weight Data (continued)

TABLE 6.4.1 (Flange Weight Data) (continued) r ~ I. Y Pipe INode 125 Lb. Slip on 150 Lb Slip on 150 Lb. Total Ref.

shaG-Sim.I N - 1 te tb+" - - \

rn - -4 . ,i. - i +/- __

-t -

'(jijil....... Fl" efLbs.. (Lbs.)

11355 28 42 70 1357 2(28) 56 16 1362 28 28 16 1370 28 28 16 1380 28 42 70 16 1390 18 42 60 8,16 1410 2(18) 36 8 1430 218) 36 8 1440 2 18) ,36 &

1455 2(18) 36 8 1465 2(18) 36 8 1485 2(18) 36 8 1500 12(18) .... 36 8 1510 1208) 36 8 1515 2(18) 36 8 1525 18 28 46 8,16 1540 28 42 70 16 1570 42 42 16 1580 28 28 16 1585 .2(29) 56 16 1587 28 42 70 16 1625 ..... _ 2(42) 84 16 1655 28 28 16 1660 28 42 70 16 1675 2(42) 84 16 1695 2(28) 56 16 1700 2(28) 56 16 6 1715 17 26 43 16 1732 26 26 16 1760 17 26 43 16 1775 17 26 43 16 1790 17 26 43 16 1800 17 26 43 16 1835 17 26 43 16 1845 2(17) 34 16 1860 '17 17 16 Notes:

1. Wt, of FE-6397 (8 inch pipe size) is considered 20 Lbs at node 1537.

2. Wt. of TI-6392 (8 inch pipe size) is considered 20 Lbs at node 1650.

Shaw Stone &Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 36 CALCULATION NO. , REV NO CCN NO MP58B-00138EM 04 N/A 6.0 DESIGN INPUT: (continued) 6.4 Flange Weight Data (continuted)

TABLE 6.4.1 (Flange Weight Data) (continued) p .7150 p Tc~J Ref 150 Lb.

150 p Slip On Lb Slip 150 Lb Pipe Node 125 Lb.

1125 Slip on Lb. Slip on on Lb. 1Total 1Ref.

- I size---- ~etb----- 1 fbbs-----

(L .)

Flmane (Lbs.)

m irTr1 IWt. (Lbs.)

1 . 7 mwtt~-----1 6 1870 17 26 43 16 1885 17 17 16 8 1895 18 28 46 8,16 1915 2(18) 36 8 1935 2(18) 36 8.

1945 2(18) 36 a 1955 2(18) 36 18 1960 2(18) 36 18 1970 18 28 46 8,16 1985 28 42 70 16 2015 18 42 60 8,16 2018 18 18 8 2025 18 18 8 2030 28 42 70 16 2060 28 42 70 16 2090 28 28 16 2095 2(18) , ,I 63(1)_ 8 _

2115 _.... 2(U2,_ 56 16 2120 2(28) 56 16 6 2135 17 26 43 16 2140 17 26 43 16 2155 17 17 16 2165 17 01 16 2185 17 26 43 16 2200 17 26 43 16 2215 17 26 43 16 2235 17 26 43 16 2260 17 26 43 16 2272 2(17) 34 16 2285 17 17 16 2295 17 26 43 16 2310 17 17(2) 16 7004 26 26 16 7010 26 26 16 7024 .... 26 26 16 7028 26 26 16 Notes:

1. Wt. of I" inserted plate of 27 lbs is included for a total wt. of 63 lbs. (See Attachment B of CCN 8 to Rev. 3 of this calculation).

2. Wt. of 17 Lbs. is coded at node 2285. Effect is insignificant and therefore acceptable.

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 37 CALCULATION NO. REV NO CCN NO MP58B-00138EM 04 N/A 6.0 DESIGN INPUT: (continued) 6.4 Flange Weight Data (continued)

TABLE 6.4.1 (Flange Weight Data) (continued)

No= e 12 b lp n 10L li nT,] lneR Pipe Node 125 Lb. Slip on 150 Lb Slip on Total Flange Ref.£ sizz ýn.- --

tHic. .

(in.) FlEmp (Lb 6____ 7100 2(26)______ 52 16 1.5 9310 _______ _12(Q) 9 9330 12(l) 9 9355 12(1) 9 9410 12 ()' 9 9430 12(l) 9

_____ 9455 ________ ________________ 12(l) 9 12.5 9505 _________ _________ 2(7.5) 15 9

______ 9605 _________ ___ ______ 2(7.5) 15 9

,3/4 9003 _______ 0.31_____4)_ 9________

Notes:

I1. Wt. of 300# Socket weld flanges (6 Lbs eacb) from Crane Catalog (Ref. 9) is used.

2. Wt. of FE-6389 (8.inch pipe size) is considered 20 Lbs at node 1983.

3. Wt. of TI-6387 (8 inch pipe size) is considered 20 Lbs at node 2065.

4. Wt, of 3000# Socketweld coupling is considered.

MP5BB-00138EM 6.0 Design Input (Continued) 6.5 Thermal Operating Conditions Table 6.5.1 Thermal Operating Conditions (Mode, NOP & Temp.)

Condition . Mode NOP Temp. Coefft. of Expansion Operating No. No. (1) (IF) (Inch/Ft) Pressure

______________ _______________ (psi)

Thermal Mode 1 -A Ipiping at 33°F (Normal, Upset Faulted)

CarbonSteel Pipe 1 1 33 -0.00259 150 Aust.Steel Pipe 2 33 -0.00382 150 Aust.Steel Pipe 3 33 -0.00382 150 Fire Protection Pipe 4 70 0.0 150 Ambient-SS Pipe 5 70 0.0 150 Ambient-CS Pipe 6 70 0.0 150 CarbonSteel Pipe 7 33 -0.00259 150 Trunnion 8 70 0.0 0.0 Thermal Mode 2 - All piping at 80?F/!I 5?F (Normal, Upset, Faulted) '

CarbonSteel Pipe 2 1 80 0.00077 150 Aust.Steel Pipe 2. 80 0.001__13 150 Aust.Steel Pipe 3 80 0.00113 150 FireProtection Pipe 4 70 0.0 150 Aust.Steel Pipe 5 115 (3) 0.00508 150 CarbonSteel Pipe 6 115 (3) 0.00344 150 CarbonSteel Pipe 7 115 (3) 0.00344 150 Trunnion 8 70 0.0 0.0 NOTES:

1. NOP? Number representing operating parameters of.pipe section as noted in the next page,

2. %T = Thermal Coefficient of expansion (in/fl) based on operating temperature and pipe material Carbon Steel (A53 Gr. B), Aust, Steel (AL-6XN).

3. 115F is considered based on sheets 18 and 19 of Revision 3 of this calculation.

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 39 CALCULATION NO, REV NO CCN NO MP58B-00138EM 04 NIA 6.0 Design Input (Continued) 6.5 Thermal Operating Conditions (continued)

PIPE SECTIONS FOR NOr No's:

2

---OO -I .. From5W25, .. 15, 7 5 2to.

Z... .3o 1.S'rom. 18to.325, From 348 to 355, From 430 to 490, From 512 to 580, From 835 to 1010, From'1202 to 1210, From 1275 to 1284, From 1310 to 1318, From 1362 to 1370, From 1390 to 1525, From 1545 to 1615, From 1560 to 1775, From 1895 to 1970, From 2018 to 2050, From 2005 to 2165, From 7000 to 7008, From 7024 to 8000, From 1730 - 9300 to 1745, From 2153-9400 to 9455, From 1441 to 9525 and From 1942 to 9625.

NOP 2 = From 35 to 85, From 95 to 145, From 50 to 162, From 195 to 222, From 230 to 280, From 205 to 348, From 355 to 370, From 125 to 430, From 490 to 512, From 580 to 775, From 260 to 835, From 1010 to 1202, From 1210 to 1275, From 1284 to 1310, From 1318 to 1345, From 775 to 1362, From 1370 to 1390, From 1525 to 1545, From 1775 to 1785, From 1825 to 1870, From 1240 to 1895, From 1970 to 2018, From 2165 to 2210, From 2250 to 2285 and From 9455 to 2170.

NOP 3 = From 1785 to 1825, From 2210 to 2250.

NOP 4 = From 7008 to 7024, From 7012 to 7050, From 7050 to 7066, From 7032 to 9015, From 7051 to 9115 and From 7063 to 9215.

NOP 5 = From 1870 to 1885.

NOP 6 = From 2295 to 2310.

NOP 7 = From 1615 to 1705, From 1615 to 1870, From 2050 to 2125 and From 2050 to 2295.

NO? 8 = From 7050 to 9765.

NOTE:

1. For Node No's, refer to the work sketch (Section 6.11).

Shaw Stone & Webster Nucdear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 40 CALCULATION NO. REV NO CCNNO MP58B-00138EM 04 NIA 6.0 Design Input (Continued) 6.6 Thermal Anchor Displacements RBCCW Heat Exchan2er X-18A,B,C Movements:

1The.eatm.nxchanger.A. 8A,i,U.mov.ements.at.nodes.5,.325, -37.Y arerecalculated using-the same. SI.-

procedure as shown on page 15 of Revision 3 of this calculation.

The Design Temperature is considered as I I 0*F and the direction of d. movement is changed based on Section 4 of CCN 02 of Revision 3 of this calculation.

B = Thermal Expansion = 1.46" per 100 ftiat 2001F.

T = Temperature Range = (2000 F - 701F) = 130*F dTemp = Design Temperature Range = (1 I00 F - 70'F) = 40°F 231-511 I 5 1-711

--12 \-anchor end dx =0.0" dy (1.46"~/130'F)*(40oF}*(5.583'/100') = 0.025" dz=(1.46"/l 30°F)*(40°F)*((-)26.5208'/100')= (-)0.119" Stiffniess Used at the Heat Exchanger X-18A, B, C (Nodes 5,325,370)

Translational Stiffness = 1.0E07 Lbs/Inch.

Rotational Stiffness = 1 .0E09 In-Lb/Radian.

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 41 CALCULATION NO. REV NO I CCN NO MP58B-00138EM 04 N/A 6.0 Design Input (Continued) 6.7 Response Spectra (Reference 14)

The Response Spectra of Auxiliary Building at Elev. 14'-6", 0.5% Damping (OBE) which is used for X and Z directions and Vertical Accelerations are 2/3 of the ground acceleration (i.e. 2/3 of 0.09gs) or 0.06gs for OBE and 0.11 3gs for DBE. Acceleration used in Revision 3 of this calculation (See Attachment D) is input as Period I I TABLE 6.7-1 (Horizontal Accelerations)

HORIZONTAL ACCELEARTIONS X AND Z DIRECTIONS)

T (Seconds) Ag , T(Seconds) A (g) T (Seconds) A (g) 0.02 0.23 0.038 0.23 .0.054 0.46 0.089 0.497 0.109 0.914 0.111 0.96 0,116 5.507 0.119 7.86 0.147 7.86 0.156 4,883 0,161 3.562 0.172 1.857 0.1I 79 1.445 0.238 0.757 0.250 0.686 0,333 0,64 0.714 0.368 0.833 0.326 1.00 0.28 2.000 0.17 TABLE 6.7-2 (Vertical Accelerations)

VERTICAL ACCELEART IONS (Y D ECTION) ..

T (Seconds) A (g) T(Seconds) A (g) T (Seconds) A (S) 0.010 0.067 0.050 0.167 0.067 0.187 0.100 0.214 0.125 0.226 0.167 0.24 0.333 0,233 0.500 0.2 0.667 0.166 1.000 0.132 1.250 0.08 1.667 0.06 2.000 0,047 2.500 0.05 P _I_:_

Note:

1. T is for Period (Seconds) and g is for Spectral Acceleration (g's).

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENT1FICATION NUMBER PAGE 42 CALCULATION NO. REV NO CCN NO MP68B-00138EM 04 NIA 6.0 Design Input (Continued) 6.8 Seismic Anchor Movements (Reference 14)

The information extracted from Section 3.3 of Revision No. 3 of this calculation is shown below.

EL. 14'6" 0.002' (0.024") 0.4002' (0.024")

EL. 3816i' 0.003' (0.036") 0.004' (0.048")

AUXILIARM tbý X z.

EZ. -25'66 0.0 0.0 EL. -5'10" 0.0014' OBE (0.016811) 0.002i' OBE (0.0252")

0.0019, 1B. (o.0228,;l) 0.0028, DBE (0.0336),

'EL. 14'6" 0.0Q26' o0E (0.0312") 0.0030' OBE (0.036")

0.0035' bBE (0.042") 0.0042' DBE (0.0504")

'EL. 25'6" 0.0031' OBE (0.0372") 0.0066' OBE (0.0432")

0.0042' DBE (0.05041) 0.0050' DBE (0.060")

EL. 38'6i, 0 . 0 0 3 6' OBESE (0.0432.') 0.0041' OBE (0.0492'")

0.0049' DtBE (0.0588"i) 0.0056' DBE (0.0672"1)

THE IAXIMMJ S?.ATrIV, DISPLACEMENT B*iWEEN BUILDINGS IS IN THE Z DIRECTION AT ELEVATION 38'-6" MD IS CALCULATED AS:

DELTA Z (]ELTA S OF WARýEHOUSE) + (DELTA Z OF AUX BUILDING) 0.048"+ 0.067,2w

= 0. 1152" THIS VALUE "IS LESS THAN 0.125" AND IS CONSIDV-M NEGLIGIBLE.

IT IS ALSO CORSERVATIVE AS TEE PIPINO IS ROVTVD PROM THE AUX BUILDING TO TI WAREaoES BELOW TICE 14 '-61' ELEVATION.

THEREFORZ A SAI A-RALYS18 WAS NOT IRFORV0ED.

Shaw Stone &Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 43 CALCULATION NO. REV NO CCN NO MP58B-00138EM 04 N/A 6.0 Design Input (Continued) 6.9 Pipe Support Data Table 6.9-1 (Pipe Support Data)

'1-~

-t t 18rui tT ~ I~uu ----.--e----

Mark No. No. Type Translational Rotational (Lbs/inch) (In-Lbs/Rad)

HI-427074 40 NS 1.0E06 H2.327002 75 VC I.0E06 H3-427113 80 VC,EW 1.0E06 H44-427063 95 NS L.0E06 Anchor 527027 145 ANCHOR I.0E09 I.OEI I H5-327098 155 VC LOE06 H5A-427075 160 EW SNUBBER 1.0E06 H6-427115 215 EW SNUBBER 1,0E06 H7-427114 220 vC I.0E06 Anchor527028 280 ANCHOR 1.0E09 1.0E1 1 427079 290 NS 1.0E06 427076 335 NS 1.0E06 H10-427064 405 EW 1.0E06 H11-327012 410 VC 1.0E06 H12-427080 425 NS 1.0E06 H 13-327013 450 VC 1.0E06 H14-427082 455 EW 1.0E06 H15-427085 475 NS,VC 1.0E06 H 15A-427068 515 NS 1.0E06 H23-380352 520 VC 1.0E06 H24-427026 535 VC 1,0E06 H25-327135 570 NS,EW 1,0E06 427089 580 VC 1.0E06 427073 610 EW 1,0E06 427087 615 VC 1.0E06 427055 635 VC 1,0E06 327138 650 VC, EW 1.0E06 427092 675 VC, EW 1,0E06 427094 685 NS 1.0E06 327147 695 VC,EW ].0E06 327149 720 VC,EW 1.0 E06 79-14-022 805 NS,VC 1.0E06 H 17-427080 825 NS,EW 1.0E06 SK-ALW-102579 860 VC 1).0E06 H20.427083 865 EW 1,01E06 H21-427084 885 NS,VC 1.0E06 427069 920 NS .01E06 H32A-427030 925 VC 1.0E06 H33-427031 .935 VC 1.0E06 H34-427091 955 VC I .OE06

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION I10NTIFICATION NUMBER PAGE 44 CALCULATION NO. REV NO CCN NO MP58B-00138EM 04 N/A 6.0 Design Input (Continued) 6.9 Pipe Support Data (continued)

Table 6.9-1 (Pipe Support Data) (continued)

Support Node Support ,Suport Stiffness (Reference 4)

Mark No. No. Type Translational Rotational (Lbs/inch) (In-Lbs/Rad)

H35-327141 970 NSIEW 1.0E06 H36-427090 1000 EW 1.0E06 427104 1020 VC 1,0F,06 427056 1055 VC 1.0E06 ....

327145 1070 VC,EW 1,0206 427067 1085 NS 1.OE06 427093 1090 VC,EW 1.oE06 327148 1115 VCEW 1.0E06 327150 1135 VC,EW 1.0E06 60469 1200 NS,VC,EW 1.0.06 527019 1215 EW 1.0206 60469A 1270 NS,VC,EW 1.0E06 527019 1285 NS 1.0E06 60469 1305 NSVC,EW L.OE06 527010 1320 NS,EW 1.0206 60469A 1360 NSVC,EW 1.0E06 327157 1395 NS 1.0E06 527014 1415 EW 1.0E06 327160 1435 NSVC 1.0906 527017 1460 VC 1.006 527013 1470 VC 1.0E06 527011 1485 NS 1.0E06 327165 1505 NS,VC 1.0E06 527012 1520 NS,VC 1.0E06 527012 1525 EW 1.0E06 60522 1535 NS,VC 1.OE06 60219 1690 NS 1.0206 Anchor 60216 1705 ANCHOR 1.0E06 I.0E08 60523 1780 NS,EW 1.0E06 60525 1785 4-WAY 1.0206 1.0E08 Rx 60525 1825 4-WAY 1.0E06 1.0E08 Rx Anchor 60526 1860 ANCHOR 1.0E06 1.0E08 Anchor 60524 1885 ANCHOR 1.0E06 I.OE08

Shaw Stone & Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 45 CALCULATION NO. REV NO CCN NO MP58B-00138EM 04 N/A 6.0 Design Input (Continued) 6.9 Pipe Support Data (continued)

Table 6.9-1 (Pipe Support Data) (continued)

Support Node Support Support Stiffness (Reference 4)

Mark No. No. Type Translational Rotational (Lbs/inch) (In-Lbs/Rad) 327125 1900 NS L.006 527009 1920 EW O06 .... _ _

327124 1940 NS,VC 1.0E06 327123 1950 NS'vc 1.0E06 327122 1965 NS,VC L.0E06 60220 1980 NS,VC LOE06 60218 2110 NS I.0E06 60214 2125 ANCHOR I.OE06 _1.0E08 60221 2205 NS,EW 1.0B06 60228 2210 4-WAY I.0F06 I.0E08 Rx 60228 2250 4-WAY 1.0E06 1.0E08 Rx 60229 2285 ANCHOR 1.0506 0OB08 60223 2310 ANCHOR 1.0E06 L,0E08 60542FLR 9755 ANCHORC() I.0E06 1.0E08 60542WALL 9765 ANCHOR ( .. 0E06 1,0E08 60541 7054 VC,EW 1.0106 60540 7066 VC,EW 1.0E06 Notes:

1. Existing Anchor is modeled with two Trunnions, one attached to the Floor and the other attached to the Wall (See Attachment D).

Shaw Stone &Webster Nuclear CALCULATION SHEET CALCULATION IDENTIFICATION NUMBER PAGE 46 CALCULATION NO, REV NO CCN NO MP58B-00138EM 04 N/A 6.0 Design Input (continued) 6.10 Special Stress Intensification Factors (SIPs) (Reference 1)

Special SIFs are considered at the following weld locations.

....... . -.-...- .oiiow.ing...no

.. .lange ldered.at...he. es.o.- lipon ....... ... ..

connections.

The nodes are 5, 25, 35, 70, 77, 85, 95, 105,162, 182, 185,210, 222, 230,242, 250, 280, 295, 308, 325,340, 348, 370, 380, 403, 405,430,445,460,485,490, 512, 525, 550,580, 595, 610, 630, 640, 645, 660, 665, 670, 685, 690, 705, 710, 715, 730, 735, 750, 765, 785, 800, 835, 855, 870, 893, 895, 920, 930, 950, 980, 995, 1015, 1035, 1050, 1060, 1065, 1080, 1085, 1100, 1105,1110, 1125, 1130, 1145, 1150, 1155, 1190, 1195, 1202, 1210, 1220, )265, 1267, 1275, 1284, 1290,1300, 1310, 2318, 1325, 1355, 1357, 1362, 1370, 1380, 1390, 1410, 1430, 1440, 1455, 1465, 1485, 1500, 1510, 1515, 1525, 1540, 1585, 1587, 1655, 1660, 1695, 1700, 1715, 1732, 1740, 1760, 1775, 1785, 1790, 1800, 1835, 1845, 1860, 1870, 1885, 1895, 1915, 1935, 1945, 1955, 1960, 2970, 1985, 2015, 2018, 2030, 2035, 2060, 2090, 2095, 2115, 2120, 2140, 2155, 2165, 2185, 2200, 2210, 2215, 2235, 2250, 2260, 2272, 2285, 2295 and 2310.

Stress Intensification Factor (SIF) of 2.3 is considered at the nodes 9005, 9010, 9105, 9110, 9205, 9210 of Threaded connections.

Stress Intensification Factor (SIF) of 2.1 is considered at the nodes 9315, 9320, 9340, 9345, 9415, 9420, 9440,9445 of Socket Weld connections.

All the Junction nodes are considered as ANSI Tee except at nodes 7000, 7050, 8000 which are considered as Unreinforced Tees and 7032, 7051, 7063, 1730, 1745, 2153, 2170, 1441 and 1942 which are considered as Branch connections.

6.0 Design luput (cent*neud) 6.11 Worksktch NODE, SUPPORT MAR'K NO..

40 427074 NS 75 32700D VC 1o0 427113 VC-E 95 427063 NS 155 327098 VC 160 A-427075 ES S 235 427115 ESS 220 427114 VC 290 427079 NS 335 427076 NS Q CARBON STEEL PIPE 145 S27027 ANCOOR

() STAINLESS STEEL 280 527028 ANCH OR UNS NOi 8367 PIPE 1%'-JGD-4 CtNT'D. ON SHEET 2 RflbC' NEAT EXCHANGSER X-IRA RBCCV PEAT EXCHANGER X-183 SERVICE VATER SUPPLY TO DIESEL ENGINE CIJULERS MILLSTONE UNIT 2 SHEET I

6., Design Input (continued) 6.11 Warksketch CONT'D ON CDNT'D SHEET SHEET 3 NODE, SUPPORT MARK NO, 4D5 427024 EW 410 327012 V.C.

425 427080 NS 4Z0 327013 V.C.

455 427082 EW 475 427085 NS, VC 515 A427068 NS 520 380352.VC 805 79-14-22 NC, VC 825 427080 NS. EC 265 427083 EW 860 SK-ALV-10a579 VC 865 427084 NS. VC 320 427069 NS 925 427030 VC (O CARON STEEL PIPE

( STAINLESS STEEL UNS NO 9367 PIPE CONT'D ON SHEET I WATER TO DIESEL ENGINE COOLERS x MILLSTONE UNIT 2 SHEET 2

6.0 Design Iuput (tontimued) 6.11 Worksketch NODE, SUPPnRT MARK NOI C0N7T'D SHEET 4 535 427026 VC 570 327133 NS. EW 580 427089 VC 610 407073 EW 615 427087 Vt 935 4Q7031 VC 955 427091 VC 970 327141 NS, E/

Loco 4P7090 EW 1020 427104 VC OCARBON STEEL PlIPE 0STAINLESS STECL z

SHEET 2 SERVIC" WATER

6.0 Design Input ýCoutiautd) 6.11 Worksketcb N0UE, SUPPORT HARK NO:

STANILEaS STEEL UNS NO 8367 PIPE 635 427055 VC 650 327138 VC. EW 675 427092 VC. EW 685 4R7094 NS 695 327147 VC. EL 720 3L7149 VC, EW 1055 4127056 VC 3070 327145 VC. EW 1085 427067 NS 1090 427093 VC. EV 1115 327148 VC. EW CONT'D I 135 327130 VC, EV UN SHIET Y

N IC SR-RV3CE WATER SUPPLY -n DIESEL ENGINE COOLERS MILLSTONE UNIT 2 SHEET 4

Serial No.11-476 Relief Request RR-04-12 Docket No. 50-336 ATTACHMENT 3 ETE-CME-2011-1005, Revision 1.

Structural Integrity and System Performance Evaluation of Degraded Flange in "A" Service Water Line to EDG Spool SK-2952 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2

ETE-CME-2011-1005 Report Generated on 8I12D01t 11"29:35 AM Page 1 of 65 EngineeringTechnical Evaluation Cover Sheet

~DominBon CM-A-TE01 ATTACMN 2 PaeIo

1. Stations Doc Type: Sub Type: 2. Document Number 3. Rev# 4. Decomisslonlng?

[] MP [] SU [] NA F1 KW [- CO ETE 000 ETE-CME-2011-1005 1 E Yes E3 No (Note: It both SU end NA, then check CO) 5.Title:

Structural Integrity and System Performance Evaluation of Degraded Flange in "A"Service Water Pipe to EDG S ooi SK-2952

6. ETE Level 7. Unit(s) 8. Quality Classification 9. FSRC Approval Req.?

[] Level 1 2 Level 1l [ UnitI [Z Unrt2 [] Unit3 [] ISFSI [ SR []NS ElNSQO Yes [ No

10. Preparation,Review, andApprovalSignatures (add or delete rows as needed)

Preparer: (Print) Signature: Date:

Digitally signed by: 08119/2011 Steahr, Thomas . 11:09:00 am Reviewer: (Print) Signature: Date:

Digitally signed by: 08/19/2011 Deconto, Raymond /L 11:18:05 am Engineering Supervisor / Designee: (Print) Signature: Date:

Digitally signed by: 08/19/2011 Marino, Michael Z *, 11:19:42 am StandardAttachments Attachment # of pages Reviewed/No Not Req.

Impact

11. Design Effects and Considerations (DNES-AA-GN-1 003) Att#1 1El El

12. Document Impact Summary (DRUL) (DNES-AA-GN-1002) Att#2 1 El

13. Considerations and Conditions for Document Updates (check N/A [0 if no document updates are noted on the DRUL)

El All Document updates noted on the DRUL can be Initiated immediately

• ] Document updates noted on the DRUL are delayed until the following documentstactions are completed:

(e.g., WO, CR etc.) (See DRUL Remarks section) 10CFR50.59Attachments Attachment # of pages Not Req.

14. 10CFR50.59/72.48 applicability review forms (DNAP-3004 or CM- Att#3 [

AA-400)

15. 10CFR50.59/72.48 screen form (DNAP-3004 or CM-AA-400) _ _

16. 10CFR50.59172.48 evaluation form (DNAP-3004 or CM-AA-400)

17. Additional Attachments Attachment #of pages Description AttachmentAMP2_SWLeak'atSpoi 39 AttachmentBMP2_SWLeak at Spo, 18 Aug 19, 2011 11:29 AM

"5TE-CME-2011-1005 Report Generated on 8/1912011 11:29:35 AM Page 2 of 65 Engineering Technical Evaluation Cover Sheet Domninion-CMAA-T-0 ATAHE 2 Pag 2 of 6

18. Distribution Primary Recipient(s): I(Enter the Name / Dept or Location for EACH Primary Recipient inthis block.)

Copy To? Other Recipient / Department or Location Cop To? 1Other RecipientlDepartment or Location

• - :Preparer Reviewer

[ Supervisor fl* Site DCE

[] 'ffected organization 1i Program Owners 1.0 Table of Contents NIA 2.0 Source Document CR438193 - "Possible Through Hole Leak In the "A" Service Water Header To The "A" EDG" 3.0 Record of Revision N/A 4.0 Purpose This ETE evaluates the structural integrity and leakage acceptability of a degraded slip-on flange located on 10" service water supp!y line to "A" Emergency Diesel Generator (10"JGD-4 spool SK-2952) to support demonstration of continued operability of the MP2 A service water supply header.

5.0 Design Inputs and Assumptions N/A 6.0 Methodology N/A Aug 19, 2011 11:29 AM

'ETE-CME.201 1-1005 Report Generated on 8/19/2011 11:29:35 AM Page 3 of 65 Engineering Technical Evaluation Cover Sheet

~Domimiour S C I C p..

• 7.0 Discussion Reference 1 CR and Reference 2 UT examination document a degraded slip-on flange exibiting through wall leakage with a current leak.rate of 10 drops per minute. The subject flange is located on the Millstone Unit 2 "A" service water supply train to the *A" emergency diesel generator. This line is designated as 10"JGD-4. The subject flange is the downstream end of spool piece SK-2952 as shown on Reference 3 isometric drawing.

This class 125 light weight flange is lined carbon steel. The degradation Is suspected to be the result of a failed lining which can occur Ifthe coating is compromised during spool installation.

Structural Integrity Assessment:

Currently there is no NRC approved methodology for ASME Code temporary acceptance of flaws in moderate energy Class 3 flanges. ASME Code Case N-513-2 (Reference 4) provides NRC approved flaw acceptance methodology for Class 2 or 3 piping but specifically excludes application to a flange joint.

Since no ASME Code or NRC approved methodology is available to evaluate flanges, a non Code methodology is developed here. The objective is to assess the applied piping design loads at the flange (as documented in the stress calculation of record Reference 5) compared to a conservative assessment of the extent of remaining flange material (based on bounding the degradation documented In UT examination report Reference 2). In addition, the piping support local to the flange will be assessed for possible reduction in load carrying capability.

The current piping stress analysis run of record is documented In Addendum B of Reference 5. In the piping analysis computer model the subject flange Is located at node point 580 (shown in model worksketch sheet 3). The ASME Code equation pipe stresses for eq 8, eq 9 normal/upset, eq 9 faulted, eq 10 and eq 11 were extracted (stress calculation Attachment B pages 10 and 53) and are shown in Table 1. Also included in Table 1 are the corresponding allowable stresses and percent ratio of allowable. As shown in the table the maximum stress at the flange location is 10.0 percent of ASME Code allowable in the undegraded condition. This low stress condition (1/10 of allowable) provides considerable margin for material degradation while maintaining structural integrity. The reduced load carrying capability of the flange is proportional to the reduction in area. This results in an increase of 50 percent to the calculated stresses. This increase in stress will increase the percent ratio of applied to allowable stress from 10 percent to 15 percent leaving 85 percent margin.

Table 1 Node 580 Stress (psi) Allowable (psi) Percent Ratio of Allowable Eq 8 1502 15000 10.0 Eq 9N/U 1709 18000 9,49 Eq 9F 1893 35000 5.41 Eq 10 1138 22500 5.06 Eq 11 2640 37500 7.04 The UT examination report is included in Attachment B. Also included in Attachment B are photographs of the flange Aug 19, 2011 11:29 AM

ETE-CME-2011-1005 Report Generated on 8/19/2011 1129:35 AM Page 4 of 65 Engineering Technical Evaluation Cover Sheet

- D ominion-CMAA-T, 0 ATAHMN 2 ..

Pae4o showing the through wall leak, located between two bolt holes at the crotch region. The sketch on page B2 identifies the location of the leak relative to the flange orientation. The bolts/holes have been numbered sequentially 1 through 12 for the purpose of discussion. As shown in the UT exam report a number of measurements were taken on the flange between each of the twelve bolt holes. Radial and axial thickness measurements were taken on the flange edge, flange face, crotch region and of the pipe at the point of insertion into the flange. Review of this data indicates the degradation Is localized to a single location between two adjacent bolt holes (holes 11 and 12). The adjacent areas and all other areas of the flange do not exhibit any degradation. This would indicate the current degradation is bounded by an area approximately 116 of the total circumference. To allow for potential additional flaw growth it can be assumed that 113 of the circumference of the flange has been lost to wastage and only 2/3 of the circumference of the flange remains.

Based on the extremely low loads (10 percent of allowable) a 33 percent loss of the flange load bearing area / structural load path will not challenge the structuWal integrity of the flange as the remaining 66 percent flange area is more than sufficient to support the low applied loading.

Pipe support mark number 427089 (shown on pipe support isometric drawing Reference 6) is attached to the mating flange.

Details of this rigid tandem pipe support are shown on the support detail drawings References 7, 8 and 9. Each leg (attachment point) of this support is rated for a 25001b load per Reference 7. This pipe support utilizes the bolts located in holes 11, 12, 1, 2 on the east side of the support and holes 5 through 8 for the west side of the support. A review of the support load calculation (Attachment E, page 1 of the pipe stress calculation Reference 5, node 580) indicated the maximum load for this support is 17931bs. This load is shared equally between both struts. Therefore each strut is subject to approximately 8971bs (17931bs12). Strut attachment to the flange is accomplished by4 bolts, through the holes described above. The 25001b capacity of each strut is shared evenly over the 4 attachment bolts. In order to support the required 8971b applied load at least two of the four bolts are required, resulting a reduction of the strut capacity by half to 12501bs. Therefore a minimum of 2 bolts are required at each strut attachment plate. Currently the degraded area is located between bolt numbers 1 and 12 (see sketch Attachment B page B2). Because the flange is degraded in this area It is conservatively assumed bolts 11 and 12 are insufficiently supported to be capable of carrying any load. Bolts 1 and 2 are still capable of carrying load. Since 2 bolts provide adaquate capability for carrying the required load, this support remains fully capably of performing its design function.

For the purpose of pipe support qualification, additional flange degradation counter-clockwise In the direction of hole 10 will have no impact on support qualification. Additional flange degradation in the clockwise direction toward hole 1 is only acceptable provided full flange thickness immediately surrounding hole 1 can continue to be demonstrated (under the nut).

Loss of Service Water Flow Assessment:

Service water flow loss from this leak location will not adversely affect the capability 6f the SW system to provide adequate cooling to the EDG heat exchangers and to all other essential safety related heat exchangers. A leakage limit of 5 gpm is applied as the maximum acceptable leakage rate (currently the leakage rate is approximately 10 drops / min). A detailed system hydraulic analysis has been performed (Attachment A). This analysis demonstrates that a margin of at least 10 to this leak rate is available (i.e., > 50 gpm can be tolerated and all essential safety related heat exchangers receive adequate service water flow for the limiting accident condition.)

Aug 19, 2011 11:29 AM

ETE-CME-2011-1005 Report Generated on 8J19/2011 11:29:35 AM Page 5of 65 Engineering Technical Evaluation Cover Sheet 07D)omninion-CMA-T-0 2 ae5o .TAHýN 8.0 Conclusions Based on the above discussion the subject degraded flange maintains structural integrity and remains capable of supporting all required design loads. Since the flange is degraded and exhibiting through wall leakage, it is non compliant with ASME Code requirements. A conservatively large degradation (1/3 of the circumference of the flange) is considered to allow for potential additional flange degradation.

The associated pipe support (mark number 427089) also remains capable of supporting the required design load. Additional flange degradation is acceptable providing continued demonstration of full flange thickness can be shown under at least 2 of the four nuts supporting each strut attachment plate.

9.0 Precautions or Limitations This evaluation places limiltations on the maximum acceptable flange degradation and maximum allowable leak rate. Flange degradation must not exceed 1/3 (120 degrees) of flange circumference and full flange thickness must be maintained under at least 2 of the four nuts supporting each strut attachment plate. Maximum leakage must not exceed 5 gpm. If desired, it is acceptable to impose a more restrictive limitation on maximum leakage to address additional concerns not considered here (such as flooding).

10.0 Required Actions Consistent with the guidance for piping flaw evaluation provided in Reference 4, periodic inspection of approximate 30 day intervals shall be preformed to assure the degraded area remains bounded and the limitations listed in section 9 remain satisfied.

11.0 Recommendations N/A Aug 19, 2011 11:29 AM

• ETE-CME-201 1-1005 Report Generated on 8/1912011 11:29:35 AM Page 6 of 65 Engineering Technical Evaluation Cover Sheet A I I & ... . S 12.0 References

1. CR438193 - "Possible Through Hole Leak In the "A" Service Water Header To The "A" EDG."

2. AWO 53102457364 UT Examination Report - See Attachment B.

3. Drawing 25203-20150 SH. 471, Rev 7 "Millstone Nuclear Power Station.- Unit 2 "A" Train Service Water Supply to Diesel Engine Coolers".

4. ASME Code Case N-513-2 "Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section Xl, Division 1.

5. Calculation MP58B-00138EM Revision 4, Addendum B "Service Water Supply to Diesel Engine Coolers - Stress Problem 118".

6. Drawing 25203-20224 SH. 61, Rev 3 "Millstone Nuclear Power Station - Unit 2 "A" Train Service Water Supply to Diesel Engine Coolers".

7. Drawing 25203-22200 SH 427089 Rev 4 "Service Water Supply to Diesel Engine Coolers Mark No 427089".

8. Drawing 25203-22200 SH 427089A Rev 5 "Service Water Supply to Diesel Engine Coolers Mark No 427089".

9. Drawing 25203-22200 SH 427089B Rev 4 "Service Water Supply to Diesel Engine Coolers Mark No 427089".

13.0 Attachments Attachment A - MP2 SW Leak at Spool SK-2952 Flow Evaluation Attachment B - UT Examination Report and Flange Photographs Aug 19, 2011 11:29 AM

Attachment #1 ETE-CME-2011.1005 Report Generated on 8/19/201111:29:35 AM Page 7 of 65 P-iDoIni~on Design Effects Table

,DIN.E Page Irfl Instructions:

This table will Identify Impacted programs, Ifa question Is answered yes, the responsible engineer shall address and document In the discussion section of the Design Change. The responsible engineer shall check "No Impact" or "Impact" as appropriate. If necessary, consult the program owner to assist with the determination. Ifit is determined that there is an impact, identify program owner, check "Impacr In the applicable section, obtain the consulted Individual(s) signature on the engineering product cover sheet and document the discussion in the change package. Ifan Impact Is determined for any program, then relevant portions of this attachment should be attached to the appropriate document. Ifit is determined that there Is "No Impact" in a section where a question Is answered "Yes', document the basis for this determination inthe change package. When all questions are answered "No' in a particular section, do not check "Impact" or "No Impact."

Station: Unit: ETE Document Number:

0 KPS 2 MPS O CO E3I 02 ETE-CME-2011-1005 r- NAPS [] SPS 033 O ISFSI Change Document

Title:

Structural Integrity and System Performance Evaluation of Degraded Flange in "A"Service Water Pipe to EDG Spool SK-2952 1.1 Fire Protection Equipment or Features 0 Yes O No 1.2 Combustible Loading 0 Yes 0 No 1.3 Hazards and Ignition Sources 13 Yes 0 No 1.4 Fire Safe-Shutdown Analysis " Yes 0 No 2.0 Environmental Qualification (EQ) [] Yes 0 No 3.0 ASME Codes / ISI I IST 03Yes 20 No 3.1 Inservice Inspection 0 Yes 0 No 3.2 Inservice Testing CI Yes 0 No 4.0 Regulatory Guide 1,97 - Post Accident Monitoring 0] Yes 0 No 5.0 Maintenance Rule D3 Yes RI No 6.0 Radiological Protection Program (ALARA) El Yes 0 NO 7.0 Environmental Impact (Non-Radiological) 03 Yes O No 8:0 NijldI&Ma*eitll-Cbn'Tfi D Yes ONo 9.0 License Renewal Rule Program and Aging 0 Yes 0 No Managlement Activities ....  :

10.0 Generic Letter (GL) 89-13 Program 0 Yes 0 No 11,0 Station Blackout (SBO) 03Yes [ No 12.0 Appendix J Program .0 Yes 0 No 13.0 NERC - North American Electric Reliability 03Yes 0] No Council 14.0 GSI-191 (Containment Recircutation Sump) 03Yes 0 No Considerations

Attachment #2 'rETE-CME-2011-1005 Report Generated on 8119/2011 11:29:35 AM Page 8 of 65 Documents Required To Be Updated List (DRUL) 2xD0Mi1"w DNSAI N10 ATAHET Page .f STATION UNIT ETE Document Number DKPS 0 MPS r NAPS DSPS 0CO 01 0 2 133 ISFSI IETE-CME-2011-1005 Operations Critical Documents Needed N/A Department / Contact Impacted Document Number and/or Title Closeout Documents Needed NIA Department / Contact Impacted Document Number and/or Title Remarks (Attach additional pages If needed):

Attachment #3 I ETE-CME-2011-1005 Report Generated on 8/19/2011 1129:35 AM Page 9 of 65 ETE-CME-2011-1005 Attachment A: MP2 SW Leak at Spool SK-2952 Flow Evaluation Preparer: DeborahL Godinez Independent Reviewer: James J Craffey

References:

A. CR438193 B. Calculation 92-120 Rev 4 Addendum B, "MP2 SWS Design Basis Alignment- Summer and Winter" dated 3/29/11.

C. Calculation 03-ENG-04035M2 "MP2 Service Water Design Basis Summary Calculation" Rev 0 CCN 03 dated 5/24/10 Reference A identified a leak in spool SK-2952 (10-JGD-4). As requested, a 10 gpm leak and the maximum allowable break as been evaluated using the PROTO-FLO MP2 Service Water flow model documented in Reference B.

To verify that the correct model was used, a benchmark case was run. Since Ref B did not run case 2b3 it has been run for the limiting EDG case.

Case 2a2 Case 2b3 From Ref B Attach A. Benchmark Benchmark 8/18/1108:41 (Ref B 3/2.8/11 09:08 8/18/11 08:39 did not rerun this case)

SW Pump Flow(gpm) 9948.08 9948.08 10946.12 RBCCW Hx Flow (gpm) 8430.25 8430.25 9519.89 DGA Flow(gpm) 774.28 774.28 1721.59 The spool where the break Is located Is modeled In pipe 83. To model the break It can be located at either node encompassing this pipe; either ARBCCW or ADG. Node ARBCCW is located at 3.5 ft elevation and node ADG is located at 11.5 ft elevation. The break elevation is approximately 9 ft. Cases were run for a 10 gpm break in both locations. To model the break, the nodal flow in the boundary conditions menu is changed to flow out of the system and a value in gallons per minute is added. For the cases listed in Tables I and 2, 10 gpm was used. To determined the maximum flow, this break size was increased until unacceptable results were obtained.

There is less than two-tenths difference between modeling the break at ARBCCW vs ADG. ARCCW is the limiting case for RBCCW and ADG is limiting for the EDG. For the limiting RBCCW case (2a2), the majority of the 10 gpm leak is compensated by increased SW pump flowrate (-6 gpm) to facility 1.

RBCCW flow is reduced approximately 3.5 gpm and EDG flow drops approximately 0.3 gpm. For the limiting EDG case (2b3), the leak results in approximately 0.4 gpm reduction in flow. The normal Page 1 of 3

Attachment #3 A eETE-CME-2011-1005 Report Generated on 81191201111:29:35 AM Page 10 of 65 ETE-CM E-2011-1005 Attachment A operation cases were run to verify acceptable results, As shown below in the table, all flows exceed theirminimum flow requirements. These runs conservatively assume the EDG bypass is open.

The limiting case for RBCCW (Case 2a2 with the leak at node ARBCCW) and the EDG (Case 2b3 with leak at node ADG) were run to determine the maximum break size that still provides the minimum flow requirements. This maximum break size was determined to be 54 gpm.

! t 4 T A*

• t T* *

• A .I

• tq W. d t=*

• A q 4 Table 1: LUOA wlo LNP Summer Uperation - Facility I with 10 m break Component Predicted Flow gpm Required Required Minimum RB TCV Position Max RB TCV Position flow flow rates corrected for

._ (Ref 1) uncertainties Case 2a2 Case 2b3 P5B to XI8B P5B to X18A ARCCW ADG ARCCW ADO X18A 8426.70 8426.76 9516.19 9516.25 7570 8411 EDG A Hx 773.95 773.80 721.30 721.15 507 563 X-181A 120.24 120.25 112.78 112.78 40.4 44.9 X-181B 69.02 69.02 64.74 64.74 20.2 22.4 X-182 46.58 46.58 43.69 43.70 22.9 25.4 X-169A 58.50 58.50 54.88 54.88 26.9 29.9 Total flow 9953.96 9953.87 10951.94 10951.85 - -

Table 2: Normal Summer Operation w/o LNP - Facility I with 10 gpm break Component Predicted Flow (gpm) Required Required flow Miii RB TCV Position Max RB TCV Position flow rates corrected for Case 4al FI P5B-X18B -Case 4b F1 P5A-X1 SA (Ref 1) uncertainties AIcCW ,.ADO ARCCW ADG XI8A 6806.18 6806.55 4421 4912 XI8B 6138.98 613931 4421 4912 XI7A 5677.44 5677.43 5328.99 5328.97 4706 5229 EDO A Bypass 1465.86 1464.86 1411.20 1410.20 - -

X-181A 84.53 84.54 81.71 81.71 40.4 44.9 X-181B 48.52 48.53 46.91 46.91 20.2 22.4 X-182 32.77 32.77 31.67 31.67 22.9 25.4 X-169A 34.98 34.98 33.83 33.83 -

Pu-npPSA 14106.64 14106.29 Pump P5B 13703.90 13703.53 Table 3: LOCA w/o LNP Summer Operation - Facility 1 with 54 gpm break Component Predicted Flow gpm Required Required Case 2a2 P5B to XI 8A Case 2b3 P5B to XI8B flow rates flow ARCCW ADG (Ref 1) corrected for uncertainties X18A 8411.10 9500.22 7570 8411 EDO A Hx 772.51 719.22 507 563 X-181A 120.04 112.61 40.4 44.9 Page 2 of 3

Attachment # ETE-CME-201 1-1005 Report Generated on 8/1912011 11:29:35 AM Page 11 of 65 ETE-CME-2011-1005 Attachment A X-181B 64.64 20.2 22.4 X-182 46.50 968.90 43.63 22.9 -25.4 X-169A 58.40 54.79 26.9 29.9 ETE-CME-2011-1005 Attachment A Total flow 9979.82 10977.02 Conclusion A 10-gpm leak In Spool SK-2952 has no adverse Impact upon the service water header's safety related support design functions. It has been shown that the safety related equipment will continue to meet its minimum flow requirements with a 54-gpm leak at ihis spool location.

Page 3 of 3

Attachment #3 ETE-CME-2011-1005 Report Generated on 811912011 11:29:35 AM Page 12 of 65 08/18/201108:39 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-1011 Page I of 2

.vfILLSTONEM4\DATA3*NE MSS\PROTOFLO CALCS\92-120 REV 4 ADD B\92-120 REV 4-B.PDB - Version 9,92-120 Rev Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convermence: Pressure--OoE-+0 Sum Q-I.OE-2 Friction=1.0B-6 FCV=I.OE-4 PCV=I.0E-3 Temperatur:=5.OF Balancing Parameters Used Benchmark Case 2a2 Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (gpm) (ft) Ratio Pump 5B 23.125 9,948.08 / 37.24 2.34 Facility ] HEADER 23.125 9,547.00 HV-6439 16.410 294.47 TB Discharge 23.125 294.63 HV-6399 23.250 8,430.25 X-18A 23.125 8,430.25 TV-6308 23.250 8,482.87 RB A DischarRe 23.125 8,482.87 /

DGA Flow 5.940 774.28 "

FV-6389 bypass 1.610 1.97 DG Discharge 12.210 778.75 L-IB Strainer Blowdown 3,068 383.08 Feed to Hypochloride System 5.940 18.00 X-169A 2.469 58.52 PCV-8943 1.380 26.84 From Chillers 3.068 58.56 PV-6925 3.068 189.34 X-181 3.068 189.34 X-181A 2.067 120.29 X-181B 2.067 69.05 I1Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum SS NPSH Available Below NPSH Required

Attchment #3 ETE-CME-2011-1005 Report Generated on 8/1942011 11:29:35 AM Page 13 of 65 08/18/2011 08:39 PROTO-FLO 4.60 byProto-Power Corporation - Serial #PFL-1011 Page 2 of 2

.WILLSTONE\4\DATA3\NE MSS\PROTOFLO CALCS\92-120 REV 4 ADD B\92-120 REV 4-B.PDB - Version 9,92-120 Rev Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convergence: Pressurc=O.OEf0 Sum O-l.0E-2 Frictiorr-l.0E-6 FCV=I.OE-4 PCV=l .OE-3 Temperature-.5.0 Balancinp Paramcters Used Benchmark Case 2a2 Flow Summary Title Diameter Flow M'mimnum Flow NPSHA NPSH (in) (gpm) (gpm) (ft) Ratio From SWOR Room 4.026 236.06 PV-6927 2.469

• 46.60 X-182 2.067 46.60 Feed to Pump Seal Cooling 1.939 48.00 I1 Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum SS NPSH Available Below NPSH Required

Attachment #3 ETE-CME-2011-1005 Report Generated on 8/19/201,1 11:29:35 AM Page 14 of 65 08/18/2011 08:41 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-10l1 Page I of 2

\MILLSTONE\4TDATA3\NE MSS\PROTOFLO CALCS\92-120 REV 4 ADD B\92-120 REV 4-B.PDB - Version 9,92-120 Rev Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convergence: Pressure=O.OB+O Sum 0=1.0E-2 Friction-1 .0F&6 FCV- I.OE-4 PCV= .0E-3 Temaeratur=5.OE Balancing Parameters Used Benchmark Case 2b3 Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (gpm) (ft) Ratio Pump 5B 23.125 10,946.12 9 / 37.24 2.08 Facility I HEADER 23.125 10,565.67 HV-6439 16.410 276.19 TB Discharge 23.125 276.35 HV-6399 23.250 9,519.89 I

X-18B 23.125 9,519.89 TV-6307 23.250 8,107.46 TV-6307A 6.065 1,412.43 RB A Dischargo 23.125 9,519.89 DGAFIow 5.940 721.59 J FV-6389 bypass 1.610 1.84 DG Discharge 12.210 726.02 L-1B Strainer Blowdown 3.068 362.46 Feed to Hypochloride System 5.940 18.00 X-169A 2.469 54.89 PCV-8943 1.380 25.18 From Chillers 3.068 54.94 PV-6925 3.068 177.58 X-181 3.068 177.58 X-181A 2.067 112.82 I! Rteverse Flow Through Check Valve && Pump Flow is Past End of Curve

• Flow BelowMinimum $S NPSH Available Below NPSH Required

Attachment #3 t tETE-CME-2011-1005 Report Generated on 8/1912011 11:29:35 AM Page 15 of 65 08/18/2011 08:41 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-1011 Page2 of 2

.MLSTONE\4\DATA3'NE MSS\PROTOFLO CALCS\92-120 REV 4 ADD B3\92-120 REV 4-B.PDB - Version 9,92-120 Rev Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convergenco: Prssurt-O.OE+O Sum O-.01E-2 Friction .L.OE-6 FCVYI.O0E4 PCV-I.OE-3 Temoerature-5.0E-3 -Balancing Parameters Used Benchmark Case 2b3 Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (gpm) (ft) Ratio X-18IB 2.067 64.76 From SWGR Room 4.026 221.41 PV-6927 2.469 43.71 X-182 2.067 43.71 Feed to Pump Seal Cooling 1.939 48.00

!! Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• Flow Below Minimum SS NPSH Available Below NPSH Required

Attachment #3 'ETE-CME-2011-1005 Report Generated on 8/19/2011 11:29:35 AM Page 16 of 65 08/18/2011 09:26 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-1011 Page I of 2 LSTONE\4\DATA3\MNE MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9.92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convergence: Pressarfe0.0E+0 Sum 0=1.0E-2 Friction=l.OE-6 FCV=I.OE-4 PCV=I.OE-3 Tcmperaturc=5.0E Balancinp Parameters Used, Case 2a2 Leak at ARBCCW Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (0pm) (gpm) 00) Ratio Pump 5B 23.125 9,953196 3724 2.34 Facility 1 HEADER 23.125 9,553.01 HV-6439 16.410. 294.35 0 0ý6 23.125 294.51 TB Discharge HV-6399 23.250 8,426.70 X-18A 23.125 8,426.70 ,

TV-6308 23.250 8,479.32 r *L,,*

RB A Discharge 23.125 8,479.32 DGA Flow 5.940 773.95 FV-6389 bypass 1.610 1.97 DO Discharge 12.210 778.42 L-1B Strainer Blowdown 3.068 382.95 Feed to Hypocbloride System 5.940 18.00 X-169A 2.469 58.50 PCV-8943 1.380 26.83 From Chillers 3.068 58.54 PV-6925 3,068 189.27 X-181 3,068 189.27 X-1 81A 2.067 120.24 X-181B 2.067 69.02

!! Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum SS NPSH Available Below NPSH Required

Attachment #3 ETE-CME-2011-1005 Report Generated on 811912011 11:29:35 AM Page 17 of 65 08/18/2011 09:26 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-101 1 Page2 of 2 LSTONE\4\DATA3\NE MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leakYPDB - Version 9, 92-12 Millstone Power Station Unit 2 - Service Water System Flow Sumnmry Report Convergence: Pressure=O.0E+0 Sum Q=l.OE-2 FrNction,..0E-6 FCV=I.OE-4 PCV-I.OE-3 T¢czranurcý5.0E-3 -Balancing Parameters Used Case 2a2 Leak at ARBCCW Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (Opm)(ft) Ratio From SWGR Room 4.026 235.97 PV-6927 2.469 46.58 X-182 2.067 46.58 Feed to Pump Seal Cooling 1.939 48.00 1! Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum $S NPSH Available Below NPSH Required

Attachment #3 ETE-CME-2011-1005 Report Generated on 8/19/2011 11:29:35 AM Page 18 of 65 L.

08118/2011 09:26 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-101 1 Page I of I DNC - SA\MILLSTONE\4\DATA3\NEMSS',PROTOFLO CALCS-92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9,92-120 Rev 4 Add B Millstone Power Station Unit 2 - Service Water System Differences Report Case 2a2 Leak at ARBCCW S:.IWLLSTONAE4VDATA3WE MSSIPROTOFLO CALCSM92-120 Rev 4 Add B192-120 REV 4-B.DBD Created: 08/1812011 8:25:36AM Default Mode - 3 *****Current Mode - 3 Type Name Parameter Current Default System Data Pipe: 128.10 BALANCED Flow = 18.00 Pipe: 239.00 RO-6670 BALANCED Flow=48.00 Node Data ARBCCW Flow (gpm) -10 0

Attachment~~~~~~~~~~~~~~~ -0110 eotGnrtdo 1921 12:5A

.T-M

..... ae1 f6 Attchment # ETE-CME-201 1 -1005 Report Generated on 8119/2011 11:29:35 AM Page 19 of 65 08/18/2011 09:28 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-101 1 Page I of 2 LSTONE\4\DATA3\NE MSS\PROTOFLO CALCS\92-120 Rev 4 Add B392-120 REV 4-B SK-2952 leak.PDB - Version 9,92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Conver*ence: Pressure'O.0E+0 Swm O,*I.OE-2 Friction= L.OE-6 FCV=I.OE-4 PCV=f.OE-3 TcmPrature-5.OE Balancin, Parameters Used Case 2a2 Leak at ADG Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (gpm) (R) Ratio Pump 5B 23.125 9,953.87 37.24 2.34 Facility 1 HEADER 23.125 9,552.92 HV-6439 16.410 294.35 TB Discharge 23.125 294.51 HV-6399 23.250 8,426.76 X-18A 23.125 8,426.76 TV-6308 23.250 8,479.38 RB A Discharge 23.125 8A479.38 DGA Flow 5.940 773.80 FV-6389 bypass 1.610 1.97 DG Discharge 12,21b 778.27 L-1B Strainer Blowdown 3,068 382.95 Feed to Hypochioride System 5.940 18.00 X-169A 2.469 58.50 PCV-8943 1.380 26.83 From Chillers 3.068 58.54 PV-6925 3.068 189,27 X-181 3.068 189.27 X-181A 2.067 120.25 X-181B 2.067 69.02 1! Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum S$ NPSH Available Below NPSH Required

Attachment #3 'ETE-CME-2011-1005 Report Generated on 8119/2011 11:29:35 AM Page 20 of 65 08/18/2011 09:28 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-1011 Page 2 of 2 LSTONM\4\DATA3\NE MSSNPROTOFLO CALCS\92-120 Rev'4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9, 92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convergence: PretssureO.OE+0 Sum O-.OE-2 Friction-l.OB-6 FCVI.0E-4 PCV-l.0E-3 Tc;e=rature=5.0E Balancing Parameters Used Case 2a2 Leak at ADO Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (gpmi) (gpm3) (ft) Ratio From SWOR Room 4.026 235.97 PV-6927 2.469 46.58 X-182 2.067 46.58 Feed to Pump Seal Cooling 1.939 48.00 H!Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum SS NPSH Available Below NPSH Required

Attachment #3 aETE-CME-2011-1005 Report Generated on 8/19/2011 11:29:35 AM Page 21 of 6.5 I 08t18/2011 09:28 PROTO-FLO 4.60 by Proto-Power Coiporation - Serial #PFL-101 1 Page I of I DNC - S:\MILLSTONE\4\DATA3\NEMSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leakYPDB - Version 9,92-120 Rev 4 Add B Millstone Power Station Unit 2 - Service Water System Differences Report Case 2a2 Leak at ADG S.IMILLSTONE1I4DATA3WEMSSLPROTOFLO CALCS192-120 Rev 4 Add B192-120 REV 4-B.DBD CrealeA-08/1812011 8:25:36 AM Default Mode - 3 ***** CurrentMode - 3 Name Parameter Current Default Pipe: 128.10 BALANCED Flow= 18.00 System Data

• r4***

Pipe: 239.00 RO-6670 BALANCED Flow = 48.00 ADG Flow (gpm) -10 0 Node Data

.300669657332101 .300647488186602 Valve Data 2-CL,-080 Position (%Open)

Attachment #3 "ETE-CME-2011-1005 Report Generated on 8119/2011 11:29:35 AM Page 22 of 65 08/18/2011 09:12 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-1011 Page I of 2 LSTONEB4\DATA3\NE MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9,92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convemence: Pressure=O.OE+O Sum 0=l.01-2 Friction=.0E-6 FCVI.OE-4 PCV-1.OE-3 Tempemier=5.0E Balancirm Parametcrs Used Case 2b3 leak at ARBCCW Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (gpm) (ft) Ratio Pump 5B 23.125 10,951.94 37.24 2.08 Facility I HEADER 23.125 10,571.59 HV-6439 16.410 276.09 TB Discharge 23.125 276.25 HV-6399 23.250 9,516.19 X-18B 23.125 9.516.19 TV-6307 23.250 8,104.31 TV-6307A 6.065 1,411.88 RB A Discharge 23.125 9.516.19 DGA Flow 5.940 721.30 FV-6389 bypass 1.610 1.84 DG Discharge 12.210 725.74 L-1B Strainer Blowdown 3.068 362.35 Feed to Hypochloride System 5.940 18.00 X-169A 2.469 54.88 PCV-8943 1.380 25.17 From Chillers 3.068 54.92 PV-6925 3.068 177.52 X-181 3.068 177.52 X-181A 2.067 112.78 II Reverse Flow Tluougb Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum SS NPSH Available Below NPSH Required

Attachment #3 ETE-CME-2011-1005 Report Generated on 8/1912011 11:29:35 AM Page 23 of 65 08/18/2011 09:12 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-101 1 Page 2 of 2 LSTONE\4\DATA3W1E MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 Icak.PDB - Version 9,92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Conver.encrc PremreO.0E+O Sum O=I,.OE-2 Fdction-l.E-6 FCV I.OF-4 PCV-1.0E-3 Temperature=5.0B Balancing Parameters Used Case 2b3 leak at ARBCCW Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (gpm) (ft) Ratio X-181B 2.067 64.74 From SWOR Room 4.026 221.33 PV-6927 2.469 43.69 X-182 2.067 43.69 Feed to Pump Seal Cooling 1.939 48.00 II Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum SS NPSH Available Below NPSH-Required

Attachment #3 *EcTE-CME-2011-t005 Report Generated on 811912011 11:29:35 AM Page 24 of 65 08/18/2011 09:12 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-101 I Page I of I DNC - S:\MILLSTONEI\DATA3\NE_MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9,92-120 Rev 4 Add B Millstone Power Station Unit 2 - Service Water System Differences Report Case 2b3 leak at ARBCCW S:IMILLSTONEW4IDATA3 NE_MSSMPROTOFLO CALCSi92-120 Rev 4 Add B192-120 REV 4-B.DBD Created: 081)8/2011 8:25:36AM DefaultMode - 8 ***** CurrentMode - 8 Typ Name Parameter Current Default System Data Pipe: 128.10 BALANCED Flow = 18.00 Pipe: 239.00 RO-6670 BALANCED Flow = 48.00 Node Data ARBCCW Flow (gpm) -10 0 Valve Data 2-CL-080 Position (%Open) .322688007298614 .32256299628028

Attachment #3 A eETE-CME-201 1-1005 Report Generated on 8119/2011 11:29:35 AM Page 25 of 65 08/18/2011 09:09 PROTO-FLO 4.60 by Proto-Power Corporation.- Serial #PFL-1011 Page I of 2 LSTON\4\DATA3\NE MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leakPDB - Version 9, 92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convergence: Pressure=0.0E+0 Sum O=l.OE-2Friction= l.OE-6 FCV=L.OE-4 PCV=I,0E-3 Teneeraturc=5,0E-3 -Balancing Pararmetcrs Used Case 2b3 Flow Summary Title Diameter Flow Minimum Flow NPSHA NPS1H (in) (gpm) (gpm) (ft) Ratio Pump 5B 23.125 10,951.85 37.24 2.08 Facility I HEADER 23.125 10,571.50 HV-6439 16.410 276.09 TB Discharge 23.125 276.25 HV-6399 23.250 9,516.25 X-I 8B 23.125 9.516.25 TV-6307 23.250 8,104.36 TV-6307A. 6.065 1,411.89 RB A Discharge 23.125 9,516.25 DGA Flow 5.940 721.15 FV-6389 bypass 1.610 1.84 DG Discharge 12.210 725.59 L,-IB Strainer Blowdown 3.068 362.35 Feed to Hypochoride System 5.940 18.00 X-169A 2.469 54.88 PCV-8943 1.380 25.17 From Chillers 3.068 54.92 PV-6925 3.068 177.52 X-181 3.068 177.52 X-181A 2.067 112.78 II Reverse Flow Through Check Valve && Pump Flow is Past End of Curve,

• • Flow Below Minimum $$ NPSH Available Below NPSH Required

Attachment #3 AETE-CME-2011-1005 m Report Generated on 8/1912011 1129:35 AM Page 26 of 65 08/181201i 09:09 PROTO-FLO 4.60 by Proto-Power Corlporation - Serial #PFL-10 11 Page 2 of 2 LSTONE\4\DATA3'NE MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9, 92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convergenec= Pressure=0.0E+0 Sum 0=1.0_-2 Friction-1.OE-6 FCV=I.OE-4 ?CVWI.OE-3 Tanieature=-5.OE BalaaoinP Parameters Used Case 2b3 Flow Summnary Title Dinmeter Flow Minimum Flow NPSHA NPSH (Epm) (8pm) (ft) Ratio X-181B 2.067 64.74 From SWOR Room 4.026 221.34 PV-6927 2.469 43.70 X-182 2.067 43.70 Feed to Pump Seal Cooling 1.939 48.00 I1 Reverse Flow Througb Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum SSN'PSH Available Below NPSH Required

Page 27 of 65 AM Attachment ETE-CME-20i1-1005 Report Generated on 8t1912011 11:29:35

1. 3 Attachment #f3 ' ETE-CME-2011-1005 Report Generated on 8119/2011 11:29:35 AM Page 27 of 65 0811812011 09:09 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-1 011 Page I of I DNC - S:\MILLSTONE\ DATA3\NE MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9,92-120 Rev 4 Add B Millstone Power Station Unit 2 - Service Water System Differences Report Case 2b3 S. IMILLSTONEW4lDATA3WE MSSIPROTOFLO CALCSl92-120 Rev 4 Add B192-120 REV 4-B,.DBD Created: 08/18/20)1 8:25:36AM Default Mode - 8

• CurrentMode - 8 iyv Name Parameter Current Default System Data Pipe: 128.10 BALANCED Flow= 18.00 Pipe: 239.00 RO-6670 BALANCED Flow - 48.00 Node Data ADG Flow (gpm) -10 0 322256725428473 .32256299628028 Valve Data 2-CL-080 Position (%Open)

Attachment #3 - ETE-CME-2011-1005 Report Generated on 8/1912011 11:29:35 AM Page 28 of 65 08/18201 1 09:35 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-101 I Page I of 2 LSTONEM4DATA3VNE MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9,92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convergenc: Pressure-0.0E+0 Sum O=I.OE-2 Friction=.OE-6 FCV=I.OE-4 PCV=I.0E-3 Ternocraturc-S.0, Balancinp Parameters Used Case 4a1 Leak at ARBCCW Flow Sununary Tide Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (gpm) (ft) Ratio Pump5B 23.125 13,703.90 37.24 1.56 Pump 5C 23.125 13,751.06 37.24 1.56 Facility I HEADER 23.125 13,401.92 Facility 2 HEADER 23.125 13,429.21 HV-6439 16.410 5.,760.25 HV-6438 15.410 5,741.31 X-17A 14.875 5,677.44 X-17C 14.875 5,559.45 TB Discharge 23.125 11,519.89 HV-6400 23.250 6,187.46 HV-6399 23.250 6,138.98 X-18B 23.125 6,138.98 X-18C 23.250 6,187.46 TV-6307 23.250 6,145.96 TV-6306 23.250 6,193.96 RB A Discharge 23.125 6,145.96 RB B Discharge 23.125 6,193.96 DGA bypass 7.856 1,465.86 DOB bypass 7.856 1,473.54 DGA Flow 5.940 2.82

! Reverse Flow Through Check.Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum $S NPSH Available Below NPSH Required

Attachment #3 heETE-CME-2011-1005 Report Generated on 8119/2011 11:29:35 AM Page 29 of 65 08/18/2011 09:35 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL- 01 Page 2 of 2 LSTONE\4\DATA3NE MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9,92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report ConvcrPencc: Presur=0.OE+0 Sum 0=I.0E-2 Friction=lOE-6 FCV.1 OE-4 PCV=I.0D-3 Tempcraturr=5.OF3 - Balancinr Parameters Used Case 4al Leak at ARBCCW Flow Summary Tide Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (gpm) (ft) Ratio DOB Flow 5.940 2.90 FV-6389 bypass 1.610 2.82 FV-6397 bypass 1.610 2.90 DG Discharge 12.210 2,945.12 L-I B Strainer Blowdown 3.068 296.87 L-IC Strainer Blowdown 3.068 308.96 Feed to Hypochloride System 5.940 18.00 X-169A 2,469 34.98 X-169B 2.469 35.83 From Chillers 3.068 70.98 PV-6925 3,068 133.06 X-181 3.068 133.06 X-181A 2.067 84.53 X-181B 2.067 48.52 From SWGR Room 4.026 194.18 PV-6927 2.469 32.77 X-1 82 2.067 32.77 PV-6926 2.469 28.04 X-183 2.067 28.04 Feed to Pump Seal Coolink 1.939 48.00 II Reverse Flow Through Check Valve && Pump Flow is Past End of Curve 0* Flow Below Minimum SS NPSH Available Below NPSH Required

Attachment #3 ETE-CME-2011-1005 Report Generated on 81191201111:29:35 AM Page 30 of 65 08/1812011 09:35 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-1011 Page I of I DNC - S:\MILLSTONE\4\DATA3\NEMSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leakPDB - Version 9,92-120 Rev 4 Add B Millstone Power Station Unit 2 - Service Water System Differences Report Case 4al Leak at ARBCCW S:IMILLSTONEI40DATA31NE_MSSIPROTOFLO CALCS192-120 Rev 4 Add B192-120 REV 4-B.DBD Created: 08118/2011 8:25:36AM DefaultMode - 34 *****CurrentMode- 34 Name Parameter Current Default System Data Pipe: 128.10 BALANCED Flow= 18.00 Pipe: 228.00 RO-6669 BALANCED Flow - 24.00 Pipe: 239.00 RO-6670 BALANCED Flow = 24.00 Node Data ARBCCW Flow (gpm) -10 0

S ..... ..... . . ... . . . . . .. . . . .. . . .

Attachment #3 'ETE-CM E-2011.1005 Report Generated on B!19/2011 11:29:35 AM Page 31 of 65 08/18/2011 09:36 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-1011 Page 1 of 2 LSTONE\4\DATA3\NE MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9, 92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convergence: Prcessuc=O.0E+0 Sum 0=I.0F32 Fdction=r.0E-6 FCV-1.0E3,4 PCV-I.OE-3 Tcm*ueature--5.OE Balancing Parameters U*ed Case 4al Leak at ADO Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (n) (gpm) (gpm) (ft) Ratio Pump 5B 23.125 13,703.53 37.24 1.56 Pump 5C 23.125 13,751.07 37.24 1.56 Facility 1 HEADER 23.125 13,401.53 Facility 2 HEADER 23.125 13,429.23 HV-6439 16.410 5,760.54 HV-6438 15.410 5,741.30 X-17A 14.875 5,677.43 X-17C 14.875 5,559.73 TB Discharge 23.125 11,520.17 HV-6400 23,250 6,187.45 HV-6399 23.250 6,139.31 X-1SB 23.125 6,139.31 X-18C 23.250 6,187.45 TV-6307 23.250 6,146.29 TV-6306 23.250 6,193.95 RB A Discharge 23.125 6.146.29 RB B Discharge 23.125 6,193.95 DGA bypass 7,856 1,464.86 DGB bypass 7.856 1,473.59 DGA Flow 5.940 2.82 11 Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• • Flow Below Mfiriium $ NPSH Available Below NPSH Required

Attachment #3  : ETE-CME-2011-1005 Report Generated on 8119/2011 11:29:35 AM Page 32 of 65 08/1812011 09:36 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-1 011 Page 2 of 2 LSTONE\4\DATA3hNE MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9, 92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convergence: Psesaxc-'0.OB+O Sum O'I.0E-2 Friction'.l.0E-6 FCV=1.OE-4 PCV=I.OE-3 TcnP=trure=5,0E Balancingi Parameters Used Case 4al Leak at ADG Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (gpm) (fit) Ratio DGB Flow 5.940 2.90 FV-6389 bypass 1.610 2.82 FV-6397 bypass 1.610 2.90 DO Discharge 12.210 2,944.16 L-lB Strainer Blowdown 3.068 296.88 L-I C Strainer Blowdown 3.068 308.96 Feed to Hypochloride System 5.940 18.00 X-169A 2.469 34.98 X-169B 2.469 35.83 From Chillers 3.068 70.98 PV-6925 3.068 133.06 X-181 3.068 133.06 X-181A 2.067 84.54 X-181B 2.067 48.53 From SWGR Room 4.026 194.19 PV-6927 2.469 32.77 X-182 2.067 32.77 PV-6926 2.469 28.04 X-183 2.067 28.04 Feed to Pump Seal Cooling 1.939 48.00 11Reverse Flow Through Check Valve && Pump FlowBis Past End of Curve

• • Flow Below Minimumn $S NPSH Available Below NPSH Required

Attachment #3 aETE-CME-2011-1005 Report Generated on 811912011 11:29:35 AM Page 33 of 65 08118/2011 09:36 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-1011 Page 1 of I DNC - S:.\MILLSTONE\4\DATA3WNEMSSWROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9,92-120 Rev 4 Add B Millstone Power Station Unit 2 - Service Water System Differences Report Case 4al Leak at ADG S:IMILLSTONE141DATA3WE MSSIPROTOFLO CALCSI92-120 Rev 4 Add B192-120 REV 4-B.DBD Created: 08/1812011 8:25:36AM Default Mode - 34

• CurrentMode - 34 Name Parameter Current Default System Data Pipe: 128.10 BALANCED Flow= 18.00 Pipe: 228.00 RO-6669 BALANCED Flow = 24.00 Pipe: 239.00 RO-6670 BALANCED flow = 24.00 Node Data ADG Flow (gpm) -10 0 Valve Data 2-CL-080 Position (%Open) .415688644584038 .413148407027606 2-SW-140A Position (%Open) 6.3421478966722 6.28955628906281 2-SW-140B Position (%Open) 6.34624994029729 6.2940418648455 2-SW-140C Position (%Open) 6.41065804469728 6.35688485334702 2-SW-140D Position (%Open) 6.38206433364657 6.32900813782273

Attachment #3 A nETE-CME-2011-1005 Report Generated on 8119/2011 11:29:35 AM Page 34of 65 08/18/2011 12:18 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-10 I Page I of 3 LSTONE\4\DATA3\NE MSS\PROTOFLO CALCS\92-120 Rey 4 Add B\92-120 REV 4-B SK-2952 Ieak.PDB - Version 9, 92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convergence: Pressume.OE+0 Sum O=J..0--2 Friction1.OE-6 FCV=I.OE-4 PCVfl.OE-3 Temperature=5.OE Balancinp Partametrs Used Case 4b Leak at ARBCCW Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (gpm) Ca) Ratio Pump 5A 23.125 14,106.64 37.24 1.50 Pump 5C 23.125 14,212.67 37.24 1.48 Facility I HEADER 23.125 13,820.71 Facility 2 HEADER 23.125 13,914.50 HV-6439 16.410 5,566.60 HV-6438 15.410 5,388.97 X-17A 14.875 5,328.99 X-17C 14.875 5,372.48 TB Discharge 23.125 10,973.72 HV-6400 23.250 71125,90 HV-6399 23.250 6,806.18 X-18A 23.125 6,806.18 X-18C 23.250 7,125.90 TV-6308 23.250 5,683.16 TV-6306 23.250 6,065.16 TV-6308A 6.065 1,129.79 TV-6306A 6.065 1,067.63 RB A Discharge 23.125 6,812.94 RB B Discharge 23.125 7,132.78 DGA bypass 7.856 1,411.20 ii Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum $$ NPSH Available Below NPSH Required

Attachment #3 'ETE-CME-2011-1005 Report Generated on 811 9/2011 11:29:35 AM Page 35.of 65 08118/2011 12:18 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-1011 Page2 of 3 LSTONE\4\DATA3\NE MSS\PROTOFLO CALCS'92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9, 92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convemence: Pressue=0.0EtO Sum 0=1.01-2 Frietion=t.OE.6 FCV=I.O,-4 PCV=t.OE-3 Temperature=5.0E BalancinA Parameters Used Case 4b Leak at ARBCCW Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (8pm) (ft) Ratio DGB bypass 7.856 1,372.93 DGA Flow 5.940 2.72 DGB Flow 5.940 2.70 FV-6389 bypass 1.610 2.72 FV-6397 bypass 1.610 2.70 DG Diseharge 12.210 2,789.55 L-1A Strainer Blowdown 3.068 271.57 L-1C Strainer Blowdown 3.068 294.52 Feed to Hypochloride System 5.940 18.00 X-169A 2.469 33.83 X-169B 2.469 33.66 From Chillers 3.068 67.66 PV-6925 3.068 128.62 X-181 3.068 128.62 X-181A 2.067 81.71 X-181B 2.067 46.91 From SWGR Room 4.026 186.94 PV-6927 2.469 31.67 X-182 2.067 31.67 PV-6926 2.469 26.33

!' Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum $S NPSH Available Below NPSH Required

Attachment #3 "ETE-CME-2011-1005 Report Generated on 8119/2011 11:29:35 AM Page 36 of 65 08/18/2011 12:18 PROTO-FLO 4.60 by Proto-Power CoMoration - Serial #PFL-1011 Page 3 of 3 LSTONI\4\DATA3\NE MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9,92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convergence: Pressur-0.0E-+0 Sum 0=I.OE-2 Friction'=L.0-6 FCV=I.OE-4 PCV=I.OE-3 Temperature=5.0B Balancing Parameters Used Case 4b Leak at ARBCCW Flow Sumunary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (Sgp) (ft) Ratio X-183 2.067 26.33 Feed to Pump Seal Cooling 1.939 48.00 1! Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum $$ NPSH Available Below NPSH Required

Page 3? of 65 AM ETE-CME-2011-1005 Report Generated on 8119/201111:29:35 Aitachment #3 Attachment #13 'ETE-CME-2011-1005 Report Generated on 8119r2011 11:29:35 AM Page 37 of 65 08118/2011 12:18 PROTOMFLO 4.60 by Proto-Power Corporation - Serial #PFL-101 1 Page I of I DNC - S:\M1LLSTONE\4\DATA3\NEMSSPROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9,92-120 Rev 4 Add B Millstone Power Station Unit 2 - Seivice Water System Differences Report Case 4b Leak at ARBCCW S:IMILLSTONMA4DATA3lNE_MSSIPROTOFLO CALCSI92-120 Rev 4 Add B192-120 REV 4-B.DBD Created: 08/18/2011 8:25:36AM Default Mode - 36 ***** CurrentMode- 36 Name Parametr Current Default System Data Pipe: 128.10 BALANCED Flow = 18.00 Pipe: 228.00 RO-6669 BALANCED Flow - 24.00 Pipe: 239.00 RO-6670 BALANCED Flow - 24.00 Node Data ARBCCW Flow (gpm) -10 0

Attachment #3 A nETE-CME-201 1-1005 Report Generated on 811912011 11:29:35 AM Page 38 of 65 08/18/2011 12:21 PROTO-FLO 4.60 byProto-Power Corporation - Serial #PFL-1011 Page I of 3 LSTONE\4\DATA3MNE MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9,92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convuracncc: Prcssure-O.OE+O Sum O=I.OE-2 Fdction=1.OE-6 FCV=I,OE-4 PCVWI.0E-3 Temverant'=5.0E,-3 -Balancing Pamrntes Used Case 4b Leak at ADG Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (gp13) () Ratio Pum* 5A 23.125 14,106.29 37.24 1.50 Pump 5C 23.125 14,212.68 37.24 1.48 Facility I IDEADER 23.125 13,820.34 Facility 2 HEADER 23.125 13,914.52 RV-6439 16.410 5,566.88 HV-6438 15.410 5,388.96 X-17A 14.875 5.328.97 X-17C 14.875 5,372.75 TB Discharge .23.125 10,973.98 HV-6400 23.250 7,125.89 HV-6399 23,250 6,806.55 X-18A 23.125 6,806.55 X-18C 23.250 7,125.89 TV-6308 23.250 5,683.46 TV-6306 23.250 6.065.15 TV-6308A 6.065 1,129.85 TV-6306A 6.065 1,067.63 RB A Discharge 23.125 6,813.31 RB B Discharge 23.125 7,132.77 DGA bypass 7.856 1,410.20 11 Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum SS NPSH Available Below NPSH Required

Attachment #3 ETE-CME-2011-1005 Report Generated on 8/19/2011 11:29:35 AM Page 39 of 65 08/18/2011 12:21 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-101 I Page 2 of 3 LSTONE\4WDATA3\NE MSS\PROTOFLO CALCS\92-]20 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9, 92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convcrvencc: Prcsusc=O.OE-0 Si=0I.0E-2 Frictianr1t.0E-6 FCV=I.0-.4 PCV=t.0E-3 Temperature=5.0B Balancing Puamctcrs Used Case 4b Leak at ADO Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (gpm) (ft) Ratio DGB bypass 7.856 1,372.97 DGA Flow 5.940 2.71 DOB Flow 5.940 2.70 FV-6389 bypass 1.610 2.71 FV-6397 bypass 1.610 2.70 DG Discharge 12.210 2,788.59 L-1A Strainer Blowdown 3.068 271.58 L-I C Strainer Blowdown 3.068 294.52 Feed to Hypochioride System 5.940 18.00 X-169A 2,469 33.83 X-169B 2,469 33.66 From Chillers 3.068 67.66 PV-6925 3.068 128.62 X-181 3.068 128.62 X-181A 2.067 81.71 X-181B 2.067 46.91 From SWGR Room 4.026 186.95 PV-6927 2.469 31.67 X-1 82 2.067 31.67 PV-6926 2.469 26.33 II Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum SS NPSH Available Below NPSH Required

-~ ,.--..................

Attachment #3 'ETE-CME-2011-1005 Report Generated on 8/191201111:29:35 AM Page 40 of 65 08/18/201112:21 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-1011 Page 3 of 3 LSTONE\4)DATA3MNE MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9. 92-12 Millstone Power Station Unit 2 - Service Water System Flow Sumnmry Report Convorpence: Pressure-0.0E+0 Sum Q-L.OE-2 Friction=l.OE-6 FCV-=1.0E-4 PCV-L.01,-3 Temperature=5.OE Balancing Parameters Used Case 4b Leak at ADG Flow Summary Title Diameter Flow Minimum Flow NPSHA NPS-I (in) (gpm) (gpm) (ft) Ratio X-183 2.067 26.33 Feed to Pump Seal Cooling 1.939 48.00 HIReverse Flow Through Check Valve && Pump Flow is Past End of Curve

" Flow Below Minimum $$ NPSH Available Below NPSH Required

AttachmentO# A nETE-CME-201 1-1005 Report Generated on 8/191201111:29:35 AM Page 41 of 65 08/1812011 12:21 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-1011 Page I of I DNC - S:.AMILLSTONE\4\DATA3\NEMSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9,92-120 Rev 4 Add B Millstone Power Station Unit 2- Service Water System Differences Report Case 4b Leak at ADI S. MILLSTONEI4IDATA3 WE_MSSIPROTOFLO CALCSI92-120 Rev 4 Add BL92-120 REV 4-B.DBD Created:08/1812011 8:25:36AM Default Mode- 36 ****** CurrentMode - 36 Tpe- Name Parameter Current Default System Data Pipe: 128.10 BALANCED Flow - 18.00 Pipe: 228.00 RO-6669 BALANCED Flow = 24.00 Pipe: 239.00 RO-6670 BALANCED Flow = 24.00 Node Data ADO Flow (gpm) -10 0 Valve Data 2-CL-080 Position (VoOpen) A38823831973723 .438822898451321 0

2-SW-140A Position ( AOpen) 7.08929798497615 7.0895218616805 2-SW-140B Position.(OKOpen) 7.09558729182421 7.09583564711775 2-SW-140C Position (%Open) 7.18595336935983 7-18561510942035 2-SW-140D Position (%Open) 7.1457484764626 7.14541666499543 I.

Attachment #3 E-TE-CME-2011-1005 Report Generated on 8/19/201111:29:35 AM Page 42 of 65 08/18/2011 13:12 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-1011 Page I of 2 LSTONE\4\DATA3\NE MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9, 92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convemence: Pressure'O.OE+O Sum 01.0E-2 FrictIon=l,0E. FCV-I.0E-4 PCV=I.OE-3 Temnperatue5.0E-3 -Balancing Paramelers Used Case 2a2 ARBCCW 54 zpm leak Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (gpm) (0t) Ratio Pump 5B 23.125 93979.82 37.24 2.33 Facility 1 HEADER 23.125 9,579A6 HV-6439 16.410 293.85 TB Discharge 23.125 294.00 IV-6399 23.250 8,411.10 X-18A 23.125 8,411.10 TV-6308 23.250 8,463.69 RB A Discharge 23.125 8,463.69 DOA Flow 5.940 772.51 FV-6389 bypass 1.610 1.97 DO Discharge 12.210 776.98 L-IB Strainer Blowdown 3.068 382.36 Feed to Hypocifloride System 5.940 18.00 X-169A 2.469 58.40 PCV-8943 1.380 26.79 From Chillers 3.068 58.44 PV-6925 3.068 188.94 X-l81 3.068 188.94 X-181A 2.067 120.04 X-181B 2.067 68.90 11Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum SS NPSH Available Below NPSH Required

Attachment t43 ETE-CME-2011-1005 Report Generated on 8/19/2011 11:29:35 AM Page 43 of 65 08/18/2011 13:12 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL- 10 11 Page 2 of 2 LSTONE\4\DATA3MNE MSSNPROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9, 92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convergence: Pressurse0.0E+0 Sum O=1.0F-2 Friction=.0E-6 FCV"- .OE-4 PCV= I,O*-3 Tcmperature=5.0E Balancinp Parameters Used Case 2a2 ARBCCW 54 zpm leak Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (gprn) (ft) Ratio From SWGR Room 4.026 235.56 PV-6927 2.469 46.50 X-182 2.067 46.50 Feed to Pump Sea] Cooling 1.939 48.00

! Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum $S NPSH Available Below NSH Required

Page 44 of 65 11:29:35 AM ETE-CME-201 1-1005 Report Generated en 811912011 Attauhment Attachment #3

1. 3 ETE-CME-2011-1005 Report Generated on 811 W2011 11:29:35 AM Page 44 of 65 08/18/2011 13:12 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-101I Page I of I DNC - S:MILLSTONE\4\DATA3'iNEMgS\PROTOFLO CALCSW2-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9,92-120 Rev 4 Add B Millstone Power Station Unit 2 - Service Water System Differences Report Case 2a2 ARBCCW 54 gpm leak S.AM!LLS.TONE140DATA31NE MSS'.PROTOFLO CALCSM92-120 Rev 4 Add B192-120 REV 4-B.DBD Created:08/18/2011 8:25:36AM Default Mode - 3 ***** CurrentMode - 3

_p Name Parameter Current Default System Data Pipe: 128.10 BALANCED Flow - 18.00 Pipe: 239.00 RO-6670 BALANCED Flow = 48.00 Node Data ARBCCW Flow (gpm) -54 0 Valve Data 2-CL-080 Position (%Open) .301257330966614 .300647488186602 S

Attachment~~~~~~~~~~~ -0110

1. 3.... Re.r Gee.e on8..21.1:93.A.Pg

.T-M 5 f Attachment #3 ETE-CME-2011-1005 Report Generated on 8119/2011 11:29:35 AM Page 45 of 65 08/18/2011 13:15 PROTO-FLO 4.60 by Proto-Power Corporation - Serial #PFL-1O 1  : Page I of 2 LSTONE\4\DATA3\NE MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9, 92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convergence: Pesure=O.OE0+ Sum O=t.,E-2 Frictioxn-l.0E-6 FCV='I.OE,-4 PCV=I.OE-3 Tetmvnetuzm=5.0E Balancing Parameters Used Case 2b3 ADO 53 Apm leak Flow Summary Tite ' Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (gp1m) (ft) Ratio Pump 5B 23.125 10,977.02 37.24 2.07 Facility 1 HEADER 23.125 10,597.12 HV-6439 16.410 275.68 TB Discharge 23.125 275.84 HV-6399 23.250 9,500.22 X-18B 23.125 9,500.22 TV-6307 23.250 8,090.71 TV-6307A 6.065 1,409.51 RB A Discharge 23.125 9,500.22 DGA Flow 5.940 719-22 FV-6389 bypass 1.610 1.83 DO Discharge 12.210 723.65 L-1B Strainer Blowdown 3.068 361.90 Feed to Hypochioride System 5.940 18.00 X-169A 2.469 54.79 PCV-8943 1.380 25.13 From Chillers 3.068 54.83 PV-6925 3.068 177.25 X-181 3.068 177.25 X-181A 2.067 112.61 H!Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum SS NPSH Available Below NPSH Required

Attachment #3 ETE-CME-2011-1005 Report Generated on 8119/2011 11:29:35 AM Page 46 of 65 08/18/2011 13:15 PROTO-FLO 4.60 byProto-Power Corporation - Serial #PFL-1011 Page2 of 2 LSTONE\4\DATA3\NE MSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9, 92-12 Millstone Power Station Unit 2 - Service Water System Flow Summary Report Convergence: Pressure0.OE+0 Sum O=!,0E-2 Friction=t.OE-6 FCV=I.0-E4 PCV=I.0E-3 Temperature=5.0E Balanrina Parameters Used Case 2b3 ADG 53 avm leak Flow Summary Title Diameter Flow Minimum Flow NPSHA NPSH (in) (gpm) (gpm) (0) Ratio X-18IB 2.067 64.64 From SWGR Room 4.026 221.00 PV-6927 2.469 43.63 X-182 2.067 43.63 Feed to Pump Seal Cooling 1.939 48.00 1! Reverse Flow Through Check Valve && Pump Flow is Past End of Curve

• • Flow Below Minimum S$ NPSH Available Below N'PSH Required

Attachment #3  :-TE-CME-2011-1005 Report Generated on 8119/2011 11:29:35 AM Page 47 of 65 081t8/2011 13:15 PROTO-FLO 4.60 by Proto-Power Corporation- Serial #PFL-1011 Page I of I DNC - S:\MILLSTONE74\DATA3\NEMSS\PROTOFLO CALCS\92-120 Rev 4 Add B\92-120 REV 4-B SK-2952 leak.PDB - Version 9,92-120 Rev 4 Add B Millstone Power Station Unit 2 - Service Water System Differences Report Case 2b3 ADG 53 gpm leak S:IMILLSTONEI4iDATA3WE_MSSIPROTOFLO CALCS592-120 Rev 4 AddBI92-120 REV 4-B.DBD Created:08/18/2011 8:25:36AM Default Mode- 8

• CurrentMode- 8 Name Parameter Current Default r System Data Pipe: 128.10 BALANCED Flow= 18.00 Pipe: 239.00 RO-6670 BALANCED Flow 49.00 Node Data ADG Flow (gpm) -54 0

Attachment #4 AETE-CME-2011-1005 Report Generated on 8119/2011 11:29:35 AM Page 48 of 65 Attachment B Page BI Exam Data Sheet Millstone Power Station UL ONIC EXAMINATION

_ _ _ __ STRAIGHT BEAM MEASURETUNTS Planthvst~ne " Unit 3 Page .. of .JL System & Zone No.__ Exam Data Sheet No NIA Component ID Line 10" GJD.4 AWO Number 53102457364 ComponentDescription 10".Flame DrawingNo, 25203-20150 SH-.471 Exampap~e~naneei~r~hormti~ n-,gX438193Lne. A_________

Instrnxaaut & Settings Calbration Block(s) Component Data Manufacturer Popawetrics Type Seiial N9 . Material ComponeT. N/A Model No. 36 DL Plus Step Block . 061291 C/s Cmoeti I Seri"l No. 002181809 Stop Block.. .99-0791 C(S A ttahments Yes Range Velocity Delay 5.00" . ..

.2326 X/A Typo

.Clbao.check, Time f blockti~ckatus Min. Mpx.

bInumazentRea(Ung min. max.

Zero Value 4923 initial 5 Awl., 4.DD9" AIV" A.UO" Cal Tole~rance dý.002" lnt--4*i~e N/A NIA, N/A N/A N/A Satemediate N/A NI/A N/A N/A NIA Search U-t Data 5inad .. V"P:46, .100" 4.000" .. 1- 0". ... 4.QQW" Manufactizre Panamtsics..

Type No. D79l i..RM . . C'Q!'

. . .DAt .. . .. Dat.

,Temperature StrialNo., 19519 . BrezW Ultrage lf. Cal. BIocITcm. N/A Frequency 5.0 MWZ atchNo, .092251I Component Temp. NIA-Size .312" SAP Batch Mgmt. No. NIA. Thermometer No. N/A Sketch/Comments Area - Attach Photo(s) of Relevant Condifions Separately Examined UT Points at 1:00 Through 9:00 Positions Around Flange See Attached Generic Sketch Sheets for UT Test Results ExaminI (p ip ) .j ." .. 1 Reviewer(sign) >sz-' I.~- M-k

-pý A~i~ ev Seqy T:~lDt ANI/ANII If Required (Sigp) N/A Date Level of Use AE -A N F U -0 Reference WRA~LTO

Attachment #4 "ETE-CME-2011-1005 Report Generated on 8119/2011 11:29:35 AM Page 49 of 65 Attachment B Page B2

Attachment #4 ETE-CME-2011-1005 Report Generated on 8/19/2011 11:29:35 AM Page 50 of 65 Attachment B Page B3 GENERIC SKETCH SHEET Plant Millstone Unit 2 Page 3. of ¶ System "WA" Train Serviob Wate". Zone Exm a Package N IA Cdmponent ID Llhe lO. Jdo4 I* I Bxa=m or Cbmlta. 4Cen I'l s r> FLISLý r1AOLES, A- EAC14 UT PQEL T AK~tý M*I NJ. /141C-K I c - r.E

.Q Examihtr- b >y1j W 1 _ _.__ ___,__gt. i _ _.

xa i_ .... Date . .DfA Level ofUseI

Page 51 of 65 Attachment #4 ETE-CME-2011-1005 Report Generated on 8119/2011 11:29:35 AM Attachment B Page B4

~1 2 I E R SK& H HPag E U.nit Plant .llf stone Syst~em :A"Tran Service W~ ..... Zone H/A Earn Pakg N[

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ETE-CME-2011-1005 Report Generated on 8119/2011 11:29:35 AM Page-52 of 65 Attachment #4 Attachment B Page B5 Plant Mllstone Unt2Pane ~of i Sybtiem OAn Train Setyoe Water.. . Zone N/A E96M OaoKige IA BXi~ QbT\4Et >U ýAplfrs A-T 5:ACV UT (eOAK5¶ ArO!

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ETE-CME-2011-1005 Report Generated on 8/1912011 11:29:35 AM Page 53 of 65 Attachment #4 Attachment B Page B6 F

GEN'ERIC SKETCH SHEET Plant Miloe Unit 2Page (-Pof Sy~tem KA" Train Seryi Water .. Zone N/A Eam Piackag0. I Cdmponeht ID Lile O!.JG'D-4 7 QEAtýtN3Gr5 0 P6TA~1ýQ F-t>eOýrt) C~v-7-ItU5 F AT Th+F A4 P051wnC~tj

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Attachment #4 ETE-CME-201 1-1005 Report Generated on 5/1912011 11:29:35 AM Page 54 of 85 Attachment B Page B7 I

GrNERtIC SKETCH SHEE-T Plant M1lI6tons Unit 2 Page 2.of 2 Sy~tem W Traln Setvig Wate. -. Zone N/!A. Ei!fli Pack~g. 6-4tA CdMpl5nehtb ID bJGrD i~- ~ ~ SOWTAk v-J.3t> GFUVWE.V',ý eOL-T- k4ol-FS A T -H5_ 5 Post poSITTO 4A I I Ex~a&Cbneriamts: -~t> 5-CA r- %.AU-T-t e I--Or K PctD Exatnihoir -M- LOV6)) nate___________

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Attachment #4. ETE-CME-2011-1005 Report Generated on 8/1912011 11:29:35 AM Page 55 of 65 Attachment B Page B8 Gt4ERIC SKETCH SHEET

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Attachment #4 ETE-CME-2011-1005 Report Generated on 8/1912011 11:29:35 AM Page 56 of 65 Attachment B Page B9 GeN, RIC SKETCH SHEET Plant HIýLone ... Unit 2 Page 2.of '

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Attachment #4  :-TE-CME-2011-1005 Report Generated on 8/19/2011 11:29:35 AM Page 57 of 65 Attachment B Page BIO Plant MLfll~tone Unit _ Page ko of kk Systemr "A' Train Service Water Zone _NIA ýExam Package.. Nt

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ETE-CME-2011-1005 Report Generated on 811912011 11:29.35 AM Page 58 of 65 Attachment #4 Attachment B Page BlI

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Attachment #4 *ETE-CME.201 1-1005 Report Generated on 8119/2011 11:29:35 AM Page 59 of 65 Attachment B Page B12 Exam Data Sheet Millstone Power Station ULTRASONIC FXAM] ATION STRAIGHT BEAM MRASUREMENTS Plant Kilstone Unit 3 Page nLof A-System & Zone No. _Exam Data Sheet No N/A Component 33 Lire 10"IGD.A AWO Number .53102457364 Componont Description 10" Flange Drawing No, 25203-20150 SM, 471

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Attachment#4 ETE-CME-2011-1005 Report Generated on 8/1912011 11:29:35 AM Page 60 of 65 Attachment B Page B13 1

GENERIC SKETCH SHEET Plant Millstone . Unit 2 Page L of .

System A" Train Service Water Zone N/A Exam Package IA ComponentiID.line10" JGD-4 I I '30 *JALt (fVCk, QE CLECTrIOk

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Reviewer NnAAA - L.velDe Dat DI_e _ _

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Attachment # A tETE-CME-2011-1005 Report Generated on 8h1 9/2011 11:29:35 AM Page 61 of 65 Attachment B Page B14 GENERIC SKETCH SHEET Plant Mllstone Unit 2 Page *. of __

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Attachment #4 ETE-CME-2011-1005 Report Generated on 811912011 11:29:35 AM Page 62 of 65 Attachment B Page B15

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