ML13091A038

Alternative Request IR-3-17 to ASME Section XI for Repair/Replacement of Class 3 Service Water System Vaves

ML13091A038
Person / Time
Site:	Millstone
Issue date:	03/28/2013
From:	Grecheck E Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13091A038 (97)

Text

Dominion Nuclear Connecticut, Inc.

5000 Dominion Boulevard, Glen Allen, VA 23060 - (A)[UUUU]U (2)UU Web Address: www.dom.com March 28, 2013 U.S. Nuclear Regulatory Commission Serial No.13-169 Attention: Document Control Desk NLOSNWDC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 ALTERNATIVE REQUEST IR-3-17 TO ASME SECTION Xl FOR REPAIR/REPLACEMENT OF CLASS 3 SERVICE WATER SYSTEM VALVES Pursuant to 10 CFR 50.55a(a)(3)(ii), Dominion Nuclear Connecticut, Inc. (DNC) requests an alternative to IWA-5250 of Section Xl of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code for Millstone Power Station Unit 3 (MPS3). Specifically, DNC requests approval of an alternative method for repair of valves in the MPS3 Service Water System Class 3 piping due to dealloying. A code repair of the affected valves is not possible at this time since the valves are not isolable and cannot be replaced on line. This alternative request is needed until the next refueling outage, which is currently scheduled for mid-April 2013. Compliance with the requirements of 10 CFR 50.55a would result in a hardship without a.compensating increase in the level of quality and safety. The proposed alternatives from specific 2004 ASME Code requirements are provided in Attachment 1.

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

Sincerely, Eugene S. Grecheck Vice President - Nuclear Engineering and Development

Attachment:

1. Alternative Request IR-3-17 to ASME Section Xl for Repair/Replacement of Class 3 Service Water System Valves Commitments made in this letter: None

Serial No.13-169 Docket No. 50-423 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd Suite 100 King of Prussia, PA 19406-2713 J. S. Kim Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 C 2A Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

I Serial No.13-169 Docket No. 50-423 ATTACHMENT I ALTERNATIVE REQUEST IR-3-17, TO ASME SECTION XI FOR REPAIR/REPLACEMENT OF CLASS 3 SERVICE WATER SYSTEM VALVES MILLSTONE POWER STATION UNIT 3 DOMINION NUCLEAR CONNECTICUT, INC.

Serial No.13-169 Docket No. 50-423 Attachment 1, Page 1 of 6 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)

--Hardship or Unusual Difficulty Without. Compensating Increase. in Level of Quality or Safety--,

1. ASME Code Components Affected ASME Code Class: Code Class 3

Reference:

ASME Section Xl, IWA-5250.

Examination Category: D-B Item Number: D2.10

Description:

Millstone Power Station Unit 3 (MPS3) "A" and "B" trains, Service Water System (SWS) valves.

Components: Neles-Jamesbury valves fabricated from alloy C95400 aluminum

- bronze (SB 148 Grade CDA 954). See below.

ValveVav Nu,.Sir i : Train . , ,,ze/Type Descriptor 3SWP*V658 A 3" Flat Face Suction isolation valve for the 'A' MCC and Rod Ball Valve Control area service water booster pumps 3"Flat Face Return isolation valve for the 1A MCC and Rod

.ABall Valve Control area room cooler 3" Flat Face Return isolation valve for the'l B MCC and Rod.

3SWP*V661 " Ball Valve Control area room cooler 3SWP*V663 A 1%" Flat Face Return isolation valve for the 'A' charging pump Ball Valve cooler 3SWP*V664 B 11/2" Flat Face Supply isolation valve for the 'B' charging pump Ball Valve cooler 3SWP*V665 B. 1/ " Flat Face Return isolation valve for the 'B' charging pump Ball Valve cooler 3SWP*V668 B 3" FlatValve Ball Face Suction isolation valve for the booster

'B' MCCpumps and Rod.

Control area service water

Serial No..13-169 Docket No. 50-423 Attachment 1, Page 2 of 6

2. Applicable Code Edition and Addenda

ASME.Section Xl, 2004 Edition (No Addenda).

3. Applicable Code Requirement

The 2004 Edition of ASME Section Xl, IWA-5250(a)(3) requires that the source of leakage be evaluated for repair or replacement in accordance with IWA-4000.

4. Reason for Request.

DNC requests approval of an alternative to IWA 5250(a)(3) for performing the repair/replacement in accordance with IWA-4000 for valves in the MPS3 Service Water System Class 3 piping. This alternative is requested on the basis that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and. safety.

Valves 3SWP*V6611664/66516681658/6591663 were identified as weeping through the valve bodies during visual examination of SWS piping. These valves are fabricated from aluminum - bronze alloy C95400 that is susceptible to dealloying where the aluminum leaches out of the alloy leaving microscopic voids in the material. This process progresses slowly and is generally characterized by an observed area of accumulated corrosion debris or wetness that returns following cleaning and drying of the surface'.

To address this condition, the degraded valves will be replaced with valves fabricated from a more suitable material. Replacement valves have been ordered on an expedited basis and are expected to be onsite to support planned replacement during the upcoming outage.

Unit 3 is currently in Mode 1 .at 100% power and replacement would require an extended unit shutdown since the valves are not isolable during power operation and replacement valves are not available at this time. Unit shutdown this close to the end of the operating

-cycle to perform repairs would constitute a hardship without a compensating increase in the level of quality and safety due to operational considerations associated with less reactive fuel and the need to process large volumes of coolant during the approach to criticality upon returning the unit to service. Approval of the requested alternative will allow deferral of ASME Code required repair. until the next refueling outage, which is currently. scheduled for mid-April 2013.

5. Proposed Alternative and Basis for Use 5.1 Proposed Alternative As an alternative to the requirements of IWA-5250, DNC will monitor (as it is monitoring now) the affected valves once per shift to detect changes in leakage rate of the valves. The inspection results are/will be documented to determine trends.

Should leakage increase above one drop per minute steady state, an engineering evaluation will be performed to assess the significance of the change in leakage

Serial No.13-169 Docket No. 50-423 Attachment 1, Page 3 of 6 regarding structural integrity.

Structurally robust enclosures have been installed on the affected valves as defense-in-depth measures to mitigate the effects of increased leakage until repairs can be made. The enclosures are provided with a perimeter seal at the mating surfaces of the two halves of the enclosure as well as the enclosure ends where they surround the attached piping. The design of the enclosure is such that the pipe ends are captured within the enclosure. The enclosure is designed to withstand the normal operating pressure and design temperature of the SWS such that system operability is maintained in the unlikely event of a structural failure of an affected valve. Each enclosure is seismically supported in a manner that ensures no additional weight is added to the piping system. Each enclosure is provided with a drain valve which is maintained, in the open position to support leakage monitoring of the degraded valve.

The drain valve can still be closed at the discretion of the shift manager.

5.2 Basis for Use Scope Indications of through-wall dealloying were identified on the subject valves. The observed condition is localized and the weepage rate is sufficiently small that it is presently not quantifiable. Further, the construction of the affected components does not support use of qualified NDE methodologies for flaw characterization.

Specific Considerations The SWS system is a low-pressure: system with normal operating pressure .of approximately 50 psig and a maximum design pressure of 100 psig. Normal system supply temperature is between 33 to 75*degrees F. The system is described in detail in Section 9.2.1 of the MPS3 Updated Final Safety Analysis Report (UFSAR).

Two independent SWS trains are required to be operable in Modes 1, 2, 3, and 4.

An inoperable SWS train must be returned to operable! status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, otherwise the unit must be placed in hot standby within the next six hours and in cold shutdown within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Consequences of potential system interactions, including flooding, spray on equipment, and loss of flow to the system, are addressed in UFSAR Section 3.6,

"'Protection. Against Dynamic Effects Associated with the Postulated Ruptures of Piping." The SWS is a moderate energy system and the consequential effects of.

spray and flooding associated with a pipe crack have been analyzed. Safety-related equipment is either designed to operate in a spray environment, or protected if sensitive to 'spray. Flooding in a given area is enveloped by worst case flow from an opening in a local pipe due to a "critical crack" with an area equivalent to a rectangle of length one-half the pipe diameter and a width equal to one-half the pipe wall thickness. This assessment bounds the condition under consideration.

DNC -has prepared a structural integrity evaluation to support continued operation'of the affected valves. As an added measure of defense-in-depth, each of the affected

Serial No.13-169 Docket No. 50-423 Attachment 1, Page 4 of 6 valves has been fully enclosed to ensure that leakage and spray is limited in the event of a structural failure of a valve during the period of continued operation.

Condition monitorinq of the affected components.

Each affected valve has been provided with a structurally robust enclosure.

The enclosure, is provided with a drain valve that is maintained open and monitored once per shift. The inspection results are recorded in a log maintained in the control room. Should leakage increase above one drop per minute steady state, an engineering evaluation would be performed to determine the significance of the change. in leakage with respect to structural integrity and the associated relevance to, the basis for continued operability.

Structural Evaluation A structural evaluation of the subject valves has been documented in Engineering Technical Evaluation (ETE) CME-2013-1005, "Structural Integrity Evaluation for MPS3 Dealloyed Aluminum - Bronze Valves" and assumes the component is fully dealloyed. This document is provided as Enclosure 1 in support of this alternative request. The structural evaluation is based on data accumulated from materials testing on similar components removed from Surry Power Station (SPS) in the mid 1990's. The SPS test report is provided as Enclosure 2.

The structural evaluation takes into account pipe stress levels for deadweight, internal pressure, seismic loads and thermal expansion/anchor motion immediately upstream and downstream of the subject valves.., .The allowable stress for the.

aluminum - bronze material (i. e., SB-148 95400) is derived based on data-contained in Enclosure 2 .(limiting tensile stress for 100% dealloyed condition) and ASME Section Ill, Article 111-3000 (Reference 10 of Enclosure 1). The dealloyed aluminum -

bronze test data developed in Enclosure 2 (Ultimate Strength Su vs. percent dealloy) is plotted as shown in Figure 1 (Attachment 3 to Enclosure 1). The plotted data only includes valid test specimens with break locations within gage marks. Specimens with break locations on or outside gage mark locations or specimens that failed in the grip are excluded. Although only one "1'00%"' dealloyed specimen was tested, plotting of the other dealloyed specimens tends to support.that the selected lower bound "100% dealloyed" Su value is reasonable. For 100%. dealloyed SB-148 95400, the lower bound ultimate tensile strength is Su = Sy = 10,400 psi (Enclosure 2). Therefore, per ASME Section III, Article 111-3000, the appropriate allowable would be 25% of Su or 2600 psi. Sc = Sh = 2600 psi (See Attachment 4 of Enclosure 1). A casting quality factor is not applied to this allowable as the tested specimens are considered-to be representative of the .100% dealloyed condition. Due to the installation of the valves in. relatively weak copper nickel piping systems, stresses tend to be lower than for comparable carbon steel piping systems. Consequently, the reduced structural capability of the assumed 100% dealloyed aluminum - bronze valves is more easily accommodated.

The potential for impact load brittle fracture resulting from loss of ductility associated with dealloying is also addressed in Enclosure 1. A review of Enclosure 2 shows

Serial No.13-169 Docket No. 50-423 Attachment 1, Page 4 of 6 valves has been fully enclosed to ensure that leakage and spray is limited in the event of a structural failure of a valve during the period of continued operation.

Condition monitoring of the affected components.

Each affected valve has been provided with a structurally robust enclosure.

The enclosure, is provided with a drain valve that is maintained open and monitored once per shift. The inspection results are recorded in a log maintained in the control room. Should leakage increase above one drop per minute steady state, an engineering evaluation would be performed to determine the -significance of the change in leakage with respect to structural integrity and the associated relevance to, the basis for continued operability.

Structural Evaluation A structural evaluation of the subject valves has been documented in Engineering Technical Evaluation (ETE) CME-2013-1005, "Structural Integrity Evaluation for MPS3 Dealloyed Aluminum - Bronze-Valves" and assumes the component is fully dealloyed. This document is provided as Enclosure 1 in support of this alternative request. The structural evaluation is based on data accumulated from materials testing on similar components removed from Surry Power Station (SPS) in the mid 1990's. The SPS test report is provided as Enclosure 2.

The structural evaluation takes into account pipe stress levels for deadweight, internal pressure, seismic loads and thermal expansion/anchor motion immediately upstream and downstream of the subject valves.- The allowable stress, for the aluminum - bronze material (i. e., SB-148 95400) is derived based on data contained in Enclosure 2 '(limiting tensile stress for 100% dealloyed condition) and ASME Section III, Article 111-3000 (Reference 10 of Enclosure 1). The dealloyed aluminum -

bronze test data developed in Enclosure 2 (Ultimate Strength Su vs. percent dealloy) is plotted as shown in Figure 1 (Attachment-3 to Enclosure 1). The plotted data only includes valid test specimens with break locations within gage marks. Specimens with break locations on or outside gage mark locations or specimens that failed in the grip are excluded. Although only one "100%" dealloyed specimen was tested, plotting of the other dealloyed specimens tends to support that the selected lower bound "100% dealloyed" Su value is reasonable. For 100% dealloyed SB-148 95400, the lower bound ultimate tensile strength is Su = Sy = 10,400 psi (Enclosure 2). Therefore, per ASME Section III, Article 111-3000, the appropriate allowable would be 25% of Su or 2600 psi. Sc = Sh = 2600 psi (See Attachment 4 of Enclosure 1). A casting quality factor is not applied to this allowable as the tested specimens are considered to be representative of the .100% dealloyed condition. Due, to the installation of the valves in relatively weak copper nickel piping systems, stresses tend to be lower than for comparable carbon steel piping systems. Consequently, the reduced structural capability of the assumed 100% dealloyed aluminum - bronze valves is more easily accommodated.

The potential for impact load brittle fracture resulting from loss of ductility associated with dealloying is also addressed in Enclosure 1. A review of Enclosure 2 shows

Serial No.13-169 Docket No. 50-423 Attachment 1, Page 5 of 6 essentially no difference between yield and ultimate strength. This indicates minimal dealloyed material ductility. ASME Section III, Equation 9 considers impact loads such as seismic, water hammer, and relief valve discharge. Referring to Table 2 of Enclosure 1,, the maximum Equation 9 faulted stress to allowable stress ratio is 0.65 (3SWP*V664; 4064.2/6240 = 0.6513). This provides a large margin for protection from impact loading which could initiate brittle fracture. Table 1 of Enclosure 1 provides a summary of the stresses selected from the pipe stress analysis calculations (References 7, 8, 9, 13, 14, 15, 16 and 20). Table 2 (Attachment 5 of Enclosure 1) provides a summary of the valve calculated stresses demonstrating that the valves meet the faulted code equation limits and that the valves are operable.

Additionally, hydrostatic pressure testing has been performed on two similar (same manufacturer, type, size, pressure. rating,. in service conditions and service -time) weeping/degraded Neles-Jamesbury 3-inch ball valves that were exhibiting a weeping condition associated with dealloying., These tests subjected the valves to a pressure that is 150% of the valves design pressure rating, demonstrating significant remaining structural capability of the degraded valves. The hydrostatic testing performed on these dealloyed valves meets the original construction code pressure test requirements (i.e., these degraded valves in their current degraded condition meet the pressure testing requirements placed upon a new valve).

Conclusion Reasonable assurance of continued structural integrity of the degraded valves has been demonstrated. The structural evaluation assumes the components are fully dealloyed and includes consideration of potential impact loads which could initiate brittle fracture. The assumption that the valves are fully dealloyed is conservative given the successful .hydrostatic testing performed on similar degraded components.

It is concluded that the reduced structural capability of the. dealloyed aluminum -

bronze valves can be accommodated by the current piping system design.

While not required to support the structural integrity assessment, the installation of structurally robust enclosures coupled with a conservative condition monitoring acceptance criterion, provides added assurance that the function of the SWS will not be compromised in the unlikely event of structural failure.

6. Duration of Proposed Alternative This alternative is requested until the completion of the next refueling outage, currently scheduled to begin mid-April 2013.

7. Precedent By a letter dated March 12, 2012 (Reference 8.4), South Texas Project requested relief from IWA-5250 of Section Xl of the ASME Boiler and Pressure Vessel Code to defer code repair of flaws found in the Unit 2 Essential Cooling Water (ECW) Class 3 piping.

The flaws were identified as indications of through-wall dealloying located on the body of

Serial No.13-169 Docket No. 50-423 Attachment 1, Page 6 of 6 cast aluminum-bronze ECW valves. On April 13, 2012, pursuant to 10 CFR 50.55a(a)(3)(ii), the NRC staff verbally authorized the use of the alternative request (Reference 8.5). The NRC safety evaluation documenting the technical basis of the verbal authorization was issued on August 16, 2012 (Reference 8.6).

8. References 8.1 Millstone Power Station Unit No. 3 Final Safety Analysis Report 8.2 ETE-CME-2013-1005, Structural Integrity Evaluation for MPS3 Deall.oyed Aluminum Bronze Valves. (Enclosure 1) 8.3 Materials Engineering Laboratory Report, Surry. Hot Lab NESML-Q-104 (Enclosure 2) 8.4 South Texas Project, Unit 2, Request for Relief from ASME Boiler and Pressure Vessel Code, Section Xl Requirements for the Essential Cooling Water System (Relief Request RR-ENG-3-08); ML12079A034.

8.5 NRC Staff Verbal Authorization of the Use of RR-ENG-3-08, ML121040361.

.8.6 NRC Safety Evaluation, South Texas Project, Unit 2 - Request for Relief RR-ENG 08 from ASME Boiler and Pressure Vessel Code, Section Xl Requirements for Repairs to Class 3 Valves in Essential Cooling Water System Piping, ML12201A256.

Serial No.13-169 Docket No. 50-423 Enclosure 1 Engineering Technical Evaluation (ETE) CME-2013-1005, "Structural Integrity Evaluation for, MPS3 Dealloved Aluminum - Bronze Valves."

MILLSTONE POWER STATION UNIT 3.

DOMINION NUCLEAR CONNECTICUT, INC.

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17. 10CFR50.59/72.48 applicability review forms (CM-AA-400) Att#2 .

18. 10CFR50.59/72.48 screen form (CM-AA-400) -- El

19. 10CFR50.59/72.48 evaluation form (CM-AA-400) __

'20. AdditiohalAttachments .4..:M 1.'. .

Attachment . # of Pages Description Attachment.A_Figure 1 AL Bronze 1 Add Description Dealloyed.pdf Attachment B Article 111-3000.pdf. 2 Add Description Attachment_5_Table_1_Table_2.pdf: 1 Attachment_6_HydrostaticTestRes 8 ults.pdf Attachment 7 Material Input.pdf 1 Add Description Attachment.8_MRIR.pdf 18 Attachment_9_WO_53M30412156.pd 12 f

P2m1.Distpibeionts Primary Recipient(s): '

ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 2 of 56 limp& Engineering Technical Evaluation Cover Sheet and Body

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IF.0-: 0, ii Copy To? Other Recipient / Department or Location Copy To? Other Recipient / Department or Location o Preparer

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LI Nuclear Document Management 2.0 Source Document

1) CR506519 - Leakage and corrosion identified on 3SWP*V661

2) CR506524 - Corrosion build up identified on service water valves

3) CR507564 - Evidence of leakage on 3SWP*V857, V658,V659 and V663 4)' CR507567 - Evidence of leakage on 3SWP*V674 and V656 3.0 Record of Revision Revision 1 - Added valves 3SWP*V857, 3SWP*V658, 3SWP*V659, 3SWP*V663 and 3SWP*V674 associated with "A" service water train.

'4.0 Purpose

Purpose:

The purpose of this Engineering Technical Evaluation (ETE) is to document the structural integrity evaluation for dealloyed aluminum bronze valves at Millstone Unit 3 (MPS3). Condition report CR506519 and CR506524.identify through wall weeping on "B"service water train valves 3SWP*V661, 3SWP*664, 3SWP*V665 and 3SWP*V668. These valves are not isolable (Reference 2) and cannot be replaced on line. Revision 1 adds the following unisolable valves: 3SWP*V658, 3SWP*V659, 3SWP*V663 &

3SWP*V674 and isolable valve 3SWP*V857 associated with "A" service water train. The through wall weeping is assumed to be due to dealloying of the aluminum phase in the aluminum bronze valves. This, information will be used along with other available information, (including a hydrotest of similar dealloyed valves 3SWP*V870 and 3SWP*V873 Neles-Jamesbury ball valves) to form the basis for continued operability of the above valves.

Note: Through wall weepage due to dealloying is a Code non compliance. However structural integrity (design function) can be demonstrated in spite of through wall weepage. Relief from the Code will be needed for continued system operation. Historic precedence indicates that typically a 30 day cycle (Reference 18) from leak identification to code relief submittal is acceptable.

Background:

ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 3 of 5.6 MEngineering Technical Evaluation Cover Sheet and Body O Dominion- _____________________

Throughwall leakage was discovered on valve 3SWP*V661. Condition Report CR506519 stated:.

While performing an ISI system leak test (VT-2) of the "B"service water system, active leakage was observed on 3SWP*V661 valve body. The examiner could not determine the exact origin of the leak due to the large amount of corrosion and salt build up. No DPM was obtained due to the leak being more like seepage. A photo is attached showing a water droplet, when blotted it would reappear.

There are other areas on the valve body that show major corrosion and salt build up. The flange bolting shows major corrosion and should be carefully cleaned to determine how much wastage exists. The photos attached [to condition report CR506519] show actual leakage, other areas on body and salt residue on the 30' header below.

Supplemental Condition Report CR506524 stated:

While performing an ISI system leak-test (VT-2) of the "B"service water system, the examiner identified heavy corrosion and or salt build up on service water valves; 3SWP*V664, 3SWP*V668 and 3SWP*V665. Valves 3SWP*V664 and 3SWP*V665 also showed bolting degradation.

Follow on extent of condition CR507564 stated:

While performing extent of condition VT-2 examinations of "A" train service watervalves ISI identified evidence of leakage on 3SWP*V857, V658, V659 and V663. Excessive corrosion and what appears to be salt build up was identified in numerous areas on the valves. Some areas appeared to be wet/moist. A detailed visual inspection will be performed after valves are cleaned and an ample hold time at normal pressure to determine exact origin of leakage (whether mechanical or through wall). Work was performed under WO 53102599042.

Follow on extent of condition CR507567 stated:

While performing extent of condition VT-2 examinations of "A" train service water valves ISI identified evidence of leakage on 3SWP*V674 and 656. Small amount of corrosion and what.

appears to be salt build up was identified on one or two areas on the valve body. Based on the as found evidence, leakage could be from a mechanical joint. A detailed visual inspection will be performed after valves are cleaned and an ample hold time at normal pressure to determine exact origin of leakage (whether mechanical or through wall). Work was performed under WO 53102599042. [Note: Valve 3SWP*V656 is non safety related and is outside the scope.of this ETE.]

Valve 3SWP*V661 - Neles-Jamesbury 3" Flat Face Ball Valve Valve.3SWP*V663 - Neles-Jamesbury 1 1/2" Flat Face Ball Valve Valve 3SWP*V664 - Neles-Jamesbury 1 1/2" Flat Face Ball Valve Valve 3SWP*V665 - Neles-Jamesbury 1 1/2" Flat Face Ball Valve Valve 3SWP*V668 - Neles-Jamesbury 3" Flat Face Ball Valve' Valve 3SWP*V857 -,Neles-Jamesbury 3" Flat Face Ball Valve Valve 3SWP*V658 - Neles-Jamesbury 3" Flat Face Ball Valve

ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 4 of 56 EngineeringTechnical Evaluation Cover Sheet and Body Dominion-Valve 3SWP*V659 - Neles-Jamesbury 3" Flat Face Ball Valve Valve 3SWP*V674 - BNL 3" Full Port Ball Valve 5.0 Design Inputs and Assumptions Design Inputs:.

1. The subject valve bodies are fabricated from aluminum bronze material (References.3, 6 and 23).

Specifically:

• Body Material SB 148 Grade CDA 954

2. Virginia Power Report NESML-Q-104 (References 5). Dealloyed tensile strength for SB-148, Grade CDA 954: 10,400 psi

3. ASME Section'll, SB-148, Specification for Aluminum Bronze Sand Castings (Reference 11):

Minimum Material Properties (i.e., as fabricated without dealloying):

• SB-148, Grade CDA 954:TensileStrength::75,000 psi I Yield Strength: 20,000 psi 4., ASME Section II, SB-271, Specification for Aluminum Bronze Centrifugal Castings (Reference 22): MinimuOm Material Properties (i.e., as fabricated without dealloying):

SB-271, Grade CDA 954:Tensile Strength:75,000 psi /Yield Strength: 20,000 psi Assumptions:

1. The through wall weepage is assumed to be due to dealloying. This assumption, does-not require confirmation. The weepage observed is consistent with dealloying previously observed.

2. When detailed analysis is performed, the conservative assumption is made that the affected valves are 100% dealloyed as defined in Reference 5. This is the limiting case. Therefore, this assumption does not require confirmation.

7.0 Discussion Detailed analysis of the valves is accomplished by accessing the pipe stress calculation of record for the subject valves as shown below:

• Valve 3SWP*V661

• Valve 3SWP*V664

• Valve 3SWP*V665

• Valve 3SWP*V668

ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 5 of 56 Engineering Technical Evaluation Cover Sheet and Body Dominion- S - -ins S*11 Revision 1 adds:

0 Valve 3SWP*V857

• Valve 3SWP*V658 0 Valve 3SWP*V659

• Valve 3SWP*V663

. Valve 3SWP*V674 Pipe, stress levels for deadweight, internal pressure, seismic loads and thermal expansioh./ anchor motion are obtained immediately upstream and downstream of the subject valve.. The appropriate pipe stress calculations (Reference 7, 8, 9, 13, .14, 15, 16 and 20) and associated NUPIPE computer analysis were reviewed to extract the. appropriate stress levels.

The NUPIPE-SW computer program (Reference 17) performs linear elastic analyses of three-dimensional piping systems, subjected to deadweight, thermal loads, support displacements, static forces, time-history forces or acceleration, and seismic response spectra.

Reference 5 documents a failure analysis of similar aluminum bronze valves at Surry power station that have exhibited similar through body weepage. This document was reviewed to determine applicability to the subject Millstone valves. The data is directly applicable for all valves with the exception of 3SWP*V674. The materials are similar with only a difference between the specification used for the Surry valves, ASTM B148 C95400, and the specification for the Millstone valves, ASME B148 C95400. These are identical with only differences.in the certification requirements and the weld repair requirements. the actual material is identical. Reference 5 indicates the Su.rry valve body microstructure is that of as cast material.

Unlike the Surry as-cast valve, the subject Millstone valves have been temper heat.treated for at least 1.5 hrs at approximately 1 175°F (Reference 21, see Attachment 8). The data from the Surry as-cast valves

• is considered a lower bound for the Millstone tempered. valves due to the changes in the microstructure that the temper heat treatment causes. The dealuminization process is considered to be an electrochemical reaction between the copper-rich alpha phase and the aluminum rich gamma phase. The gamma phase is less noble than the alphaphase. The purpose of the tempering heat treatment is to alter the quantity and distribution on the aluminum rich gamma phase. The as cast microstructure consists of alpha grains surrounded by continuous network of an alpha-gamma mixture. As stated it is the gamma that is the cathode and is attacked. Since the network is continuous, a leak path is created. The temper

' treatment is intended to replace the alpha gamma mixture with martensite. This reduces the amount of the alpha phase which improves the anode cathode ratio. The resulting tempered microstructure is significantly different from the as cast microstr'ucture and would have better. mechanical properties.

Note that valve 3SWP*V674 is a BNL Industries ASME SB-271 Alloy 95400 (centrifugal cast form) unlike the remainder of the valves considered here which are Neles-Jamesbury ASME SB-148 Alloy 95400 (sand cast form). This is acceptable because only the fabrication process is different. The chemical properties and minimum material properties are identical. Valve 3SWP*V674 has undergone a quench and temper heat treatment (Reference 24 Attachment 9). The microstructure that results from the quench and tempered heat treatment is significantly different than the as cast or even. tempered at 1200'F. The material is taken to 1600+F which is above the eutectoid temperature. Quenching from that temperature avoids the formation of the microstructural constituent that is attacked in the other microstructures. Above

ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 6 of 56

.Engineering Technical Evaluation Cover Sheet and Body W oDominioa" 1600+F the alloy is all beta and rapid cooling results in a martensitic transformation. In the resulting microstructure, the beta phase is discontinuous and therefore more resistant to dealloying.- Examination of a valve that had been quenched and tempered after 15 years of service did find dealloying but the depth was significantly less than with the other microstructures' The depth of penetration was approximately 0.170" which is 1/3 to % of the depth for the other microstructures with similar exposures.

The size of the constituents in microstructure of the quenched and tempered material is much smaller than with the other microstructures which results in better mechanical properties. The original yield strength of the quenched and tempered material is 15 ksi higher than the as cast material and the dealloyed material would retain much of this higher strength.

The allowable stress for the valve aluminum bronze material is derived based on Reference 5 (limiting tensile stress for 100% dealloyed condition) and ASME Section III, Article 111-3000 (Reference 10). The dealloyed Aluminum bronze test data developed in Reference 5 (Ultimate Strength Su vs. percent dealloy) is plotted as shown in Figure 1 (Attachment 3). The plotted data only includes valid test specimens with break locations within gage marks. Specimens with break locations on or outside gage mark locations or specimens.that failed in the grip are excluded. Although only one "100%" dealloyed specimen was tested, plotting of the other dealloyed specimens tends to support that the selected lower bound "100% dealloyed" Su value is reasonable.

For 100% dealloyed SB-148 95400, the lower bound ultimate tensile strength is Su = Sy = 10400 psi (Reference 5). Therefore, per ASME Section IIllArticle 111-3000, the appropriate allowable would be 25%.,

of Su or 2600 psi. Sc = Sh = 2600 psi (See Attachment 4). A casting quality factor is not applied to this allowable as the tested specimens are considered to be representative of the 100% dealloyed condition.

The materials group has reviewed the available OE concerning aluminum bronze dealloying in sea water (See Attachment 7). It should be noted Attachment 7 identifies the potential for additional degradation should Long Island Sound become heavily polluted with sewage. However it is not credible for Long Island Sound to become heavily polluted with sewage between now and when a Code repair can be implemented (no later than approximately May 2013). No additional degradation mechanisms have been identified that would further reduce the above lower bound material strength.

The valve body is idealized as a straight pipe.

Valve stresses are acceptable if the ASME Section III, Equation 8 allowable limit is met and if ASME Section III, Equation 9 Upset and Equation 9 Faulted meet the Equation 9 Faulted allowable limit (i.e.,

operability is met if'Equation 9 Upset meets the Equation 9 Faulted limit).

Full qualification requires that the calculated Equation 9 Upset stress meets the Equation 9 Upset allowable. Since this allowable limit is not met for valve 3SWP*V664, this valve is not fully qualified.

However, valve 3SWP*V664 Equation 9 Upset meets the faulted allowable (Reference 19).

Full qualification also requires meeting the. material property requirements of ASME Section-Il, SB-148 /

SB-271 (see the Design Inputs section of this ETE for specific values). Once thevalves dealloy beyond the minimum wall thickness required by ANSI B16.34, the minimum wall properties will no longer meet the Code required mechanical properties and the valves would not be fully qualified. The assumptions of this ETE dictate that.the valves are not fully qualified.

ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 7 of 56 Engineering Technical Evaluation Cover Sheet and Body Dominion" ___

• A potential concern is impact load brittle fracture resulting from loss of ductility associated with dealloying.

• " A review of Reference 5 shows essentially no difference between yield and ultimate strength. This indicates minimal dealloyed material ductility. ASME Code Equation 9 considers impact loads such as seismic, water hammer, relief valve discharge, etc. Referring to Table 2, the maximum Equation 9 faulted stress to allowable stress ratio is 0.65. This provides a large margin for protection from impact loading which could initiate brittle fracture.

Table 1 (Attachment 5) provides a summary of the stresses selected from the pipe stress analysis calculations (

References:

7, 8, 9, 13, 14, 15,16 and 20). Table 2 (Attachment 5) provides a summary of the valve calculated stresses demonstrating that the valves meet the faulted code equation limits and that

• the valves are operable.

Note: Through wall weepage due to dealloying is a Code non compliance:. However structural integrity

.(design function) can be demonstrated in spite of through wall weepage. Relief from the Code will be

• needed for continued system operation. Historic precedence indicates that typically a 30 day cycle (Reference 18) from leak identification to code relief submittal is acceptable. In addition to the stress analysis results documented above, a hydrostatic pressure test of dealloyed valves 3SWP*V870 and 3SWP*V873 was performed (Reference 12). The system design pressure is 100 psig. The valve pressure rating is 230 psig at 100 'F. The valves were pressurized to approximately 100 psig, then 150 psig (1.5 x system design pressure, then 230 psig, finally 345 psig (1.5 x valve pressure rating) with 10 minutes minimum hold time between pressures. The ASME Code requires initial hydrostatic pressure to be 125% of the design pressure. ANSI B16.34 Section 7.1 requires that each shell test at a gage pressure no less than 1.5 times the 100°F rating. *Therefore the dealloyed valves meet the original construction Code pressure test requirements (ie: these degraded valves in their current condition meet the requirements placed upon a new valve).

On valve 3SWP*870 through body weepage was detected at one location (leak through wall), the structural integrity was maintained. It is noted that this weepage occurred at a suspected location of 100%

• dealloying.. The leakage rate did not increase while the pressure was maintained at approximately 345 psig. On valve 3SWP*V873 no weepage was observed and the structural integrity was maintained. The.

results of this hydro test, including pictures of valve 3SWP*870 weepageare included in Attachment 6.

The hydrostatic pressure test result provides additional confirmation a dealloyed valve retains significant structural load carrying capacity.

Based in part on review of the valve drawings (References 4 and 23) the hydrostatic pressure test of the Neles-Jamesbury valves is also considered to be representative for the BNL valve as both valves comply with Code Case N-1 33'and both valves have similar mass per inch. The Neles-Jamesbury valves are 8 inch long and weigh 50 lbs while the BNL valve is 13.5 inch long and weighs 90 lbs.

Structural Integrity Assessment Summary The structural integrity of the subject valves has been demonstrated to be maintained for deadload, pressure, operational basis earthquake, safe shutdown earthquake and thermal expansion / anchor motion. This is consistent with previous experience.. At Millstone Unit 3, in small bore piping systems (e~g., 3 inch nominal diameter and less), the aluminum bronze valves are typically installed in copper nickel piping systems (e.g., SB-466, No. 706 or SB-467, No. 706). The piping material allowable for

ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 8 of 56 EngineeringTechnical Evaluation Cover Sheet and Body

&WOF Dominion-____________

copper nickel is about half of the allowable for a typical carbon steel piping system (e.g., the allowable for SB-466, No. 706 is 8700 psi while the allowable for carbon steel (SA 106,Grade B is 15,000 psi), thus the copper nickel piping systems are better supported and the system stress levels are lower than for a comparable carbon steel piping system.

8.0 Conclusions Conclusions Adequate assurance has been provided to support the operability assessment of the subject MPS3 aluminum bronze valves. Detailed stress analysis has demonstrated that structural integrity is maintained. Due to the installation of the valves in relatively weak copper nickel piping systems, stresses tend to be lower than for comparable carbon steel piping systems. Since stresses are generally lower in copper-nickel piping systems, the reduced structural capability of the assumed 100% dealloyed aluminum bronze valves can more easily be accommodated in copper-nickel piping system installations.

The brittle fracture concern has been addressed. ASME Code Equation 9 considers impact loads such as seismic, water-hammer, relief valve discharge, etc. Referring to Table 2, the maximum Equation 9 faulted stress to allowable stress ratio is 0.65. This provides a large margin for protection from impact loading which could initiate brittle fracture.

In addition, hydrostatic pressure testing of two similar Neles-Jamesbury 3 inch weeping / degraded ball valves at a pressure that is 150% of the valves pressure rating (i.e., 345% of the system design pressure) demonstrate significant structural capability of the degraded valve. Based on the hydrostatic testing performed on similar valves (same manufacture, type, size, pressure rating, in service conditions and service time) these dealloyed valves meet the original construction Code pressure test requirements (i.e.:

these degraded valves in their current condition meet the testing requirements placed upon a new valve.)

Therefore, based on the detailed pipe stress analysis, the conservative characterization of the dealloyed material strength, the installation in copper nickel piping systems and the successful hydrostatic pressure test, reasonable assurance is provided for continued operability of the subject dealloyed susceptible aluminum bronze valves at MPS3.

It is concluded the subject valves will continue to perform their design function.

Note: Through wall weepage due to dealloying is a Code non compliance. However structural integrity is demonstrated in spite of through wall weepage. Relief from the Code will be needed for continued system operation. Historic precedence indicates that typically a 30 day cycle (Reference 18) from leak identification to code relief submittal is acceptable.

10.0 Required Actions

.None.

ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 9 of 56 Engineering Technical Evaluation Cover Sheet and Body WrDominion-

..- _ *., . S, 12.0 References

1. Condition Reports - Source Documents 1.1. CR506519 - Leakage and corrosion identified on 3SWP*V661 1.2: CR506524 - Corrosion build up identified on service water valves 1.3. CR507564 - Evidence of leakage on 3SWP*V857, V658,V659 and V663.

1.4. CR507567 - Evidence of leakage on 3SWP*V674 and V656

-*2. Piping and Instrumentation Drawing 25212-26933-00002 (EM-133B), Piping And Instrumentation Diagram Service Water, Revision 75 "

3. Valve Drawing 25212-29973-00001, Revision 2, 1-1./2" 6150(C) Flat Face Ball Valve w/ Locking Device

4. Valve Drawing 25212-29974-00001, Revision 3, 3". 9150(A) Flat Face Ball Valve w/ Locking Device

5. Virginia Power Report NESML-Q-104, Examination of Dealloyed Aluminum Bronze

6. Valve Drawing 25212-29974-00002, Revision 3, 3" 9150(A) Flat Face Ball Valve w/ Locking

• Device

7. Pipe Stress Analysis Calculation: NP-X1917, Revision 003, CCN 05, Pipe Stress Analysis Service Water Lines Auxiliary Building.

8. Pipe StressAnalysis Calculation: NP-X1 920, Revision 003, CCN 08, Pipe Stress Analysis Service Water Lines Auxiliary Building

9. Pipe Stress Analysis Calculation: NP-X1914, Revision 004, CCN 12, Pipe Stress Analysis Service Water Piping.ESF Building

10. American Society of Mechanical Engineers (ASME), Section I1l, 2004 Edition, Article 111-3000 (See Attachment 4)

11. ASME Section II,.Material Specifications SB-148, Specification for Aluminum Bronze Sand Castings

12. Related Condition Report CR 506083 - Materials testing of AL-Bronze Alloy 95400 components

13. Pipe Stress Analysis Calculation: NP-X1918, Revision 003, CCN.06, Pipe StressAnalysis Service Water Lines Auxiliary Building

14. Pipe Stress Analysis Calculation:NP-970-XD, Revision 04, CCN 02, Small Bore Piping Stress Analysis Service Water Piping Auxiliary Building

15. Pipe Stress Analysis Calculation: NP-955-XD, Revision 07, CCN 09, Small Bore Piping Stress Analysis Service Water Piping Auxiliary Building

ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 10 of 56 Engineering Technical Evaluation Cover Sheet and Body Dominion- ________________

16. Pipe Stress Analysis Calculation: NP-X1919, Revision 003, CCN 06, Pipe Stress Analysis Service Water Lines Auxiliary Building

17. NUPIPE SW, Piping Analysis Program, Program Description and User's Manual.

18. Functional Administrative Procedure, MP-24-ENG-FAP947, Revision 001-05, Non-Code Repairs in Safety Class3 Piping, Step 2.5.4

19. NRC Regulatory Issue Summary 2005-20 ,Rev. 1, Revision to NRC Inspection Manual Part 9900 Technical Guidance, "Operability Determinations & Functionality Assessments for Resolution of Degraded

-or Nonconforming Conditions Adverse to Quality or Safety" dated April 16; 2008:.

20. Pipe Stress Analysis Calculation: NP-969-XD" Rev 5 CCN 09, Small Bore Piping Stress Analysis Service Water Piping Auxiliary Building ISO's 12179-CP-319735, 319736, 319738

21. Material Receipt Inspection Report #394-222 (Film Roll 50683 frame 411) Select pages included in Attachment 8.

22. ASME.Section II, Material Specifications SB-271, Specification for Aluminum Bronze Centrifugal Castings

23. Valve Drawing 25212-29975-00008, Revision 0 (Vendor # HBV-F2-30-0024), 3" Full Port Ball Valve with ANSI Class 150 Flanged End Caps, with Padlocking (attached to IEE 10000017558)

24. AWO 53M30412156 "Replace valve 3WSP*V674" 13.0 Attachments Attachments

1. Document Impact Summary

2. 10CFR50.59/72.48 Applicability Review Forms.

3. Figure 1 Dealloyed Al Bronze

4. ASME Section III, Article 111-3000 Basis for Establishing Allowable Stress Values

5. Table 1 - Table of Stress Levels Reported at Piping Adjacent to the Dealloyed Valves, Table 2 -

Dealloyed Valve Stress Levels

6. Hydrostatic Pressure Test of Valves 3SWP*V870 and 3SWP*V873

7. , Materials Group Input

8. Material Receipt Inspection Report - Heat Treatment select pages

9. AWO 53M30412156 "Replace valve 3WSP*V674" selected pages including Certification Test Report and NPV-1 Certificate

Attachment#1. . ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 11 of 56 Documents Required To Be Updated List (DRUL)

DNSA-N10 ATAHMN 2 Pge1 f.

STATION - UNIT ETE Document Number

-1 KPS 0[ MPS 0 NAPS 03 SPS 0 CO 0 1 0 2 E0 3 0 ISFSI ETE-CME-2013-1005 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 #2 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 12 of 56 50.59 / 72.48 Applicability Review ominion-D-p CMA-0 tahmn aeIo Applicable Station Applicable Unit(s) ISFSI Parent Document/Revision F North Anna Power Station F Unit 1 F Unit 2 r- ISFSI ETE-CME-2013-1005 Rev. 1 Surry Power Station r7 Unit 1 F Unit 2 F ISFSI Millstone Power Station fr Unit 1 r Unit 2 I Unit 3 F ISFSI r Kewaunee Power Station F Unit 1 I ISFSI Part I. Brief Description of Activity Being Reviewed (See Attachment 2, Part I)

Structural integrity evaluation for MPS3 dealloyed aluminum bronze valves 3SWP*V661, 3SWP*V664, 3SWP*V665, and 3SWP*V668.

Part II. Activity Previously Reviewed (See Attachment 2, Part II)

Is this activity futL. bounded by one or more of the following?

1. fEul* bounded by a F- YES FT NO F Attached (optional) - If YES, identify bounding source.document completed 50.59/72.48 Screen or Evaluation?

2. fully bounded by a station F. YES r- NO F Attached o(ptional) If YES, identify bounding source document activity that has already received NRC approval?

PART II. CONCLUSION

- Both of the above review questions are answered NO, continue the Applicability Review r7 One of the above review questions is answered YES, a 50.59/72.48 Screen is NOT1 required; complete Parts V, VI, VII Part III. Controlled by Other Regulatory Change Control Process (See Attachment 2, Part III)

Check if any of the following documents are identified as part of the proposed activity.

NOTE: For example, when a design change is the proposed activity, consequential actions may include changes to one of these documents which have a different change control process and are NOT to be included in this 10 CFR 50.59/72.48 review.

1 Technical Specifications or Operating License F

2 Emergency Plan F 3 Security Plan F

4 Fire Protection Program and is NOT associated with ISFSI 5 Quality Assurance Program Description 6 Inservice Test Plan - IST F

7 Inservice Inspection Plan - ISI 8 ECCS Analysis F

9 Environmental Protection Plan F

F 10 Radiation Protection Program 11 Radiological Environmental Monitoring and Offsite Dose Calculations Manual F

12 Reactor Vessel Surveillance Withdrawal Schedule PART 1MI.CONCLUSION

[- If there are no documents selected, continue the Applicability Review.

F One or more of the documents listed above are selected, AM the proposed activity is limited to changing those documents, a 50.59/72.48 Screen is NOT required; complete Parts V, VI, VII.

F One or more of the documents are selected, however, some portion of the activity involves facility or procedure changes; continue the Applicability Review for that portion.

Part IV.1 General Pre-Screen for Maintenance - Not Applicable to ISFSI (See Attachment 2, Part IV.1)

1. Is this a maintenance activity limited to restoring an SSC to the normal as designed condition AND F-. YES NO does NOT permanently alter the design, performance requirements, opera tion or control of SSCs?

2. Is the activity limited to installing or testing approved facility changes?  : YES rv- NO Part IV.1 CONCLUSION r Both of the above review questions are answered NO, all or some portion of the activity extends beyond maintenance; continue the Applicability Review for non-maintenance activities.

r7 One of the above review questions is answered YES, the activity is subject to review per the Maintenance Rule; a 10 CFR 50.59/72.48 Screen is NOT required; complete Parts V, VI, VII.

Attachment # ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM

• Page 13 of 56 50.59 / 72.48 Applicability Review.

Dominion")C-A40-Atcmn ae2o Part IV.2. General Pre-Screen (See Attachment 2, Part IV.2)

Does this activity accomplish any of the following?

1 Does this activity involve any changes to the ISFSI written evaluations required by 10CFR72.212? F. YES r NO 2 Does this activity involve fire protection activities associated with the ISFSI? r7" YES F NO 3 Does this activity involve maintenance activities on the ISFSI? r- YES F NO 4 Does this activity alter (temporarily or permanently) the design of an SSC through a modification or F YES F NO addition to, or removal from the facility as described in the SAR?

5 Does this activity alter (temporarily or permanently) the function, ability to function, or method of rF YES F NO performing a function of an SSC as described in the SAR?

6 Does this activity modify how SSCs are operated or controlled as described, outlined, or summarized F YES F NO in the SAR?

7 Does this activity change a numeric value of a design or performance requirement of a SAR r- YES F NO described SSC to a value that has NOT been previously reviewed in accordance with 10CFR50.59/72.48?

8. Does this activity perform a test or experiment that is NOT described in the SAR? F 'YES r NO 9 Does this activity involve a change to a method of evaluation used for evaluating behavior or F YES I NO response of the facility or an SSC described in the SAR?

10 Does this activity involve a temporary modification? ,. - YES F NO PART IV.2 CONCLUSION F All Pre-Screen questions are answered NO, a 50.59/72.48 Screen is NOT required; complete Parts V, VI, VII

- One or more Pre-Screen questions are answered YES, perform a 50.59/72.48 Screen per Attachment 3 and complete Parts V, VI, VII.

Part V. Safety Analysis Report Interface (See Attachment 2, Part V)

Does this activity require revising the Safety Analysis Report? If YES, initiate a Change Request in accordance with CM-AA-SAR-101 and include the Change Request number F_ YES F_ NO If YES, additional review required by 50.59/72.48 Screen Preparer/Reviewer if Applicability Review F Y Preparer and Co-signer (when required) are NOT 59.59/72.48 Screen qualified.

Part VI. Comments (use supplemental pages as needed)

(Examples: Identify any 50.59/72.48 Screen or Evaluation, or NRC approved activity.that contributes to this review, identify parts of the activity that are bounded or not bounded by a previously completed review or that are NOT part of another change process, identify the source document supporting a numeric value previously reviewed per 10 CFR 50.59/72.48)

N/A Part VIZ. Signature Preparer Name (Print) Preparer Siqnature Date Digitally Signed by

• 02/28/2013 10:25:53 AM Form No. 729534 (Jun 2010)

Attachment #3 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 14 of 56 Figure 1 - Dealloyed Al Bronze 80

~70

.50 a4 0 S . Test Data Su, ksi Lower Bound Su, ksi

~30 Cu -. *.; - m Best Estimate Su, ksi E 20

~10 0

0 20 40 60 80 100

% Dealloyed per Surry Rpt NESML-Q-104

Attachment #4 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 15 of 56 ARTICLE 111-3000 BASIS FOR ESTABLISHING ALLOWABLE STRESS VALUES 111-3100 BASIS FOR ESTABLISHING (1) one-fourth of the specified minimum tensile STRESS VALUES FOR MATERIAU S strength at room temperature; FOR CLASS 2 AND CLASS. 3 (2) one-fourth of the tensile strength at temper-COMPONENTS ature; (3) two-thirds of the specified minimum yield 111-3110 GENERAL BASIS strength at room temperature; In the determination of allowable stress values for (4) 90% of the yield strength at temperature but pressure parts the Committee is guided by successfu not to exceed two-thirds of the specified minimum yield experience in service, insofar as evidence of satisfactor' y strength at room temperature.

performance is available. Such evidence is considerecI (c) For bolting materials, the basis for setting equivalent to test data where operating conditions ar e stresses is the same as for all other materials with the known with reasonable certainty. In the evaluation of added requirement that the stresses for heat treated new materials, it is necessary to be guided to a certaihI materials at temperatures below the creep range will extent by the comparison of test information with sim _ .not exceed the lower of 20% of the room temperature ilar data on successful applications of similar materials . specified minimum tensile strength or 25% of the room temperature specified minimum yield strength.

(d) Stress values for high temperatures are based, whenever possible, on representative properties of the 111-3200 FERROUS MATERIALS materials under laboratory test conditions. The stress 111-3210 PROCEDURE FOR ESTABLISHING " values are based on basic properties of the materials STRESS and no consideration is given to corrosive environment, to abnormal temperature and stress conditions, or to

.The .mechanical properties considered and facton other design considerations.

applied to provide the maximum allowable stresses an given in (a) through (d) below.

(a) At any temperature listed below the creep range the maximum allowable stress value for ferritic- steel!

is the lowest of the following: 111-3300 NONFERROUS MATERIALS (1) one-fourth of the specified minimum tensil(e .111-3310 MECHANICAL PROPERTIES strength at room temperature; CONSIDERED (2) one-fourth of the tensile strength at temper.

ature; The mechanical properties considered and factors (3) two-thirds of the specified minimum yielc I applied to provide the maximum allowable stresses are strength at room temperature; given in (a) and (b) below.

(4) two-thirds of the yield strength at tempera-- (a) At any temperature listed below the creep range,.

ture. the maximum allowable stress value for nonferrous (b) The maximum allowable stress value for austen-- materials, except for bolting, is the lowest of the fol-itic steels is the lowest of the following: .. lowing:

269

Attachment #4 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 16 of 56 M-3310 1989 SECTION III, DIVISION I - APPENDICES 111-3310 (1) one-fourth of the specified minimum tensile strength at room temperature;,

(2) one-fourth of the tensile strength at temper-ature;

, (3) two-thirds of the specified minimum yield strength at room temperature; (4) two-thirds of the yield strength at tempera-ture; (5) 90% of the yield strength at temperature but not to exceed two-thirds of the yield strength at room temperature for some alloys.

W(bFor nonferrous bolting materials, the basis for setting stresses is the same as for all other nonferrous materials with the added requirement that the stresses for materials whose properties at temperatures below the creep range are enhanced by heat treatment or cold working shall not exceed the lower of 20% of the room temperature specified minimum tensile strength or 25% of the room temperature specified minimum yield strength.

. 270

Attachment #5 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 17 of 56 TABLE 1 Millstone Unit 3 Dealloyed Aluminum Bronze Service Water System Valves Table of Stress Levels Reported at Piping Adjacent to the Dealloyed Valves Line # ASME ASME ASME ASME P&ID EM, 3SWP- Stress Computer ASME Eq.8 Eq.8 Eq.9U o, Eq.9U Eq.9F o, Eq.9F Eq.10 ,o Eq.10 Eq.11 a, Eq.11 3

Valve ID# 133x, Loc Size, in xxx- Calc # Point # Run # a, psi Allow, psi psi Allow, psi psi Allow, psi psi Allow, psi psi Allow, psi SIF Do, in T, in Po, in Z, in 3sWP*v658 B. C-09 3 70 X1917 252-274 11/06/19e610:55 1085 5149 5630 2049 3134 2.1 3.500 0.219 100 1.7439 3SWPeV659 B. G-10 3 149 X1920 332-340 Rt88420N J9936 1105 1674 1650 7014 8119 2.1 3.500 0.219 100 1.7439 3SWPeV661 ., G-02 - 3 171 X1918 322-327 Rt18418N J7948 1589 2539 2722 1020 2544 2.1 3.500 0.219 100 1.7439 3SWPeV663 e, G-09 1.5 104 969XD 195-203 R1884NR5 J0872 621 939 942 4471 5092 2.1 1.900 0.15 100 0.3348 3SWP*V664 B, D-03 1.5 105 970XD 19-27 R1884NR4J2115 3236 6041 6219 645 3880 2.1 1.900 0.15 100 0.3348 3SWP'V665 B.G-04 1.5 "106 955XD 18-2e R1884NR7J1198 1687 2326 2690 2668 3939 2.1 1.900 0.15 t0 0.3348 3SWPweV66 8B,0C-03 3 153 X1t9t 705-79 11/06/19969:01 - 1155 1 2986 3010 3955 5110 2.t 3.500 0.219 tOO t.7439 3SWP*V674 3, K-10 3 67 X1914 601-609 R188414A J1789 757 1352 1594 1 438

• 1195 2.1t 3.5000 0.219 1oo 1.7439 3SWP*V057 B, E-11 3 86 - X1917 6310-634 R188417DJ4087 775 1789 2277 462 1238 2.1 3.500 0.219 100 1.7439 Notes The above table provides the largest pipe stress level for the identified ASM E equation immediately upstream or downstream of the subject valve.

Specification 568 indicates that the valves were designed and constructed in accordance with ASME Section III,1974 Edition through the Summer of 1976 addenda. Code Case N-133-3 describes the requirements for aluminum bronze valves. This code case refers to ANSI 816.34. Per Table 3 ofthe 1977 Edition of 816.34, for 150 lb Class, the minimum wall for a 1.5 inch valve is 0.19 inches and for 3 inch valves is 0.22 inches. These minimum wall thicknesses compare favorably with the nominal wall thicknesses used for the adjacent pipe elements (i.e., for 1.5" pipe the nominal wall is 0.150 inches and the valve minimum wall thickness is 0.19 inches and for the 3 inch pipe the nominal wall thickness is 0.219 inches in the table and the valve minimum wall thickness is 0.22 inches. ). Thus a ratio ofthe stresses is appropriate / conservative.

The vendor valve reportis) for the subject yalves is (are) not available. The valve body will be idealized to be a straight pipe. The flanged ends of the valves are considered to be qualified by the valve body evaluation.

For the purposes of this evaluation, the entire valve body wall thickness is assumed to be dealloyed (for determining the allowable(s)). The evaluation found below is based on the unintensified stress (SIF=1.0).

TABLE 2 Table of Dealloyed Valve Stress Levels Line # AWL AsM- AWL AMi-P&ID EM- 3SWP- Stress Computer ASME Eq.8 Eq.8 Eq.9U a, Eq.9U Eq.9F a, Eq.9F Eq.1 o,.' Eq.10 Eq.11 a, Eq.11 IShI Valve ID# 133x, Lot Size, in xxx- Calc # Point # Run # a. psi Allow: psi psi Allow, psi psi Allow, psi psi Allow, psi psi Allow, psi pin 3swP-vs658 , C-09 3 70 X1917 252-274 35375.45497 834.8 2600.0 3415.1 3120.0 3720.5 6240.0 975.7 3900.0 1810.5 6500.0 3swP'v659 B, G-10 3 149 X1920 332-340 R188420N J9936 847.5 2600.0 1208.7 3120.0 1193.5 6240.0 3340.0 3900.0 4187.5 6500.0 3SWP"V661 B, G-02 3 171 X1918 322-327 R188418N J7948 1154.8 2600.0 1757.9 3120.0 1874.1 6240.0 . 485.7 3900.0 1640.5 6500.0 3SWP'V663 B, G-09 1.5 104 969XD 195-203 R1884NR5 J0872 509.9 2600.0 711.8 3120.0 713.7 6240.0 2129.0 3900.0 2638.9 6500.0 3SWPeV6e4 0.D-03 1.5 1l0 9700X 19-27 R1884NR4 J2110 2170.2 2600.0 3951.2 3120.0 4064.2 6240.0 307.1 3900.0* 2477.4 6500.0 3SWP*V665 B, G-04 1.5 106 955XD 18-26 R1884NR7 J1I18 1186.7 2600.0 1592.4 3120.0 1823.5 6240.0 1270.5 3900.0 2457.2 6500.0 3SWP*V668 B, C-03 3 153 X1919 706-709 35375.37571 879.2 2600.0 2041.7 3120.0 2057.0 6240.0 1883.3 3900.0 2762.5 6500.0 3SWP'V674 B, K-10 3 67 R1914 601-609 R188414A J1789 626.5 2600.0 1004.3 3120.0 1157.9 6240.0 208.6 3900.0 835.1 6500.0 3SWP*V857 B6.-ti 3 66 01917 6310-634 R1684170J4087 637.9 2600.0 1281.7 3120.0 1591.6 6240.0 220.0 3900.0 857.9 6500.0 Note:

For 100% dealloyed S18-148 95400, per Virginia Power Report NESML-Q-104, Su = Sy = 10400 psi. Therefore, per ASME Section III, Article 111-3000, the appropriate allowable would be 25% of Su or 2600 psi. Sc = Sh = 2600 psi. A bolded underlined allowable indicates that the allowable was not met. The equation 9 upset equation for one valves was not met. However, structural integrity is maintained since the faulted allowable limit is met.

Attachment #6 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 18 of 56 Attachment 2 Elevated Pressure Test (Sheet 1 of 2)

1. DATA System: S IL) ASME Code Class: (1, 2, 3, , WO#:- /A (Circle One)

Line

Description:

'3 StOP V'VS 70 and dro Rtf, -USMKOI Hydro Factor (From Attachment 7) x Design Pressure = Elevated Test Pressure (ETP)

Limiting Components:

Conditions Affecting Test:

Buried LI Insulated El Un-insulated El. Shop Hydro Method:

Hydrostatic RTest W] Pneumatic Test L-Static Head Correction:

Yes LI (Attachment 3 attached) No Test Pressure/Compensated Test Pressure from Attachment 3: _ " _ _ _

Gauge Elevation: ________ Gauge QA__L__3?95 Cal. Due 3 Maximum Pressure: __ Hold Time: "__ _

Minimum Pressure: __ Hold Time (from Attachment 7): A1/A

),se Ar&Aed i7Rt, Level of Use EN 31090 Reference STOP THINK ACT: REVIEW Rev. 006-00 31 of 42

Attachment #6 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 19 of 56 2nd hydro of 3SWP*V870 and SWP*V873 with pressure maintained for 10 min.

Subject:

Proposed Hydrotest Pressures for Dealloyed Aluminum Bronze Valves Please use the following hydrotest pressures for the subject degraded valves:

1: 100 psig

.2: 150 psig

3. 230 psig

4. 345 psig The basis for these hydrotest'pressures is provided on the attached sheets (Code Case N-133 and MEL for service water line 3-SWP-003-008-3).

Safety precautions shoUld be made as this testing has the potential to result in catastrophic rupture of the subject test valve(s).

If you have any questions or require any clarification regarding this email, please call me at extension X6130.

Regards, Ray, X6130 Per discussion withha 10 Min. hold time for each pressure has been added to the criteria listed above. If no leakage is detected at 345 PSIG after 10 Min. maintain pressure and hold as determined byengineering.

Leakage shall be characterized (DPM and number of leaks on the valve) at each pressure.

Attachment #6 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 20 of 56 Attachment 2 Elevated Pressure Test (Sheet 2 of 2)

Relief Valve (if required):

Setting/Com pnsated Setting: Maximum Setpoint: -I (From Attachment 3)

Minimum Setpoint: A Elevation: ý141 Prepared By:- Date: 311/13 T! I Hydro to be (witnessed/reviewed) by ANTI:

Yes El NoM

2. PREREQUISITES AND INITIAL CONDITIONS

• Elevated Pressure test boundary verified as marked up P&ID or similar information supplied in WO package.

o- Test gauge meets calibration requirements required for testing.

-Test gauge is installed.within the test boundary at elevation identified above or test pressure has been compensated.

• If required, a relief valve is installed within test.boundary.

All equipment, blind flanges, gags, pancakes, etc. are installed within test boundary and identified on Attachment 1.

• Prerequisites and Precautions to this procedure have been reviewed by all test personnel.

Signature:. Date:_______

3. TEST ACCEPTANCE Test Acceptable: Yes [] NoXh]

Date:________

Signature: (Level) .2L VT2 Level II Certified R Yes El No [1 N/A (non-ASME Only)

ANII Signature: / Date:

Level of Use EN 31090 Reference STOP1: THINK ACT.:. REVIEW Rev. 006-00 32 of 42

Attachment #6 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 21 of 56 3SWP*V870 Shop Hydro Results 03/01/2013 100 PSI 1321 - 1331 No leakage detected. Pressure 100 PSI.

150 PSI 1334- 1344 No leakage detected. Pressure 150 PSI.

230 PSI 1346 - 1356 No leakage detected. Pressure f PSI. 13 0 I4C/3 350 PSI 1429 - 1439. Leakage detected in one area only approximately 1/64" round droplet. 35,0 IflC8

Attachment #6 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 22 of 56 Attachment 2 Elevated Pressure Test (Sheet 1 of 2)

1. DATA S(A ASME Code Class: (1,2, 3,(D) WO#: AV)

System:

(Circle One)

LineDescription: VoJVC 3 5f*.A9 73 aM Hydho Hydro Factor (From Attachment 7) x Design Pressure Elevated Test Pressure (ETP)

Limiting Components: t'0 11f, Conditions Affecting Test:

Buried EI Insulated DI Un-insulated [] Shop Hydro 4 Method:.

Hydrostatic Test Vo Pneumatic Test El Static Head Correction:

Yes El (Attachment 3 attached) No V Test Pressure/Compensated Test Pressure from Attachment 3: _ _____

Gauge Elevation: 1__1__ Gauge QAPITMP0395 Cal. Due,,.

Maximum Pressure: Hold Time:

Minimum Pressure: __ Hold Time (from Attachment 7):

A Altt*o*Ph Ae EI-,n

.- l.,i" Levcl of Use EN 31090 Reference STOP THINK ACT REVIEW Rev. 006-00 31 of 42

Attachment #6 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 23 of 56 2nd hydro of 3SWP*V870 and SWP*V873 with pressure maintained for 10 min.

Subject:

Proposed Hydrotest Pressures for Dealloyed Aluminum Bronze Valves Harvey, Please use the following hydrotest pressures for the subject degraded valves:

1: 100 psig 2: 150 psig

3. 230 psig

4. 345 psig The basis for these hydrotest pressures is provided on the attached sheets (Code Case N-133 and MEL for service water line 3-SWP-003-008-3).

Safety precautions should be made as this testing has the potential to result in catastrophic rupture of the subject test valve(s).

If you have any questions or require any clarification regarding this email, please call me at extension X6130.

Regards, Per discussion with in a 10 Min. hold time for each pressure has been added to the criteria listed above. If no leakage is detected at 345 PSIG after 10 Min. maintain pressure and hold as determined by engineering. .

Leakage shall be characterized (DOM and number of leaks on the valve) at each pressure.

Attachment #6 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 24 of 56 Attachment 2 Elevated Pressure Test (Sheet 2 of 2)

Relief Valve (if required):

Setting/Compensated Setting: Maximum Setpoint: -/

, (From Attachment 3)

Minimum Setpoint:

Elevation:

Prepared By:. Date: 3/./13 Hydro to be (witnessed/reviewed) by ANII:

Yes 0I NoP

2. PREREQUISITES AND INITIAL CONDITIONS

• Elevated Pressure test boundary verified as marked up P&ID or similar information supplied in WO package.

- Test gauge meets calibration requirements required for testing.

0 Test gauge is installed within the test boundary at elevation identified above or test pressure has been compensated.

- If required, a relief valve is installed within test boundary.

All equipment, blind flanges, gags, pancakes, etc. are installed within test boundary and identified on Attachment L.

• • Prerequisites and Precautions to this procedure have been reviewed by all test personnel.

Signature:- Date:

3. TEST ACCEPTANCE Test Acceptable: Yes [ No [D Signature: _ Date: 311!1, VT2 Level II Certified  ;] Yes El No El N/A (non-'ASME Only)

ANII Signature: Date: _ _ _

Level of Use Reference EN 31090 STOP THINK ACT REVIEW Rv, .006- 00 32 of42

Attachment #6 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 25 of 56 3SWP*V873 Shop Hydro Results 03/01/2013 100 PSI 1128 - 1138 No leakage detected. Pressure 100 PSI.

150 PSI 1145 - 1155 No leakage detected. Pressure 150 PSI.

1257 1207 No leakage detected. Pressure-4-- PSI.

- a.30 3/C/S 230 PSI 1210 - 1220 No leakage detected. Pressure 350 PSI.

35O PSI

Attachment #7 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 26 of 56 Thomas A Steahr (Generation - 6)

From:

Sent:

To:

Subject:

1. There is no reason to believe that there is anything significantly different about the aluminum bronze used at Surry 25+ years ago as compared to that Millstone purchased almost 20 years ago. The only difference between and ASTM specification and an ASME specification is in the paper work needed.

2. Once the material has completely dealloyed, I.am notaware of any other corrosion mechanism in sea water that would further degrade the material. The environment would have to change for other corrosion processes that attack copper alloys to become active, i.e. ifthe Long Island Sound were to become heavily polluted.with sewage then microbes and sulfur become an issue.

Attachment #8 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 27 of 56 I',

, E S.

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&LOCKING DEIE'

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ND-S51 811 -500B SWP* V658 ND-S51 81 1-50013 3SWP #V659

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ND S51 811-5OOH -3S Pl*V873 K

,,. v6

,The rcords contained; h*m*. ave, and'accuracy. The records are auti

,QualityRepresenltative Date

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Attachment #8 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 28 of 56 FORM NPV-1 N CERTIFICATE HOLDERS DATA REPORT FOR NUCLEAR PUMPS OR VALVES*

Ao Required by the provision, of the ASME Code,Section III, Div. 1 I

I.-. 'Manufacutureid by.t' N3LJ~L-!m Ue 11G.TER MAo9216 .1:'

2. Manufactured for rLA =Q 3.Lociation' of Installat on MILLSTONE W. SM.

PULER ~ ~ RYP~'(RUE16 4 *-'pnmto~ av A. AW:iknlIltSz Otlet size jj n ~0 ro~t if ic' a te t ( ) *ai "( Mj  ; ~ ~ 71 (1) 0150 N-591590A N/A i>ND.

N ND.

(3~ 9110 N-5Sl0O (4i : 10 D-,lh-5rDN/.

(5). 9150 -ND-SS1111-5008 / NU-UblUhl-bUU x~vas ~.

.(6) 915eJ ND-115Xal1-500? NZA ND-S51811-SOO R_9V.3 3 NI/A 1995 (7) 9150 92-815211=9200 K/A ND-151811-iA90 RW. 3 N/A 19 (a) 9150 ND-S51611-s~ogs N D-IS18116-500 WR.8 13 Nlk 99 (9)

5. I

a. aflfl . *nn 0=

6. Design Conditions

.BOWY 145 23PI 220 00

. t~%em eramale 7PEAor Valve Pressure Class 10(j)

7. Cold Work.ng Pressure 230 _si at 1000F.

8. Pressure Retainiz)g Pieces 1 I. I.

Mark No. 1aterial Spec.No. Manufacturer . Rvemarkw ... ::

(a) Castings ,, I-- ,..

(1) RT-B I 8-148 UNS NO.C95400 FEDERAL BRONZE CAhSTwG BODY .. *..

- - *1 . t. - ~ I.

(1) R.-10 _

SB 3149 OiLS NO.C95400 FEDERAL BRN 'CASTTIGI I::.:

4.

BODY CAP . i=- :::.'.-:-:;?

(2) RZT- I SB-148 UNS NO.C95400 FEDERAL BRONZE CASTING BODY (2) RZU-4 SO-148 UNS NO.C95400 FWEDRAL BROM"CAST3IN . BODY CAP . ""

(3) RzT7 .....

....... '.SB-148 S-; UNSNO.C95400 FEDERALL.O T =

,ECASTING .,- BODY 4.

(31 RIO-B SB-149 UNS NO.C95400 FEDERAL BRONZE CASTING BODY CAP

,.. (3) .- RZ __ - ._ . __.

RXV(4 1T4.! I~I. 314 ~ ~ 5N - O.C9S400IFERLROZCATN BODY.

(i:4) RZO 1 ).d 93-149_038 9NO.9i40( .30W-

__ y .

- ,,~..i dibIY74,~YAZ,.ahae au I,

-.----- M sw . AS-m SD4

. (5) RZT-2 SB-14B UNS NO.C95400 FEDERAL BRONZE CASTING BODY m

(5) RZU-6 83-148 OHS NO.C95400 I CASTING(., BODY CAP...........

.i: (6)_

(6) RZ*-5RZT-9 i,,88-148 MI~S NO.C9S400 BODY R)-.6.

(7)i*.:.I':1 5 .,::-:,,:+:.!.18-146 X55 NO.C95400,: BODY CAP I

R8-1.48 OS-All TtfirV A-Ih II 8B-148 .*S 4

rm.. . -

ant ina.... ý:Uaby C".7 13-1;48 UNS NO'.C 7~~

4 T7T.vI 7..i ~.

4 ______________________________________

(1) or For manually eoperated drawn valyes orly.

rovlde4 *Sqpp*_*enta.*.

(I. size. it *x I,. for*mtion norton .n thr .orm of inAtrems lists I throuclh sketch, 4 on t*l' ole ane thj e.is num. . .. he n - .....or

• sh *e ai ,a

Attachment #8 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 29 of 56 FORM NPV-l (Bacik)

Mark No. Material Spec.No. Manufacturer Remarks

-I I

£*. Bolthna,.. ASME.SA ' . , * . .

o5sse8 193 GRADE B6 N OVA MACHINE BODY STUD

'29939 I. 94"GRAIE 6 NOVA MACHINE  :.HEXN.:UT

-8644748. 19"GRAD!E6 -NOVA MACHINE : -...  : UT. I 'I j.

I Mg

,.. -.£~ux.

%C¶A TWOI Wfl. ?JaA& ftn ENRY RMSCR.

, ,' ' .i

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st p'

,. 'ydrosta.ic te'st .eiL .a.Di*, Differential NOuu soou,o, . =ouu '

CERTIFICATE or 006M qamH ". i -;'*HiA. .

We gertify tat tbg;starements wade In h irretndthat this contorms to tMe ruJle5Oa construct on Ja

-eotja%:

Section 111, Div. 1., Edition 191 Addenda e

.I83..

o CodeCjeo ear t P1.r

?J 4-Dt -

Signed NXe9S0WgL= %i CeriplxCato Holuert by -f =_______________

Our .:.AMS

,.! .. , ..,Certiicat6

.*..:..* , . : . - of , . ..Authorization

* . . .. No.

.T. _-8to usa the". N ymbol expires._.27.

CERTIFICATION OF DESIGI Destin iozuatis file at NoRIE UnILTE SERCE CO." .o' P BOX 270o jArTORD. C.

4.

Stress analysis report '(Class 1 only) on file at N/I A. .',

Design specifications certified by (1) TR0IAS., M.*H*SOU PE State .eg. 2ONCITNo.. 240 Stress analysascert iLed _by (

lP*.* State-,t!V0- ,:;.= A* , .:* -- ']3*:. " :*'***

• ,,[ *;6*.!:-**]-.. ***;:* L *'*':d* -:° * ' ""*3

't* '3 1*

- .... ';***!*'::*. " :; *=IL CERTIFICATE OF SHOP INwSPoI.N I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel inspectors and the State or Province of - - ..-

and employed by, PROTECTIO HMUTL- _ of tructetp.valve doaounew.r**seum_,ton'..,.,

ye.

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MJAE I BU.. state. PProv. aNao. I S-'-"a~~'.~

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Attachment #8 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 30 of 56 T~0)589-7078 JI) 589-7575 FEDERAL BRONZE.CASTING INDUSTRIES, INC.

'0 SA:CKUS1ST.

(

A" A ,= "'," " L: ... '"';" '

NEWARK.N.J. 07105 V V ~Heat No. r5~ coroe a0 N Ne~es-jamwshury <0!.,:

AQ.A-,Departimeft ' .:ý e -:ý ý - I 1V ASME--SBl48-ý-954-;198V'1 inozeraai;speczsc~ui

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'i qV-i toi B3atch .4 77ii

. . "" ' " " '*

• 7'* ; =L."=*

futher cad y that the material me0tioned herein Ls fee from

-cury contamination.

olumbiunt & -

itaniumAMESBURY Quality TEO.

Castings,.Temuper Aninealed'1,15O -. 12000 F. for a . .~. .

ev 1,.

U. ~etiv.tht.thm~terial1 nr~hr furnished was mianufactured applic ~3800 '

CERTS OQ '. !CONFORMANCE: ..... .

Federal,.-.. -AsronzqeCasting- -,usu ies.ý Inc. has.,5supplied castings

.i .--. _ -, , , :it .h,ya-- C,,:.' ,. - -" rei ".:-r'ents. i LL;'*'*L

.:  :. "* = *. "* '* .* t "" :" '." " "' *-'"" " " ... v. ...

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ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 31 of 56 Attachment #8 "0)594767V ýFEDERAL BRONZE CASTING INDUSTRIES 1 INC. 3 3 It r20'1) 589.7078 9 BACKUS ST.;

NEWARK. N.J. 07105 Ne e5.JamesbIy,,: M ' .- *!i ' DAi!e__________:_::

• ,,Heat No. 9529 c

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raphic Io 6.0 doe_

We fuaher ceotify thdt them*eatlat mentioned herein Is free from mercury contaifatlon. , 0 ME) BY tlum& r  :

4. ........... .. . ........JAMES1BURY QualitYI

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~~~~~~~...............

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ýiv No welding has been', perforMedo "

Castngs.-. Temper Annealed' -..

MEtr~1 .Wnihe d ftidfadt'f8 3 We er

-uw etify :that th and~guppiedA4n acordn veith h quality... system PrOgr*M7 ý.we and/orrdate of isssued accepted byel a

.appic~able.equirements -of NCA 3800..

. ... :rERa S. *o'* z '.c.. . .M.R CE :o.. g .. " "

Feeral -!-zeCasting InutiesIn. ha supied. casti9%g5 4 "i,1 a 0anqj, rcbseorder requiremens

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SOUG REICHARD QC. Coordinator Q-I

ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 32 of 56 Attachment #8 I'mR 0j D* 15:3 TREAT,~

O'1YIET 85 466 **

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32 ~ 1 0oeAeu Poil office Boxn 33IU

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TREATSDEFUMC

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ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 33 of 56 Attachment #8

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Attachment #8 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 34 of 56 1*

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B.........

. .URY SERIAL

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? l.. -,:*,-:* :Ii*:S:'i:*ii:. ;ii  :: .~.'.i".' 4-:.**:::

• ;i~:*(ii-:i:i:.::.The records o~ntained..heroin have be~en reviewed approved fobr completenless

.:*:..*, .... and accuracy* <,, 1: ..,'"*

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• • X,:.**..*._*.,.***,..*.:i*.***.*.:,..**::. ,Th.e !r~ecords .!';.' *;.}...** are.:*iatetcadaeC

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. ored valid Qaliy Recordas.

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-- I 640 .INCOLN STREET BOX 15004 WORCESTER, MASSACHUSETTS 0161S-0004 U.S.A.

PHONE: (508) 852.0200 TELEX: 92-0448 FAX: (508) 852.8171

Attachment #8 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 35 of 56 "R "'p * '.-.': ':." o.:

" .. . .':"6 : " . -

. . ,,,;,,CERTIFICATE:OF;CONFORMANCE ".  :.. : ' . 5. '" -. . .**J:,wi .{" ' 2...<i.'..:.; . . . i .,'.*:'..

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Northa ONuclear Enorgy'i.ompa0ny, MiVý~1Aa03199 Millstone* uclear Power. Stat on .(063)'-. / U a.. t' ' " ' '. :: , :" . ."" " : -.. ' . - .' :

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R I' 0685......

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fteerc 0otes V:O.o.I2.2f.

-.",n Nee-ams y Inc Orde No Vi manufactureo and inspecte.df in1 on the above reference were certify th~at'the valves being supplied We accorda'ncc' With -all apoflcable requlrementa of Neies.Jamnesbury, Incs Nulmt Uillty. Program Mapsi~

the above 1.refteIre. n.ced Northeast ...

werefound to be In conformance with Rev.22 dated Sep. 93 aind we ls crtfythat thembelow listed itemWs were manufactu'red an.d Insetedhacrac Jamesbury, inc.'s Commercial Quality Program Manual Rev.A-3 dated Apr. 93 and were Dedicated In accordance with Work Instruction B. 1 (Dedication of commercial grade parts) and found to be acceptable.

~~~~~~~~~.........

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REF. 0UTNE AND ASSEMBLY DRAWING (ND.S35151 1-520 REV.8) 0IL.PMTEILSC MFRILPEFIRCATION X ffMPART INAME

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2 INSERT ASME 8S-160 UNS NO. C63000 4 STEM . ASME1SB.1 lNO.NO440041.W

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640 LINCOLN STRIET BOX 15004 WORCESTER. MASSACXUSETTS 0161S-0004 U.S.A.

PHONE: (508) 852-0200 TELEX: 92-0448 FAX: (508) 852-6172

Attachment #8 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 36 of 56 FORM ' NV-m. - CERTIFICATH HOLDERS DATA REPORT, FOR' ,UCLER.PUMPS.ORALVES*

As Required bjr' Itb* ov:.uLonlobf the ASvE Cd ction 1.~~Q §1ufctre 2.,H auxdfo

3. Location oIf installation MILLSTN MULA W. Ownft SeisB~ .,~oJyoe Wegistato -

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JISM&RDEAe 1319 ---

6. Desi .~~k

,I .Iio1 * , "*F Doi - 1*T K Ea r or Valve . . Pressure Class ISO(1)

7. Cold Working- Presaszpe - 0".si atr..00F. , , .

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Attachment #8 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 37 of 56

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1 Section III~c Div. 1, Clo Addend .63 Cd . t IaN.N12 Signed JCK_ R~~ .by ~ 4 & I ' . J L J O urj 3 1 3 C r i i a e o t o ization No.-- ...L J33g..to use t e~ c sY bo I y) on:~ l at' /

Stre sSIL a a y i e o t ( ~ a sI onlM _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

4 Design specifia'aac-no certified by (1). MMM -J. HAVOCAI .;:l PH state ýKP AM'S

• 0 54 CZRTIFICM OF -SHOP MSP=n=

1, the uudarsigwýdj a valid'coamission issued by tbe 7M 'Board o f Boiler And' presou" vago, "Iw" lthe.Statt'ýft 7 of.

and: GUIPAIC I by C

lim VACTORTOUIýý lobikEERnTat SC lh. 14q.4 v 19 SM4r, A ba.

wI-OM-re -MMMM,. 4.,! i:

Attachment #8 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 38 of 56

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Im I mm PENNSYLVANIA STEEL FOUNDRY *& MACHINE COMPANY _

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. 31-95

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640 L9NCOL.N STREET BOX 15004 WORCESTER. MASSACHUSETTS 01615-0001 U.S.A.

PHONE:.(508) 8650200 TELEX: 92.0448 FAX: (508) 852.8172

Attachment #8 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 40 of 56

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33 P s.JjýAMESBURY INC.O.DF-202 FOR.

t tby IDROSTAMt TET qV CLOSURF. MEMBER HYDROSTATIC TEST d.INSPECITON -

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PHONE; (508) 852.0200 TELEX: 92.0448 FAX: (508) 852-8172

Attachment #8 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 41 of 56

~~~~~~~.

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NELES~JAESBUR

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I

.~ ~..~ ~ ERTIFICATE'OF CONFORMANCE

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o t e s Speci.fica,...

• on No.*,

.,:.'* :P-14E, 749. Rev  ;.....'7. . .

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Rp eo F.r A .~~c ..

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CT 08385. o :N 51 1 Wfo a de

. .7 ,.t7 IWe certify that the valves being Su~pplied on tho. above4t~ weemnfcuedadIsetd in F~le ..:l..

%b~di-Alth ~1~

bl .

requlrehl :___,_-.__________.._.____;__-,-__'_'.,-_,o______,,.,.__.,,____....___%*_-- '01 .

Inc~~bj 9n7 uc e~af a ltjF 1 ____,__._*:*.*':,:

ram *,

• ~:W~ te*. f "rdr-* *. * ' ...*t R . **!i:ii; '=* " :.. .' ..........  ! ':" " " *:'!=*:40E : '*'

....; ual Rev.22. dated, Sep. .93 and. wqer. ouind, .to be, In ofrmance with-the. above'rfrne

.... . . .. . .s .

Norheat '..PO~ISp&i&ain

.. " i' "". . ., " "aNd Nes-Jamesbury, , .. .:*"*::*::::".:.:..*I";:P:**.':*:'.."

Inc. Order.' i;.* ... ..  ;:';.*;,.',-.':*.'..I  ;*::.*-...N.- ,

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• We also certify that the below listed item(s) were manufactured and Inspected in accordance with Neles-Jamesbury, n.*..'s*mmercial Qua*t Program Manual, Rev dd

,,::acc6ord~ance width Wok In"t#t" .1(edcto fcmerilgaeprs an fud' to'be acceptable.

REF. OUTLINE AND ASSEMBLY DRAWING (NDOS5i1.52 I E-.8) BILL OF MATERIALS C ITEM . PART NAME MATERIAL SPECIFICATION 2 INSERT ASME 59-1560 UNS N0O. CIS00 4i S-i - 'i 0 LQ

. 21 COMPRESSION RING MONEL..

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640 LINCOI.N STREET BOX 15004 WORCESTER. MASSACHUSETTS 0161 S.0004 U.S.A-PHONE. (508) 852-0200 rELEX: 92-0448 PAX: (508) 852.8172

Attachment #8 ETE-CME-2013-1005 Report Generated on 3/8/2013 5

07:14 PM Page 42 of 56

."'FORM -NPV-1,..N ýCERTF1CAT, ..HOLDER9 DATA' RHPORT! FOR NUCT.NAR' PNPB OR' VALVZS -

AuO*-e ad byi' the ptvoision of tahe *ASMi Code, Sectionl Div. 1I 1.~~~~ b Z~I, odetx~ Isection X .*.

2.' -Manufactured ._or' O0 3.4: Location of Istalation ... TONE t a. M al .. ).

• ring C.) Clas (

3iEiiiz 30 .

(S)

(7) j9Y s.,S 1jrlex- LlescriLPT-on oZ BsrvIM zor wnrLCzi erlymeiýn WX =33.95501

• • ATERFOR, CT.068 B=DY@ 230 F

6. Design Condition~s; BEAT 0 12fs_ OF or Valve Pressure Class I' (1)

,7. Cold Working Pressure 230 psi atu 300 7.

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F Mark No. material SDec.No. Mmnufacturer' Remarks

..- 44S.;B-O050 EWBLAI TE ~ *;,..=..

.: ..*;;;ii,..*!,:i.-,.:;;:;;,*,*;.

OR-148 TiMS MO.C95400 I. P8LvpmZ STEEL .. - I amY I MD-1413 DS 3O.C95400 r I AJVLVM= BTMM 6*~ I

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Attachment #8 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 43 of 56 FORM NV- 3 (Back) Mark No. Material Spec.No. Manufacturer Remarks 9 (a) Dolting 9 __________________ I __________________ I "1

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U we tlieuy tatemaentprd. in M M" eo2t r opor tand that tft .0Woaj v at CownStrutot oh 0~f MU aefrN la power... Section 111, Div. 1.j Edition .frAddenda ..I83.. Code CMOe No. NI3z.Jt A~ 2 Sigiied =ffl by 7449%6CKC, Our ASKS Certific4ate of Autho rizat~ion No. JH.l22jL~t use U D es n .i .t .' ",. :.

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stress analysio . - ,rt ( a 1 only) oanfi.e at.. N.i I Design specificatioais certified by (1) THOMA ~J. lN i o... St ~aan yt~cer a led l j PR. tate A W

                                        .                                                               r CR Eot~CRT             g se w                                          .       ......... ...... ...

I. the undaer.ignd, holding a valid commission issued Ly the National Board of Boiler and Pressure Ve..s... Z a.rs and the.State.. or..Prvince of A"A .... andeupayd b PLYI EMUL o

Attachment #8 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 44 of 56 PENNSYLVANIA STEEL FOUNDRY &MACHINE COMPANY. . QUALITY ASSURANCE. CERTIFICATE OF COMPLIANCE

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Attachment #9 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 45 of 56

                             *"oiein-,. "'

ROUTINE WORK ORDER illilllIIlIiliM 0 PLANNER LEAD CRAFT:." ominion I PTIO .-- SREACE V WORKORDCONTROLLED WELD I PARENT WO: WO RNVSLEVEL: r oCNTROLLED COPY PRINT:, COPY 0 i M33SWP*V674 , IUNIT- 03 1 SAFETY RELATED WORK DESC;RIP;TION: REPLACE VALVE 3SWP*V674 < REMOVE / INSTALL INSULATION AS REQUIRED' WORK-INITIATION VALVE NEEDS REPLACEMENT DURING 3R10 (CR-04-04229)

                'REPORTED BY:         ross0,07                      ICR#: CR04-0422.g1TAG#:

WORK AGAINST LOCATION M33SWP*V674 LOCATION DESC ESF A/C VENTISI PUMP COOLER SUPPLY HEADER "A" ISOLATION WORK ID 0 LOC LIST LOC LIST DESC EQUIPMENT EQUIPMENT DESC SYSTEM DESCRIPTION & PHYSICAL LOCATION OF WORK AGAINST SYSTEM ISWS I SERVICE WATER SYSTEMS AREA ES. IENGINEERED SAFETY FEATURES(ESF) ELEV 0024' GRID TERRY TURBINE PROGRAM INDICATORS QUAL CLASSj_] APP. R f AOV ON] APP. J [-]N FP [3Fl SEC XIf jj* EQML N] SEISMIC L_] MOV [N] HELB [] CHK. VLV =N' lST EQ RELATED ] PRA [ LIC. RENEW f-] KSREL [] HEAVY LOAD [N] ASME CLASS REG. 1.97 EE] FAC L PMT MATRIX [7] ERDS [] ENVIR [ CRITICAL IN SBO[80 HUMAN FACTORS [ SPV[3 ADDITIONAL STATIONS REQ. PROGRAMS TASK INFORMATION REQUESTS 91-18 OPERABLE/DEGRADED [] ADDITION #1 [] WORK QUAL. CLASS I SR I Y/N REACTMTY MANAGEMENT'[] ADDITION #2 E] ASME PROGRAM L--i- RWP REQUEST LEi INDUSTRIAL SAFETY *] ADDITION #3 [] WORK PRIORITY N REQUEST [Y] SCAF SYSTEM HEALTH [] PMTDS 7 ] INSUL REQUEST [J BACC fN* CONTROL ROOM ACTIVITY F TAGGING REQ [yl

                                        .CAPR L-]                                    MODE CHANGE REQ                        COATING REQ []

COBALT REDUCTION [L] UNIT STATUS Li6--- VALIDATION R9Q1 10/19/2008 12:44 Page 1 of 15

03 CD. wmtMXDE10/19/200$:S Ir 8 N L IND INc JobNo.: 34039 1CO5C041 4 30 INDUSTRIAL PARKRD P.O.No.: WDOID03 VERNON, CT 0~60 VOLI PmdAwm~ -WaaOeay V0193ilU U Pemt i444-709 -Far 212M?W taml9o.ý P.1(9. 4M1A Spot: AJ4SA927143-C95400 Attn:GA DEPT (1) 8uscno Us o Ow.'vyil 4 SlipphungMole: 10/13/2005 Pago I of I m cmm"AL AN1.Z.*3Z gloat no. toat Type 1(0. PCe. AL. 12 NX In OE PEIAL 4 10.4 as 3.9, 0.1 0.3 0.1 1 Where: OL1111ok"ifla

                                                                                                                       -ft dmvmd k" bw w

OOECEMOCAL floflRT~us cktior =ý= tz= 0 Neat No. u'IT. , 15 (2) &Oam muu SZ.,tf ýý - !AN 2 7 205 psi P8+/-  % 4g go-sisal 114.000 311.100 is 207 PO JAU"I A1k CD 0L 0 THE CON~M1 O TH 114382 107z CEUTIP73 - BE C22Q hIS ,uAu-OT. 20 10.OO1)T 15 CERTIFIE TO 0079011WTO DIMI S0A;. 81MMEMETS. PI) 19.TSRIAL IS rREE. FROMHflCU~R CONCTAMINATIONC. 90 LON VZfuIN MINT. ICATSRIALBusis IN47112 flRCT10 or THESEC37O8INGB. Mk4fIFACrjRCD UMMR WC QU~ALITY SYSTEM~ IWIAI. L a PAM 12/30/2003. ALL TEST RISULTs AND 73(2 OPENATtomS PaWzmo By we0An n COMPLANMCE WITH iA sizcTIOa AoMTHE SPCII 11 7148.xruz~o. APC CAL0021.M 1W NE2WRZPA.XRWASNO0TPEPRFORMan H:S KhaftEIAL. ASKS OtM6rIY SYSTEMCtRTIFICATE IMATESL&S) ZROM 00-S23. EXPIRATION1 DATE,N1OVEMBER 6.* 2001. WISCONSIN CuNthIFUGA.. COMPLIES WITA M5 UZQ Iavms or 10CMIi. L '/ i- i ACTUAL HJ=4R3T+/-7~ 1 2 HR25 11O; 110.2142 63742(.2S3P 45 K=W NO. OCcT19M w Tur U,1ad wadf: 0wakaIAmali.o- SIp C..,I15 Mb~Aiuha!-COmAvalen. aqjn 3* NftprwdL*fri 93dnm alg14vw p- opwuvWJ TheIm0~wd" oflqW. ldamwAar koadjaga wosw hmlb w an .6k rep on y baw rw~oa~nyawkaaaw 1 1011/200 (7 A caawmWaion wipim - OIaorS 52008 Quali~~~~W y u ry Asumcjlbdý IO l

AMINDED 10/7/2005: SPEC ON LIND INC. Jcb-H.. 33746 (C050041) 30 INOUS¶ROAI PARKRD P.O.N*. W081003 VERNON4, C 06066 US E.&SPOW h bVie

                                                                                                         -~V#*Pf       33VISUSA                  P*6)4mo:602-A40-04*54-AIC2 Allm QAkDEPT  (1                                                                                                                 Guwrtty 7 CamUicAmaN TUST REPORT               f                     Shippi 0.1.: M/2M200 pag. I of I euwCAL ANAL-ai!sZ zst. No.                     te0t. TYPO NO- PC8. A6L            CU     FE    WI    x    - TO!                                                                                       m
                                                                                                                                                                                               --i 10.5     64.1   3.9   0.1   CA2    a.)                                                                                       m TIML           1 sls"1
        /7                    feru    0    -0lP35..?10 C')

en~k cps OUC=*zCAh PaOWZRT1=B 15= IS 11tl) .A W 15 szený . AN:27 ?N No. P64 1011.000 P.1 3S.100 I0S 1le 1.97 0 CD. THE!-COXTDMT OF THIS REPORT IS C.kTg15 TO 53 COIU13C ARD ACCURATE..- CD PRODUTic IS CE5TIPIMV -0 CCIFORM TO VrAZIISIMI- REZ--OtI:2TS. CL 0 9021M*AL 18 7353 FROM MER30tI5 COW2I W-109kIO. C.) sto LwV HLT130 10131 IIASraIS USED IN IZ PROD20UCTION OF 70155 CAST'licS. 2! IGJIUACTU UNDE 3305 C 3C7LITT SI(SrEM KANIUhLRZV It DAM2./11202 BYWC ARC :j COMPLIAMCS WITHTHE! MATERIALSPVKXIWCPLT103A5ITEE SPSCIFIC AIPPL.ZCA=3 0BXZU5L f31l~Cl 1,j ALL TEST RESULTS AND THE! OPREIfLTOtSMpRPS C? 15W REPAIR MS. 301 9E1?VW CM1THIS I@.ZERIAL.

            ,.tH- GOWy¶ SYSTEM      C13tTIFlCATZ CNATDZALsI NUMBE QSC-52S, EXPIRATION EATS; 807L'ENCR E. 2005.                                   p...-

14!SCONlSIPC1"UY1R700L COMPLIES 11111 THE38SEZX3ITS OF 10CM21.  % ATEURALPP=AWC==A1 UND013A QDZAL:T SYSTEM 141506 COMPL1IESWI.¶TH6AMB GICTZ0 III Joel WITE SIDPAf 1903 90Awc. OC-721 ACTUALOW V TRIUUHUIT 162ST1 2 1455 - IQ; 3.185? - 4 RILE 30 N13tS - 310. OT-

             ,tdm*d    .&      0.os Ch-W      11.i.-   OES      A.FUI8               AWJ~J1-Cib~a     IM~30       ~h,             w W00 MWIUI1U9    MOW.

10/7200 my =eimw api~s~- odoebw J. 2DOB Qualttl Aus. H.R aPubfc

BNL INDUSTRIES, INC. NUCLEAR POWER ASSEMBLY & TEST REPORT SHEET 1: COMPONENT IDENTIFICATION CUSTOMER Dominion - DESC: 3" B.V. 15OPSI DATE: s- Og CONTRACT 4 .3643'6, C*6 DWG: HBV-F2-30-0024 Rev. 0 CODE CLASS 3 ITEM: 00001 QTY": .2 SALES ORDER #: A050511I NDE PROCEDURE: N/R, . UNIT: Dominion m DESIGN SPECIFICATION: SP-ME-749 R!I & DCN#'s DM3-S-(0033-94,0394-94,0426-96,0778-94,0962-96,1014-96,1305-95) C? ANI REVIEW: DATE' "z-- SHEET I OF 2 CD ALVE SERIAL NO. BNL INDUSTRIES. INC. TRACEABIUMY NUMBER FOR PRESSURE RETAINING COMPONENTS BOLT ] STUD ( NUT IPRE-ASSY

                                                                                                                                'a BODY- END CAP POPT/BALL[ STEM                                                       Hp          0 CI A05051 1-] -21                       le- 21.              V_..                                                              0 CL A050511- -21                       0-9-71                                                           v!i__-)

IN 0 _. ,-.l- _ _ _i- m_

Attachment #9 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 49 of 56 04/04/04 04/08/04 Approval Date Effective Date ASME Section XI Repair I Replacement Plan 6I SECTION A - DESCRIPTION OF REPAIR/REPLACEMENT ACTIVITY (Sheet I of ) 1.

Title:

Replacement of Isolatibn Valve 3SWP*V674

2. SystemName SWP System No.: 3326

3. AWO No.: M3-04-12156 DCN No.: N/A P.O. No.: N/A 0

4. ASME Code Class Designation Class 1 [] Class 2 El Class 3 0 Class MC El Class CC [I

5. Provide a General Description of the Work to be Performed:

1) Replace Ball Valve 3SWP*V674 and bolting.

                                                                                                                         ]_Co..ntintion Sheet 5:1     Will the activity involve any of the following?

Welding [I Brazing El Metal Removal El Replacement [

6. Flaw or Relevant Condition Found During Scheduled Section XI Examination of Test s l YES E] NO State tie Reason for the Repair/Replacement Activity:

CR-04-04229 identified valve as being degraded. 6 7. Item(s)

Description:

Itfms) Descri9Jiot

                                                                                ,___   ____ _"E Item(s)

Description:

Continuation Sheet Item(s)

Description:

                * -Description: ..................... 3" Ball Valve CgW'r 4         THREADED ROD 5/8"               Heavy Hex Nut 5/8" Material: ........................ SB-148,C/95400                SA193 Gr B7 '                   SA 194 Gr2H Dwg. NoJSh.: .................. 12179-C1-SWP-67 SH 2 of 5     12179-CI-SWP-67 SH 2 of 5       12179-CI-SWP-67 SH 2 of 5 ftern No.:     ...............      108       S- IAC*             93                              94 Qy:o                                                              8                               16 Line/SupportNo ....... ;....        3-SWP-67-3                    3-SWP-67-3                      3-SWP-67-3 Manufacturer. .................. Contromatics.                 later         'bss %o/te[* later Stock Code ................         42064944                     -42 97 M['*           '7Zj       M3600061 UTC/Batch: ............. *.......         -                       js         o     *    "          at -- C2"      i PMMS ID: .....................      M33SWP*V674                   M33SWP*V674                     M33SWP*V674 I    ,,*'Td4$A7 -, r                          '                    El Continuation Sheet

8. Supporting Documentation: Yes 0 No b] qource Document: 12179-CI-SWP-67 SH 2 OF 5

9. Section A - Descriotion of Repair/Replacement Activity Prepared by:

DavidS. Brady I.. I1Jan 2008.; (Printed Name) (Signahte)) 4 (Date) 6! Form WC 3-001 Rev. 001-01 Page 1 of 6

Attac:hment #9 ETE-CME-2013-1 005 Report Generated on 3/8/2013 5:07:14 PM Page 50 of 56 FORM NPV-1 CEIMnRCATE HOLDERS' DATA REPOR'T FOR NUCLEAR PUMPS OR VALVES* W ~~As Requlied bV the Provisone of the ASME Code. Section Ill. Divison I

1. MerAacettuteclandceni41.dby IINL INU'USTR1ES, IN". *3C 1I J!-TR',AI. PARKie F-%D. 'jER4N'.1, cc'*

tIms sod ad&*&*c 61N Canitincet. olei

2. Minultorsdfor IXIl41NON NUCLEAR CT,--PO- BOX 75459, RtCW1NONO.-'VA 23260-5459

3. Locadmo(Jasitallathn DOMIN-ION NUCLEAR CT. H&OPEFIF39IY R:), WATERFORD. CT 06395 (no"e and 0de""l

4. Model No.. Series No,.or Type VALVE Dr)jwin &MV YZ --002 4leru. 0CAN - -

S. ASAE Code. Section Il.M~n1 1983 . '-3 - (.IlJonl .e) a*"* Idccc lCode Cce no.

8. Pump or v% VALVE Nommnal nbet~ a'- Outlet si.-

7. Material Sd SB271 AL.CS546Obh,,t SB271 XL.C954O0)Dj, SB564 A!- 44D0BNOG ,,,A193JGrII6/5-"I'4Gric liI le) lei Cant. Body Disk HeD.?.' Serial Seri,,

Dowd No. Swrim No. No. A050511-1-0lI 51581 51.i51 W198-I 51581 515"11 W198-; A.050511 C2)

                *uww
                  &plmnr       c~notion In (am oFIlute. eldwa. w r*.w~og mws be used Proldi            ý,as Ise x 11. 12) kInfNmo"ion harhms     1 throg 4 on"OIsDte Bscon Is nduded n escadt  deet Msadhasi Isajhmierd   w            u fdthe       -howte to diMardeda. the rcoof fts fbumf.

TiA frm EOOO371 may beamonBted hornUs OW row DePt. A k W06'f=rd~rjOO~o 0 0

Attachment #9 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 51 of 56

                        -~   -FORM                                      WP    -

I1I5.c-Pg. 2ofd-

a. Design condition, -m F a. valve pressure cleat ANSI__15____011 120

9. Cod Working preertse 106iPSIG l F psi at WOOF

10. Hydrostati test 350 Pa Disk diularsntlai test ciafg.2

                                                                                             "-                                                           nil

11. Remiadk:

CeTl*VATION OF DESMG D4,111m1,Specification Canlflad by  ?.J. MANSON P.E. State T Rag.no. 12400 Oee~flailflebyPE.LState - Re0. nor CERTW1CATE OF COMPUANCE

                                                                                                                                        ~

We citify that the sltatements made in thta report samcorrect end that this'piunp or valve ccinfwnirif-otheirre faorconstruction of the ASNEll Code. Section itI. Division I. NCenificsieafAuthoqzulzIonlNo . . N-288,' Expirs 1100 0 o.A42?7 J BNlLINDU.STRIF~S, IN Cartificateot d~rl INC. Sge

                                                                                                                              %."i CERc7F1"TE OF uSPwTcI0ow 1.the undersigedind hokq  n      vaa    ommhalid    on issued by the National Board of aoller and Pressure Vosua Inpectots. and theSteta rProvltnceof         CONN'.                           ,ip~oylsdby                       ONEBEACON AMERICA INS.

BOSTON, MA ofSON have Inspected ili pump, at valve, deaerthed in this Data Report on

                             ,      ;.    .          . and elt Owtlto the beat of my knowledge and belef, the Certificate Holder has con-tsct*d 10thpump. or valve. In accoardnce with the AWEt* Code. Section IIl.Dvision 1.

By iWning 1"th certificate. neither the peclt nor his employer makes any weruanty. expressed Or Implied. concewrng the comnWeot dmafted In Oft Data ReptM Fthe*momu nelther It Inspectoetr.r his employer shell be Ui in a&ymainew for any perso Inalw cr p.l o. any kind aulsing from or connected with this Inspection. Date rtsS .-

                                                                        ).IN~et'L Comminslsons      112    14 S. Ilei. inidoessms ~tat w

ltstaevperov. asod e, III For manualy operated vvea only. S

                                                                                      -Z(?( (IW)

Attachment #9 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM .Page 52 of 56 ASME Section X1 Repair / Replacement Plan AWO No.: M3-04-12156 Supplement - I0 NOTE The forms in this procedure incorporate the minimum information to control repair/replacement activities. These forms may be revised or computer generated without requiring a change or revision to this procedure providing the intent is not changed and the required information is not deleted from the existing forms. SECTION I Supplement Number: CHANGE I Associated Repair/Replacement Plan Number: 53M30412156 Reason for Supplement: CORRECT MATERIAL LISTED FOR BALL VALVE El Revision [] Cancellation SECTION II Provide description of change or reason for cancellation. List replacement parts to be added providing same U1 information required on Repair/Replacement Plan MATERIAL FOR BALL VALVE SHOULD BE C95400, NOT CA95400 AS SHOWN IN MATERIAL SECTION SECTION III Originator: (certifies ANII was notified) *X2- Date: j' / Inservice Engineer: (required for revisions only) ,-

• Date: lop, RPE (for IWL): (required for revisions only) -/WJ - Date:

Code Inspector: (required for revisions only) / Date: /, Requiester: Date ibll (Supplemenf adde to AWO) 0 Form WC 3-001 Rev. 001-01 Page 6 of 6

Attachment #9 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 53 of 56 K BNL INDUSTRIES [NC. RECORDS INDEX PAGE I OF 3 CUSTOMER: Dominion SALES ORDER # A050511 P.O. # 45364306, C/O# 6 7 DESIGN SPEC: SP-Mz4-749 t/i & DCN,* DM3-WS-.Il,)4-,42. -4,O8f.2.*. I W-M.,, 30.-J. ITEM: SIN A050511 -I-(I THR U 2) LIFETIME FILE RECORDS LOCATION BNL OWnER BNL INDUSTRIES, INC. RECORDS INDEX X ASSEMBLY & TEST REPORT X INSPECTION & TEST REPORT CERTIFIED MATERIAL TEST REPORT X HEAT TREATMENT RECORDS FINAL NDE REPORTS REPAIR RECORDS DESIGN REPORT X AS-BUILT DRAWINGS X WEI.D PROCEDURES DESIGN SPECIFICATION X FINAL RADIOGRAPHS CODE DATA REPORTS x FINAl. HYDRO/PNEUMATIC TEST REPORTS x DISCREPANCY REPORTS NOTES: QA = QUALITY ASSURANCE FII.ES E = ENGINEERING FILES PREPARED BY: 1". J. MAGRO 08109/05 S Ll N

Attachment #9 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 54 of 56 30 INDUSTRIAL PARK ROAD- P.O. BOX 2560 VERNON. CONNECTICUT 06066-0660 USA DSTRIESIC TEL M-870-6222 FAX 860470-4221 www.valves.net

                                      £-"%Vv;D
               -   ".u
                   --.- -    1a'.          *liml              n a-S   aa PURCHASE ORDER                 45364306~ C'Of 6 BNL SALES ORDER                A050511I ITEM                           00001 0

S

'Attachment *9 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 55 of 56 I. BNL. INDIISTRIES INC. RE:CORDS INDEX PAGE 3 OF 3 CUSTOMER: Dominion SALES ORDER # A0505I I P.O. # 45364306. C/O# 6 DESIGN SPEC: w-,-mr-749 Wi & DCN6's )M3-S-((0o.3.-94,03Q4.Q4,o426.96.,0778A4-.nS62.96. 1014.96.1 305-Q)SI ITEM: S/N A05051l-l-0lTHIRU2), QUALITY ASSURANCE RECORDS VALIDATION: The records identified herein have been received and approved for completeness, authenticity and accuracy. These records are considered to be valid Quality Assurance Records. Signature: Dale Quality Assurance Manager The BNL INDUSTRIES, INC. RECORDS INDEX (all three pages). and the records identified in this index as Owncrs records.. have been received by the Owner or his designce. Transmittal of these documents to the Owner or his designce is documented by the signature, title and date below. Please return a copy of this page to BNL INDUSTRIES. INC. within 30 days of t.he above QA Mges signature date.

                .. ; sAA2A                                                 Dat           ,A Owner or designeeltitlc:       S. ufv J                             UrL44                       0§ Oskl        15C'A -,~

0

Attachment #9 ETE-CME-2013-1005 Report Generated on 3/8/2013 5:07:14 PM Page 56 of 56 30 INDUSTRIAL PARK ROAD e P.O. BOX 2560 6 L- VERNON. CONNECTICUT 08066-8660 USA OSTRIES, NC . TEL. 860-870-6222 FAX 860-870-221 www.valvos.net CERTIFICATION OF COMPLIANCE This is to certify that the material and or services supplied on Purchase Order Number45364306, C/O# 6 Item 00001 Quantity 2 - are in strict compliance with purchase order and SP-MIi-749 RA & OCNVrs DM3.S-40 33. i5-95) 4.394-g4.0426-96.0778-94,0g&2-%.1,l14-96.I The test reports represent the actual attributes of the items furnished and the test results represent the actual attributes of the items furnished and the test results are in full compliance with all applicable specification and purchase order requirements. The material and/or services were manufactured in accordance with ASME:Scction II and Ill, 1983 Edition, S'83 Addenda CODE CLASS 3 & QA Manual. 5th Issue, RI0, datcd 09-15-04.. No welding or NDE was performed or required. Valves meet the water & cleaning req. of ANSI N45.2. I & .2. Seats'& seals.TEFLON / R. TEFION Cure date is NI/A shelf life is unrestricted Stem o-ring - VITON 'A' Cure date isq.%j, shelf litfe is 49yrs. Body o-rings. N/A Cure date is NLA, shelf life is N/A Dravwing#'s HBV-F2-30-0024 Rev. 0 Seismic analysis# N/R Valve S/N A05051 I- I-(I T IRU 2) Design Report# DR-A0505 II. Rev A ]*.,iJ{i I Date: JAN 27 206i Thorfd J. Magro Quality Assurance Manager S (7../, c;,y,, .

Serial No. 13-169 Docket No. 50-423 Enclosure 2 The Surry Power Station Test Report Materials Testing on Similar Components Removed in the Mid 1990's. MILLSTONE POWER STATION UNIT 3 DOMINION NUCLEAR CONNECTICUT, INC.

Me~moranduim VIRGINIA POWER 7]= NORTH CAROLINA POWER To: DISTRIBUTION Innsbr0ok TechnicalCenter From: u u m December 15, 1993 MATERIALS ENGINEERING LABORATORY REPORT SURRY HOT .LAB NESp-p ,-104 The;attached Failure Analysis Report NESMLQ-ý104, is'poied use. If you have any'uestions or comments please direct them forM to: At~tchmients DISTRIBUTION:

DATE: December 13,: .1993 NES MATERIALS ENGINEERING :.LABORATORY

                                . A..

FAILURE

                                   ..          ANAYSIS REPORT NESML-!ýQý-104 "tation.:

S. Surry :2. uMd i i. and 2. .3. Component.:. Surry charging ..pump .service. water system aluminum brOhn-zee. valves 1: 1/2 1,and 2" diameter.,. Jamesbury style 5150:, Cl-ass 1.50, ASTM B148 %alloy :C: 95.400: material. 4C. Safe6 Rlgtd X. Yes 0__N:-

5. Descri*tion of Failure: .44 aluminum .bronze service water; val-ves, which were"installed in .1986, :were inspected in Surry U6nits.: 1 ,and 2, indicating !that: 1 valve had. minofr through-wall. leakage, 10 valves were observed to:, show through-Wall seepage:, and .1 valves.

exhibited some: form i.of crystallizat.ioni .on the surface (from. through-.wall mbisture) .The laboratory was requested to perform.

      .:a railureý analysis and. dete"ine .niterial *residual s.treng.th for
       .the affected valves;.
.6..   :Laborato__rv.onclusion:               The valves were determined* to. eXhibi t, dealloying (cor-rosion). of the aluminum ri..h prtions (beta.phase) of the microstruc.ture leaving, a porous materi 'al wi't'h much lOwer strength.         The dealloying: ws a result of: ()                           corrosi e-Ithe c servicde. water-i, - (2) the. presence of microbes which added tlo. the.

corrosive nature p.hosphorus., of the environment. (ocompounds of sulfur, calcium,.. ,potassium., chlborine., Iron and: si'lica), (3) the , low-fl6w". nature of these service Water lines:, -and (4): the:

       .suscepibiity o                this alloy In the as-cast c ondi ion
       ,dealuminification.

7. Inspections andi Analyses Performed: suts:

Visual Inspection: Visual inspection.of the valves and corrosion products., Fires I and 2,. revealed a heavy buildup ofcorrosion product.s. n.o..dules;, and.ýorganic rias in many of ;the. valves. Some valves were r!eported *to be partia*lly blocked. by these: substances. MLight Microscopy./acrosections: Light, ;microscopy .of.

       -macrosect ions,: Figures 3 and, 4., revealed. regions. of. dealloying

(.dealuminihfcation.).., The dealloying was 'seen in. three, distinct. f orms:.. (1.) general are.a..dea.!loying, Figure. 3' and Figure. 4a, which

was the -most -common form :of attack; (:2) cellular attacký above a region of general area dealloying as shown in Figure 4b. and a highly l:.ocalized attack ,Or ".plug type" dealloying normally

      ."assoc..iacted-. wit-h discretej, individual corrosion nodules with high levels of microbial; activity '(see section on Microbial Analysis of Corrosion Nodules.below).

?N..ESML*Q-.1O04 Decembern .3*:,. 1993:. 'Page 2 Metall"ography: Me ta1"*oraphy Io the .. uminum bronze- material ,of the valve. bodies is shown' as. Figure 5.. The mi.rostructure is that

• of as-..cast .ASTM-.B: 148. aloy C 95400 (954)', wh.ich iS composed of an alpha: phase., eutectoidý transformed beta phase, and an aluminum

        .richAl-Fe.-Cu pha-se.- As s~hw ihn Figure 5, the. aluminum*"rich. beta,

• nihse&- and.All-Fe-Cujphe aesltily leac'he (Or-roded)' fkom~

the: alloy leaving a porous :netwtk. of. apha, phase and .corrosion products-., SEM Microscopy: .SEM eectron. micrographs were..made': of" the

        !stru ture ofa.deal'loyed: sample and' a'res::shown as.. Figure6.            6si 'The:

SEM rmiCr10gra.ph cle-arly shows. .the porous nature of the dealloyed: strucue ind a I"each path" for corrosion producý,ts from the stru.cture.: EDS: Analysis:ý Numerous '-EDS: .analyses: .:were made in:the. Surry Hot Lab of corrosion. products, dealloyed :structures,: and. different phases of. the aluminum bronze valve material/samples. The resultts a."re presented in Table 1.. Co.orrosion products ýwere found to 'be rich 'in aluminUmi. sulphur .iron, and chlorine4,,.,am6ng other elemerit.S. These results"point strongly to a: icrobial influence in the .dealloying process.

        .Quantita.tive Chemistry-:              Quantitative      ch.emicalI a!analysis :was perf ormed By an outsided vendor, on sanipes rfom two valves.                    These

results are presented -as Attachment 1. '.T*echical IanalysIs results indicatedd that: both valves were sligqhtly., low in. aluminum and. iron for. a.l.oyC *9*54..00 of ASTM..B.14:8. Slightly lower "aluminum

      ..content would not have adVersely. af fected the.corrosion: resistance f the, valVes.        Also, :the'*lower. iron value' is. :not. known:   t.o.1 .lowerr corrosiOn resistance,             Aluminum:values -were 9*'.69% and .9.68%vs. a:

spec"ificationminimum of 1.0%.:'::. value in.imum value.f values were, 2.76% andd Iron .3.0%. 2..69%: vs. at specifaion Measurements of, Dealloyed Wall.. Deplth:/Percentage.:, :.g.ive, service alves were: sectioned and.evaluated metallographicaally to vwater

        'determine, depth of idealloying along., the axial -section'lines.. 'The results of these measurements are presented in Attachment 2.... Two.

v alves.showed *some areas .of throughi-wall dealloying,' while three

    *.valves revealed. no areas: where 4dealioying had progressed. t*hrough
        .Tensile:           Extensive 'tensile testing was:: performed: on samples removed[ from valve l-SW26. Tests were made of good.:"material and deallooyedi :material in: various .percentages of: deal:loy ing.                 These
        ..results. are':.. presented as. Attachment. 3..In                summary, . t"ensile strength varied..f rom .75 ks:Ii- for good. material i{uundealloyed)Y, .*to approximately 10 ksi for..100.%deal~loyed mate.rial..

'NESML-_:Q*- 1:0 4.

,December 13, 1993

.Page .3' Fracture Toughness: Fracture: -toughness ... tests were investigated but. were, not. performed due to vendor :.quoted :times of. 3 to 4* mont-hs.. for. t.esting.vs,. 'Valve replacement -scheduled'for ,2 ýmon~ths. %T~he lengthy etsimefor was a resul:.t of -theý :small (physical) si~ze. tesing of materials to be tested. and possible use of complete: valves as test specimens: resulting in extensive engineering .time to make and.

analyze test fixtures, and. analyze test. results.-. No J-,R curveý fracture toughnes's test data :for ASTM.B-;.148,ý CJ locat.ed...,... -95400:. "as-cast .were AMicrobial-i. Analysis. 6f Corrosion No*d~l'es': A ..microbial anal.ysis was,

      'perrformedm       o.n ,se*cted: .orrosionnod.ule.s'....from valve.:                     by.- an 126-.. by outside                  BTI. This            ivendor,presented as Attachment 4.

iThis report. concluded that total bacteria/gram in the -no.ule wasu at 'a level of'"2'... 18 ..x 10. and 8"that' aerobic,, anaerobic, sulfate' reducing' and: aci'd producing bacteria were present. Lltraspni',c .Te:st:'Technique: An-ul:trasonic test (UT) technique was developed by the. Virginia Power Nuclear. ISI/NDE Department, for: deterTninati0oi (as needed) of remaining wail. thicness of aluminum bronze valves': in. the .. !Surry service. water ýsystem. While- the; details of this.,technique are avai-lable i a. different forma, the results .of.. 'UT .readi..ngs of.f remaining uindealloyed valve wall:

     thickness           vs:,. metallographic section read ing- (at the:., same .

location) of val~ve l-.SW-ll7 are presennted, as the last table. in:

       .Attachment. 2:.* :Generally, there, was good agreement between the UT:

and metal-lbgraphic readings of:.remain.ing .wall..t*hickness:.

8. Commentsit: The-Surry charging pump se.rvice water syst em aluminum bronze ball valves, Jamesbury class* 1501D, in 1 1/2,":and: 2.1. size, failed after approximately:, :8 years of.' service as a, resultL.of exposure to. wa. corrosive service water. environment... The ASTM.B,148:

alloy C :954,00 aluminum bronze: .cast *material is. knownf. :"to be.

       .susceptible to': dealloying (dealuminiflication), in sea water- or.

other: corrosvet :water environments. .Te dealloying is primarily. a result of attack."of the. higher aluini..um content"- be'ta phase which x.,re presents approximately. :50.% of. the ;str0ucture 'of ",',as-cast". material. The resulting dealloyed. st:,ucure is porous. has much

       -lower      tensile strength and is quite brittle as comparned to' the good,      or: undealloyedý, aluminum bronze. -Also, it ,was determined that nodules and 'other corrosion products.in the valves were .high:

in populations, of aerobic, anaerobic, SRB:' and acid producing

        .bacteria.:. Those valves with large numbers:of: corrosion nodules, or heavy fouling, showed dealloying to a greater: depth, over: more.

of the circumference , than- other valves,. and it was concluded that this was: due to a:microbial influence. This microbial influence: appeared to. involve. the formation;.* of :compounds of sulfur, iron,.. silicon, chlorine potassium and, other el.ements inan acid env-ironment. The 'Surry qcha:,rging :pump,.. serv' isce: water system has

,December 13, Y§99,3' Page- 4

      .been operated over t.he years in a "var~iable f low" manner,. butý genferal.ly the ..system flow rate, would be considered      dPatiai low.

blockage: of some: valves was noted previously. to:: be: related:: to microfo0uling:, and thes*e valves were subse.quen'tly cl1eaned aindi

       .returned t~o: .s er:Vicee    Apparenlythe cleaned -valves-refouled .in'        'a relati&ely short period of .time..

9. Recommendationst All of these: .charging,"pump service water system

      .,valves,. which are used: in safety related: applications, are being
      -changed. out with valves. of: c6rrosion, 'resista~nt. materials not:

sensitive to dealoying. Also, it is our' understanding" that consideration..is being given t o ssome form of chemical treatment of

       'thi*is s.step'm. In*: "iaddition to           these.activities, .t-e lab would
      -suggest a. scheduled maintenance/inspection program to periodically
      -remove       a     valve(s)      :from    service     fo8'r <inspection, .for' corrosion/pitt'ing under deposits or fouling: which might, be present.. Al~so, regions :of -the 'system where flow can be increased.

(to design values) should see ýreduced fouling, better. flow,. and potentialily less. corrosion damage. Prepared By:.- Checked By-.- Attachments-a

TABLE 1 Sl4l*-0IANTITATIVE EDS PHEZICALj AAYSISl OF SURRY lLUMIýMý BRONZE SERVICEl WATERl VALVE STRUCTURE AND_ CORROS ION TPRODUCTS Sample Sample 1Description EDS Weight % By Element ......-....... .... _ (valve).. .Fe S S . Cl- z.. Na I SW-132 Valve Body Base. 6.73 9'.14 . .... . . i... Metal *~ "_._ , ......... .. .. .. ...- i i . .. .. . I_ I -S W .I 3 2 B lma l dy..n Bo t

                                            .er        6 3 .43       .      -  . .   .13                                              ..              i    -- -       . "      -- .        .  . 34."
                                                                                                                                                                                                  . .....3 4-.9 I   SW 1.32         Bal I.                                                           .36    ..                                                                                                                                 .17...

I-SW.-.126 Base .Metal.: . 85.62. 12.36: 2 16 ...

Microscopic Alpha Phase (Av-,.. of 6) 1--SW"-126: Baseý Metal: 82-.237 1 5.9 6 1.77...... -. * .- .. ....--

                  .Micdroscopic Beta
         .    ... Phase (Avg. __    of 5)         *_I_...._._*                                                                                                                                                                   -

l.-SW-126 Base Metal: 5i,.22. i5.'34 33..45. - --- -----.

                    . icroscopic* A.-.Fe.-Cu

_ __ _ hase (Av of 2) ........

6. .. _......

.SW-12.6 Underside of Large 33.00 1--.'. 29.91 17.43 10.72: .4:.38 -. 1 11 * ..... * . ... 3..44' Corrosion Nodule " """*...

I-.SW-126 Underside of Small 47.75 25.20'1 :8.61 11.93 ..i64 --- -. . 2.06 Corrosion Nodule "_____ *.._.. I-SW- 0.D. surface deposit ---- 16.39 24, 24 ;76 12.74 6,62 12.23 227,02 (seeping through valve wall). (a) ..... " . ' ' " -_' : :.......... . ' _  : 35 i !. . ..... ...i.... .. .. ..... . .. I-SW-:126 O.D. surface deposit.. .. " 25.10 17.63 2.07 1.91 3.48 --. .13.04 .- - . 2.798 iseeping through valve wall) (b) "_ _ ". , . ... 5 . .75 . .76 .94 . . .. ... 12.67 -48.82 l.2.26, 16.01 .

   .-SW -132        Cross Section.of Large Corrosion
                   *Nodule'                        "                                     ._.....                                                    .

Trace amount detected

S0"... ' " 4 3 a 1 *1 T"FTr Tq Figure' 1: Top, appearance of Ja:nesbury. Class::. 150,' aluminum bronze ball.

         ...valve, 1,1/2" diameter as-teceived in" .the Surry..Hot- Lab for metialurgaicalI anaiysis., Bottom , typical Jamesbury Class 1,50 ba ll1..

valve sectioned, in :the laboratory to reveal deposits. Exposed., aluminum, bronze body -section: is ,to the right. of bottom photograph.

Figre.: Nodules composed of corrosionp...roducts and microbes asseen. in ph t.graph1 at top lo~okinig: into. the: port 0of a 1 1/2 aluminum bronze service water valve, and.. in. photograph. at bottop with -a saw cvto through

a. nodule. The dealloye& area is evident ,In the saw cut. under: the nodule in the bottom photograph M(agnification 3X).

Figure 3.: Metal.lographic cross sections through:1 1/27Iand 21-

          .diameter Jamesbury aluminum' brinzei ervice water valves showing degree ýof: dealloying. The dealkloyed areas (shown by arrow) .ha.ve.! etched darker.... In.. each photograph .the valve I.D.. surface is to the bot.t.om.

Fioure 4 A:xial, metall-ographic. macro-sections through, valve:.bodies: of Jamesbury Class '150 valves. showing the forms of dealloy corrosion in ;the Surry service :water aluminum bronze valves: A,, general attack (valve I.D., .and dealloying., is to, bottom of ..all three;

        .photographs),;    B    general   atta'ck/cellular   attac.;   C,,  'plug type Attack under corrosion nodule. A, 1l-SW-ii-7; B,,         .2SW
                                                                      --132,; C, .:l:SW'-

126. Magnifi-cat.ion i.n4 each*c.ase. is :5..x; Etch,. A, B- silver ni*trate:;: C. ferrýic: chloride.

j' Figure 5* Tp, microstructure of §a cast aluminum bronze, alloy 954:,..servi.ce water valve I.-SW-1,2G. Large 1*ighht colored structure isalpha0, surrounded- by a matrkix o. eutectoid transformed beta. Small gray rosettes in, grains are an aluminum rich Al- Fe-.Cu phase, Magnification 400X. Etch, 10%.ammonium. persulfa*te. Bottom, .samestructure showi ng dark, dealloyed regions (bottom of ph*ot*og~raph) and

         .unaffected region (top of, -photograph).       Magnification l.OOX: (.same etch):.-

Figurd 6: SEM electron micrographs of a dealloyed region of

         " amlufminum b*.Z.oze .ervIce water valve.. Top, shois the deal"oyed. region under, corrosion nIdufie (left side of photograph) and unaffetced region '(to right side. of. photograph) away from corrosion nodule.

Botcom: electron. m'iqcro .graph-...shows,porousI.region of structure in. a. shallow pit- bottom (dashed line). on. valve T.ID. surface. Top, 28..X, bomtom, 1,,18.0X..

ATTACHMENT 1 Quantitative Chemical Analysis of Sur Aluminum Bronze Valves l-SW-125 and SlSW-126. :Vendor. NNI

V4

.INS LABORATORY SERVICES,,          031.., 1        11/*08/9l3 .14:4.8.

FINAL ---------- ý..AB .NUMBER 93013823. DATE ENTERED: 11/04/9,3. COMPLETED  :.11/08/93 14:40

• .EQUESTOR  ;"LAURA DEPT:. NNI. CHARGE :. 176L45012

?O..OR.`-NO.. :      ST 42.3109: R12       ITEM :I          NNPN   :"
.)WMGGRP/SH/LINEr : JOB ORDER 2351L4:50:12 tATERIAL         ALUMINUM BRONZE
;YS/ART/LOC         : SAMPLE FROM. SURRY, VALVE I-SW- 125 "PECIFICATION. : ASTM B148 ALLOY C95400
 'UR:P OSIE O 1F: TES-T : INFORMIATIO 1N: CHEMICAL ANALYSIS IFEAT NO.:,                     LOTW:      .LOT                SIZE:,          SAMPLE SIZE: 1
-ONTROL LEVEL :                   QID TAG NO. :                       053 CNTL# OR 195# : V875691 T4ANUF/CUST : VIRGINIA POWER/INNSBROOK--JAMESBURY                     VALVES OIMNTS:(.3).. :JHA
)I.ST.RIBUTION:'(1)      : 3..-LAURA-NNI.-PICKUP BASKET
?ARAMEER                                          RESULT
'CHEMICAL ANALYSIS OF COPPER BASE METALS)

MANGANESE (%) .08 ALUMINUM (%) 9.69 PHOSPHORUS (%) .022. SILICON. () .02 ZINC (t) .66 TIN (%) .10 IRON (%) 2.76 LEAD() NICKEL (%) .01 COPPER. () SULPHUR (%) N.A.. CARBON (%) N.A.. COLUMBIUM (%) TIT*A*IU (%) N.AN ANTIMONY (:%) N.A.. COBALT-(%) N.A.

     ,REMARKS                                       COPPER BY DIFFERENCE.

ANALYST(S) HR SAMPLE NO. (CHECK* TO SPECIFICATION) COMMENT: REPORTED. FOR. INrORMATION. AS -REQUESTED. ANALYST INITIALS SIGNATURE

.-ELEASER'
.)ATE

kC.5: INS LABORATORY SERVICES, 031,1: 10/26/93 14:06

   .;" ...... .....  .--  .- "---- i* .. ..  ,----   .

FINAL

AB NUMBER:

.EQUESTOR: 93.013049

LAURA DATE ENTERED : 10/20/93 COMPLETED. : 60/26/93 13::o DEPT.. : NNI CHARGE : 5176L45012

?O.-ORý.NO. :B8ST 421.09 R12: ITEM : NNPN. )WG/GRP/SH/LINE : JOB ORDER 2351L45012 4ATERIAL : ALUMINUM BRONZE YS/ART*/"LOC :SAMPLES A &"M FROM SERVICE WATER VALVECPSSRY UNITS 1& 2 PECIFICATION :: ASTM: B148 ALLOY C95400 ?URPOSE OF TEST : DETERMINE EFFECT OF SELECTIVE CORROSION OMN PROPERTIES. iEAT NO.: LOT#.: LOT SIZE: SAMPLEL SIZ IE: .2. AUF/CUST : VIRGINIA POWER/ INNSBROOK--JAMESBURY VALVES

,OMENTS (1) : TEST:PHOTOGRAPH D:Elo                                 YED TENSIL SPCIMENS, COMPARE TENSILE
-OMMENTS(2                    PROPERTIES          OF   SOUND  .AND:DEALLOY       AREAS:CALCULATION    DEALLOY ZOMMENTS(3).:                 AT TENSILE FRACTURE;               -CHEM
)ISTRIBUTION(i) : 3-LAURA-NNI-PIC'KP BASKET
?ARAMETER                                                      RESULT:

(CHEMICAL ANALYSIS OF COPPER BASE:: METALS) MANGANESE () .13 ALUMINUM (.) 9.63: PHOSPHORUS (%) ..018 SILICON (%) .02 ZINC (%) 1*.00, TIN (%) .08 IRON: (%) 2 .69. LEAD (4) .. :0 NIKE ... .041......... COPPER (%) 8*6:.32 SULH (N) .A.. CARBON (%) N. A. COLUMBIUM (%)N.A. TITANIUM (%) N.A.: ANTIMONY, (%). NX.A COBALT (%) N.A. REMARKS.. COPP.PER; BY DIFFERENCE ANALYST (S) .GEL/JB SAMPLE NO. "A" (CHE*ICAL ANALYSIS OF COPPER BASE METALS) MANGANESE (%) .14 AUMINUM: (1) .9 *8. PHOSPHORUS (%) .019. SILICON (4) .02 zINC .() 14,04 TIN (%) .09 IRON (t%), 2.69 LEAD .(%) .07 NICKEL (%) .02 COPPiE (4) 8.6,07 S.ULPMU  % N..A

CARBON (%) N'A, COLUMBIUM (%) N.A.

TITANIM (%) N:.A.

ATTACHMENT 2 Meaisureengrts of' Percent DaMaged

*Wall. Surký"Alumintu      Bronze Service Water Valves UT vs. Mechanical: M__easurements of Rem-ainin    (dodd) Mall VaIve. 1-SW!ý,117.

Dealloy Ana-lysis: Surry SW.... Valves Measu'rements on Vaive" l-SW-1V7. ction. .Wall. Thickness -Darraged Wall (in .1/. Damaged. Center Region S (in.. Location .(I.) Location .(2,' [ýocacionr ( A (12:0.0) .44 .. . .203If46%-! 0.183"141% B (3:00 0.302o 0.2521i/,83% 0. 176S8% a* 6 C (,6:0) o 43A 11 0. 249 1,/54t o. 2o08 ,/4G% - O.157 5i /13% D (6:.30) 0.278)" 0.201*/72- 1.26"/4S'%  ::0.23.1u 3% E (9:00) 0. 29,.7" 0.*67I"/Sr 0'. 1,31"/,4401 0 .19,2-/-6 .

         .There. was   a_   region with 100% throUgh-.wall dealloying"

Dealloy Analysis,: :$iUrty S. W. Valves Measurements on.Valve, 1-SW.-.12 5: Section WallI Thicknfess Damaged Wall (n.1)/W Damaged. Center Region:'

           ...   .(in.)                            Location       (1)     Loc   caatio1n i.2)          Locatiorn (3)

A (12,:00) 0.274 0..059/22% .. 0.00"/0% 0,172/63 B (1:30.) .0..2S2" 0,123"/4.7. .0."i./5 ,.0.

                                                                                                     !        017/64%

C (2:30) . . .,. **. . . . ...

                                                   ..* 000/0%

0.25" 0.107./41%: 0.163"./6.3% .D (31:30). '0.25*1 0-.00011/0.%0. o0..,l89.//75,% O. 209."/83% E (4:;30) .0..293" 0.0.761",26% .. 06i."/2 1%  :..0.s202/69% F (5:30).. 0.264."- *0'.092 ./3.5% 0..o0 "/o0% 0,.171 /65% G (7:00b) 0.255:12/31% 0 Q9. 1 3151... 0.12.1'/41A !H (9: 00) . -0.,279:" 0. 145"/52% 0.<147"/53. 3 0 1.03-/37% I (11: 00) 0..281.. 0:..01i /36% 0 009:3.."/3 3%. 0...i.3!8:":/49% There was .n. region with.-00.%G through-wali deailoying

Dealloy Analysis: Surry S.W. Valves Measurements on: Valive I-SW-1. 26 Section :Wall Thickness Damaged Wall (in 0) /% Dmged Cen ter Reg ion .

 "_  _:  (in.")                            Location (1)                 Location (2) Location                13)

A 0.315" 0.173a/,5%s 0.134J43% 0.215,/68s

  "-               0..00-*                 01*2"/61%                    O.135"/45%          0.212"/71       %

C 0.31.1 O.170" /5S0 0 / 0'.'0.220 //71%

          *~~.                                    .. ...     ......                                         ,,*

0.324"2 45,-5i% 0.1;23/.5% :0-206"/64%,

                                           ,       20.3,S, "13%
                                                        ../2            0.. 116.37%         0.227"/7-*

F 0, 305, 1o.VI"/36,k 0 "/0 0:.* 14 /64 0o3,2" 0. '0 ..000"10 0.194",/64, 0-06 o/S 1..74: 0.,//.4*1it 0.:2 17/71% 0.297" 0..12i/41. .0..74"/481 0.-212/1%: I 0.28S"o 0.89"/66V 0 184"/64% 0.-212V ,/:74!k J .0.474" 0 .1 3 I9"/38 0.233"/49% r(Top at stem) ..... K: "Thin cut at :bottom could not measure L Not decontaminated N 0.248. 0. 141"/57ý% 0.1.53 "/62% :o.1179/-72% N:*o -24 6;:. 0 .0 00"/[0 0.111."/4:5 o':209."/85* o 0.225" :0.047"/21 o .1.22/54- :0.225./10oo 0:.257" .067"/26% 0.143"/56% Q.225ý"*/io Maximum region with i00% through wall dealloying = 18% of circumference

Dealloy:.Analysiss. Surry SW.I Valves Measurements on Valve 1-SW-132 Section Wall T]Ac)knesO Damaged.Wall: (in. R)/% Damaged.

               . Centei Reg~ion                                                 ......

( ___in__ ).*.... LOcation .(): , Location.12) Location. (3) A- 1 12 0'0:0) 0.433"' 0.19*1.",/44V 0:. 22"/49V o.:194:, /45t A-2: (9:00) . 0,311" 0. 63"6/52 0.117"/57V :0.205,!'/60 B 77:00 ) .0.2s6" o ,.27,tso¥ 0.,88"/73% 0.226"/100% c (6::00) 0.227f! 0..15o"661 o.193 06' . 0..204./100t D .(5:00) 0.438" 0.iG6"/38% 0.190"/44% 0. 189"/43% (*0 5. .2 . 1 5 4.2 (4:OA 0..7~"0.10/4. 1.5;95~/816 06":/s9

 -F (13:00)               0.3211"               .0...236:"/74%        0:.219"/68%        . 0.228"/71%

G (12:05) 0 301" 0.186'=/62% 0..i98"/66% 0.206"/69.

• Maximum .region with 100% through. wall -dealloying = ::25t%.of circumference

Dealloy Analysis: Surry 'S.W Valves Measurements.

                                                .(2           ýon   Val4ve Diame~ter Vaive)       2 -SW- 132

Section Wall 'Thickness Damaged Wall. (ifn..)/. Damaged Cent.er Region

(*n. ") Ljocation (1) Locat ion. (2). Location (3) A (12:.:0. 0) 0.58.51. . 0. 1341"/23%: 0.156,/27% .0...!56:"./27% B (v00): B. :3*.o ..o).:: i*..* 0.... *2 , .:,! . . 321:1 !o..0 s s ,../ 7..* .. ..o0,15.4tý"4,8t 0.5"17%- ..*. .4*,,.l.-. 4.i. o ......,..-S 0'.l74ý"/54%-. C..(6:00) 0..51,8". .0.097"./1,9% ..'0 .:.137 /26%-t 0. 134. /26%

• D (9:.00.) 0:.:319,", 0.000o"/.o% 0.115-.1/36*% 0.06111/190 E (9:30)" . 0.."325" 0.093/29 0..13%i"/40% 0.068"/821%2 ..

  .No .region of the, circumference showed 100% through-wall dealloying..

Dealloy Analysis:. Surry S.w. Valves Measurements: on Valve: I-SW-117 "by.UT anid-Mechanical: Euipment Remaining Undealloved Wall Thickness Measurements (inches) Location (Circumference) _ Location Along Axis Froni Flange (Outlet)_.

                                                        /1:" !
                                                      .1/4"                1/2"              3/4"                            1"                1 1/2             1 3./4" U"T.:.                     0.269                0. 213.            0.2.04        .0.19.8         0.283                 0.2173            0..269

.......... .. Mechanical. 029. 0.276 0.29-5. 0.0 286 0:.259 'G01 77.. .0.265 2." U0..T.. " . .... 0.205 0.191 0.3 0..149 -0.126 Mechanical . .- .. 0.2 4. 0:..156 . ... 3.6 0. ,S5 0..096 3..:5" ..-. .. 'T. .. 76 0..263 o.-267 .. :.262*0'o. 25"0 0.278 . 0.27.372

 ...            _Mechanical                       - 0,..255              .0...260           0..265        :. 251          0.243                 0.271             0.274 "TaT..                          ...                                         -         0.102         10-107.         0.140                 0-.:124ý          0.113 Mechanical Me h    ni  a            .                     ----.-           .0:.,120        0:.113     .    .. 116       . ..... U-130:...30   '   0..94..:.

                                                                                       ýTFNS I IX TEVT RKSULTS.
                                                                                  ..    . ,         ,ZVAL.VE,        EWl.

SURRY. UNIXT 1, NIIRVICO WATri AWML-0'.l4 Tacit s~uvia '7"eo of. Sample  %.Dealloyed ana. Tonvi1a Viol1 .ocatfObe vifluai. Conjfirmation oi'%. dodi'loyed by.Virgivias of break A :Lccationa rcpp(Vad by outside strspgth: 'ýv 'I} ______ 3b.orVirginia P'ower ("nih, C

                                                                                                     *4 I   s        .     -Ronind R-4                tjane.                                        tip, I

_2__ . und RA4

                     'Po.1i~~h                 Vo*lleI                                                     4  Ili 34         _OK             yet)5.
                                                                                                                          ............... AST Si ,t etd.

Di. gou*id P.. 4 Ul..6f11 . Ii, fIpin .0K

                     .0.159" dini I ASTM Sid     Le~3e. e~rn'pI~

6

                 ?4:RectaIgulia RGff~i;Ar Z          nglr
                                 -ec UI     T Nono
                                               ;2"VrinaPwr
                                                                    *... f7 024.

5, 5641 q1]'#, S;

                                                                                                      ý4,0                   MF tflrioke. at

ý14 ld ilis; tenoi)e vpt Te~tersile Ave.

fnqh VA4

egh:sel?.*i samsple man -hAve -bont I -. tent .

0.02.. u 0 5 2~t4-. rn% y~a~ q. 23' v s to 9 C Rectonvular '7011 2~ or ~ Vail2,~30 fe. 10 M4 Rect~ngular 79% :12 51~i3 Nn~'n '0.0.0) FBIle iie~S ~-~~ 1p~r~~pl 024~~ 1 7outed meanaured f tiluia ye lave Matld N1 U otv 1% A, 14,9.4 D o .171 Pa. Ed Ye tma iot be menciur d )J ta Isr s x uts~e ia o.taide gag c'"tkgj

.12                                                                                                                        Oxtnua10%5,3   Yea.

13~ 14 Rcpglr 10%9~007 aitd,In YCGu au tIP.&e fractureep tenaila atrngth c=M Abe 0,240" It 038'ri.j u t cture Iccatiorn

ATTACHMENT 4 .Microbial Anaiysis* ofgCorros ion Nodules from Surry Se-rvice water Valve 1-SW-126: Vendoi" BTI

ATTACHMENT 3.. Tensile Test Results From Surfy Service Water. Valve: 1-SW,-J26 Aluminum Bronze Analysis

                                                                         ~p I A>  fX7 IMV~                       b~fL~~

111Inorpowtd ~

                                                                                             ..   .  . a November 29,; 1993 Innsbrook Technical Center 5000 Dominion Boulevard GlenAlln, .VA. 23060,

Dear Enclosed please find one copy of bur final report on The- Microscopic:

Analyses of a sluge samlpe: from the.Surry Electrical Power Pia.Service Water.System. !f you have any questions, pleaseifeel free,to contact me at.(800) 798-.4650. Thank you; for your continue.d.:intere.st in, Sincerely.., Enclosure /ssm

MICROSCOPIC ANALYSES OF A SLUDGE SAMPLE*F-ROM THE SURRY ELECTRICCAL POWER PLANT .SERVICE:.WATER SYSTEM Submitted to:: VIRGINIA POWER: Glen:Allen, Virginia By: BIOINOUSTRIAL TECHNOLOGIES, iNC. Gborgetown, Texas Incroidsrated November 29, 1.993,

INTRODUCTION On October 26 1993, :a sludge sa.pe, colected from the. s-rvic. vwater system of the Surry electrical power plant: was recvd~by Bioindustrial Technologies, Inc. (BTt) and given BTi control number 930427. of Virgnia Pow er requested. that microscopic analyses for total bacteria, using the fluores.Cein isothiocy.anate (FITC) method,. and sulfate-reduc.ng bacteria (SRB) using the.indirect fluorescent:antibody (SRB-IFA) method be performed.' Additionally, enumeration ý"of viabe ,bacteria using.the BTI MICKIT Ill, and screening for iron depositing bacteria was requested. Please. refer .to Appendix A for detailed methods. The sample-was collected on October. 15: and *shipped to BTI via .regular postal service at ambient temperature., Since the microbial: .constituents ca.n change significantly. over time in non-preserved samIples, it ;Should be notedtthat the results reported in these analyses may not represent the: in.situ: conditions.' A :portion-.of the sludge sample was weighed andridmade into slur'r'y in phosphate-buffered saine/.forma~dehyde solution, Equal portions of:the:.slurry were spotted on toxoplasmosis slides and stained. according to the referenced methods. The microbial ."couts were nornma)ized to number of cells per:gram f sludge..'

RESULTS, The results of the microscopic :analyses are shown .in the. follcwing tablei It should be noted that this methodtincludes both live and dead microbes..

BTI CONTROL NUMBERL, 930427ý

                                   ,.TOTA.L.

BACTEI/RM FITO ,ME`THOD _2 18.x 10" PRE'SUMPTIVE SR8/GRAM SRB-IFA METHOD..

                                                                     ý5.           0 J/   RON BAGTER1A.

SCREENING:: NON OBEVE B/G".A. .-I.. CTER:IA":: BA..TERNING.A>.. R~* '*; BA*CTERIA'G.R The results of vre-iable!: ___________NMB i Banayses

                              '.cultur        ~ i BACTERI. *.. .A are. . .shown    . in theifollo~wing    ..      K:

table. C "

                                                      .3            6 510          0.8.3, 1'0NON                8BSRVE     10
     '930427.                    8

_.31x 108 BTI CONTROL GENERAL GENERAL* ...SULFATE ACID NUMBER AEROBIC ANAEROBIC REDUCING. PRODUCING

COMMENTS Total Bacterial Count Both. rod6-shaped .and Cocci typ e bacteria were observed.: It should be ..noted, that these data.include both live and dead microbes. No filament.os. bacteria c6lohies: of the -type: associated with iron deposition were:observed. FITC-reactive polysaccharide (slime) was: observed}}