ML110070026

Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition

ML110070026
Person / Time
Site:	Waterford
Issue date:	01/04/2011
From:	Kowalewski J Entergy Nuclear South, Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1-2010-0089
Download: ML110070026 (24)

Text

Entergy Nuclear South Entergy Operations, Inc.17265 River Road Killona, LA 70057-3093 f Tel 504 739 6660 Fax 504 739 6678 ikowale@entergy.com Joseph A. Kowalewski Vice President, Operations Waterford 3 W3F1 -2010-0089 January 4, 2011 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition Waterford Steam Electric Station Unit 3 Docket No. 50-382 License No. NPF-38

REFERENCES:

1. W3F1-2010-0019, Technical Specification Table 3.4-1 Isolation Valve Addition, February 22, 2010.2. NRC Letter, Request for Additional Information Re: Technical Specification Table,3.4-1 Isolation Valve Addition, June 28, 2010.3. W3F1 -2010-0065, Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition, August 12, 2010.4. NRC, Request for Additional Information on the LAR to Revise TS 3.4-1 Isolation Valve Addition, October 28, 2010 [ADAMS Accession Number ML103010180].

Dear Sir or Madam:

In letter W3F1-2010-0019

[Reference 1], Entergy Operations, Inc. (Entergy) proposed a change to Waterford Steam Electric Station Unit 3 (Waterford

3) Technical Specifications (TS) Table 3.4-1 Isolation Valve Addition.During the submittal review process, the Nuclear Regulatory Commission (NRC)determined that a Request for Additional Information (RAI) was required [Reference 2].Letter W3F1-2010-0065

[Reference 3] submitted the additional information.

Letter W3F1-2010-0065 did not contain the requested Environmental Qualification (EQ)report due to the EQ reportnot being available at the time. The EQ report is contained A00(

W3F1-2010-0089 Page 2 in Attachment 2 to this letter. An additional RAI [Reference 4] was received and its response is included in Attachment 1.This letter contains no new commitments.

If you have any questions or require additional information, please contact William Steelman at 504-739-6685.

I declare under penalty of perjury that the foregoing is true and correct. Executed on January 4, 2011.Sincerely, Attachment 1: Response to Request for Additional Information Attachment 2: LPL-EQA-35.1 Qualification Test Summary I Similarity Analysis I Temperature Service W3F1-2010-0089 Page 3 cc: Mr. Elmo E. Collins, Jr.Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam Mail Stop O-07D1 Washington, DC 20555-0001 I

Attachment I to W3FI-2010-0089 Response to Request for Additional Information Attachment 1 to W3F1-2010-0089 Page 1 of 2 NRC REQUEST FOR ADDITIONAL INFORMATION In letter W3F1-2010-0019

[Reference 1], Entergy Operations, Inc. (Entergy) proposed a change to Waterford Steam Electric Station Unit 3 (Waterford

3) Technical Specifications (TS) Table 3.4-1 Isolation Valve Addition.

During the submittal review process, the Nuclear Regulatory Commission (NRC) determined that a Request for Additional Information (RAI) was required.

Letter W3FI-2010-0050

[Reference 2]submitted the additional information.

After NRC review of letter W3F1-2010-0050, additional information was determined to be needed and another RAI [Reference 3]was generated.

Letter W3F1-2010-0065

[Reference 4] submitted the additional information but W3F1-2010-0065 did not contain the requested Environmental Qualification (EQ) report due to the EQ report not being available at the time. The EQ report is contained in Attachment 2 to this'letter.

An additional RAI [Reference 4] was received and its response is provided below.The following provides the responses to the remaining Waterford 3 NRC RAIs.RAI 1 rReference 31 Letter W3F1 -2010-0050 RAI 6.b response -We need a summary of the licensee's EQ calculation.

All design information has to be completed before we can review the application.

The vendor should have these calculations ready.RAI 1 Response Attachment 2 contains LPL-EQA-35.1 which contains the Qualification Test Summary /Similarity Analysis / Temperature Service for solenoid valves SI-4052A (RC LOOP 2 SDC SUCTION INSIDE CONTAINMENT BYPASS ISOL) and SI-4052B (RC LOOP 1 SDC SUCTION INSIDE CONTAINMENT BYPASS ISOL) that will be installed under EC14765.Attachment 2 LPL-EQA-35.1 page Attachment XI.8 gives the report conclusions.

RAI 2 rReference 51 Please provide a summary evaluation of the impact of the proposed modification for the new solenoid valves on compliance with 10 CFR 50.63 Station Blackout.RAI 2 Response Station Blackout (SBO) evaluation for Waterford 3 was performed in accordance with 10CFR50.63 using the guidance in NUMARC 87-00 and Regulatory Guide 1.155. The plant specific evaluation for Waterford 3 demonstrates that equipment will be functional such that Waterford 3 can safely cope with an SBO for four hours. During the 4-hour SBO event, maintaining reactor core cooling for the plant is performed via natural circulation.

Shutdown cooling will only be initiated after the 4-hour SBO event.

Attachment 1 to W3FI-2010-0089 Page 2 of 2 SI-4052A(B) is required to support shutdown cooling only and is not needed for natural circulation.

Battery capacity calculations verified that the Class 1 E batteries have sufficient capacity to support station blackout for four hours. Offsite power or Emergency Diesel Generator is credited for restoration of AC power to the plant ending the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SBO event. Once AC power is restored, the safety related battery chargers provide DC power to the DC buses and loads.

REFERENCES:

1. W3F1-2010-0019, Technical Specification Table 3.4-1 Isolation Valve Addition, February 22, 2010.2. W3F1-2010-0050, Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition, June 8, 2010[ADAMS Accession Number ML101620417].

3. NRC Letter, Request for Additional Information Re: Technical Specification Table 3.4-1 Isolation Valve Addition, June 28, 2010.4. W3F1 -2010-0065, Response to Request for.Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition, August 12, 2010 [ADAMS Accession Number MLI102300177].

5. NRC, Request for Additional Information on the I2AR to Revise TS 3.4-1 Isolation Valve Addition, October 28, 2010 [ADAMS Accession Number ML103010180].

Attachment 2 to W3F1 -2010-0089 LPL-EQA-35.1 Qualification Test Summary I Similarity Analysis I Temperature Service Attachment 2 Contains 17 Pages LPL-EQA-35.01, Rev. 8 Attachment Xl Qualification Test Summary / Similarity Analysis / Temperature Service Condition Valcor Report MR526-6040-22-3 (Model V526-6040-22, P/N 214167301 for SI ISV4052A & SI ISV4052B)Attachment XI.)EC-14765 LPL-EQA-35.01, Rev. 8 Qualification Test Summary / Similarity Analysis / Temperature Service Condition Valcor Report MR526-6040-22-3 (Model V526-6040-22, P/N 214167301 for SI ISV4052A & SI ISV4052B)Test Sample Description The following Valcor Solenoid Valves were submitted for qualification testing.MIodel/Part No. Tag No. S/N Description V526-6180-1 0Q014-01-01-01 IQ Valcor 2", 1500# ASME U1, Class 2 pilot assisted, P/N 356136301 0Q014-01-01-02 2Q normally open, 2-way position indicating, DC voltage solenoid operated valve. The solenoid coil assembly is a Valcor P/N V52653-6042-1 rated at 180'C (Class H), 125 VDC continuous duty.The Model V526-6180-1 Solenoid Valve has a Class H 125 VDC coil which has an operating range of 100-140 VDC (no rectifier

& zener diode assembly is used). Electrical power to operate the valve is applied to the solenoid through a conduit port located on the side of the solenoid assembly.

The inrush and holding current is 1.5 amperes at 125 VDC & 70 'F. The valve de-energized position (fail position) is open;therefore the valve is energized to close. The disc assembly consists of a stellite which seals against an ASME SA-479 Type 316 hardface seat in the valve body. The test specimen contains 2 position indicating switches which are actuated by a magnet assembly that is attached to the plunger. The coil housing O-rings were constructed with silicone rubber. The assembly drawing for solenoid valve V526-6180-1 is shown on Dwg #356136301 (EMDRAC 5817-13985 shl) which is included in references (h) and (i).Solenoid Operated Valve V526-6180-1 was mounted and qualified in the stem-vertical position (QR 526-6180-1-1 section 3.6).Acceptance Criteria Pre- and Post Qualification Baseline Function Testing of serial numbers IQ & 2Q valves was performed by Valcor with satisfactory results. Excessive output leakage was observed on both test valves during a Pneumatic Disc Test. The leakage was documented and monitored without increase throughout qualification testing. The Pneumatic Disc Test was revised to be performed with water, vice air and both qualification valves exhibited leakage-within the required 50 cc/hr. The overall results are given below and can be found in QR 526-6180-1-1 Appendix F Sh. F l-2: Test Limits Pre-QualtTest-Results Post.Qual TestResults (IQ/2Q) (IQ/2Q)Dielectric (Solenoid) 2 mA MAX. 440 ýiA / 480 PiA 180 .tA / 200 [LA Dielectiic (Switches) 2 mA MAX. 280 1.A / 260 pA 100 pLA / 130 [LA Insulation Resistance 20 MQ MIN. >1 Ok MQ / >20k MNQ >20k MQ / >20k MQ (IR)-Solenoid I I ADD EC-14765 Attachment XI. 1 LPL-EQA-35.01, Rev. 8 Insulation Resistance 20 MQ MIN. >6k MQ >I Ok MQ >20k M >2 / >0k Mi0 (IR)-Switches Position Indication MUST INDICATE SAT /SAT MISSING SWITCH (Normal)Position Indication MUST INDICATE SAT / SAT SAT / SAT (Energized)

Hydrostatic Shell Test 4200 psig Water for NO LEAKS SAT / SAT SAT / SAT 15 rain.Hydrostatic Disc Test 4 CC/HR MAX.4100 psig Water for LEAKAGE .001 cc/min / .001 cc/min .01 cc/min / .005 cc/min 5 .ain.Pull-In Voltage 57 VDC MAX. 40 VDC / 40 VDC 37 VDC / 37 VDC Drop-Out Voltage 4 VDC MIN. 16 VDC / 11 VDC 15.8 VDC / 14 VDC Response Time Open/Close MAX. 16 msec. / 25 msec. N/A 2 sec 50.2 msec / 62 msec.EC- 14765 Radiation Aging Two model V526-6180-1 specimens (P/N OQO14-0 1-01-01 & OQOI14-01-01-02) were sequentially radiation aged in the beginning of the qualification programn based on the results of testing by the Nuclear Regulatory Commission (NRC) and reported by Sandia Laboratories in report SAND 79-0924C.

Radiation exposure was performed by Steris-Isomedix Services under guidelines specified by Valcor. The test specimens were exposed for 106 hours0.00123 days <br />0.0294 hours <br />1.752645e-4 weeks <br />4.0333e-5 months <br /> to a Cobalt-60 gamma source and received a minimum total integrated radiation dose of 93.6 Mrads (9.36E+7) gamma with no anomalies and no degradation of non-metallics noted (QR 526-61 80-1-1 section 3.13.3). The valve's performance characteristics (pull-in, drop-out, and leakage tests) were measured satisfactorily before and after the radiation exposure.Thermal Aging First a Heat Rise Test (Reference QR 526-6180-1-1 Appendix D) was performed in order to determine the maximum stabilized solenoid and o-ring temperatures that occur when the solenoid is continuously energized in its maximum operating ambient temperature.

A total often thennocouples were installed as close as practical to the o-ring seals. The coil temperature was calculated based on the measurement of current changes. The fuilly instrumented test valves were mounted onto a steel plate to simulate actual mounting and heat transfer conditions.

These assemblies were mounted in the chamber oriented with the valves in a vertical position, solenoid above the valve bodies, and on a I-inch thick insulation board on the floor of the chamber. All thermocouples were connected to a temperature recorder and additional instrumentation to measure the applied voltage and current during the test. The test valve temperature was stabilized at 1 30°F with test fluid supplied to the valve at 306'F. A voltage of 125VDC was applied to the valve and the baseline current was measured.

When thermal stabilization was reached, which is the point when the current did not change more than I mA in a I-hour period, the current flow in the solenoid was measured.

The coil winding temperature was calculated in accordance with the following equation: Attachment XI.2 IF 0.00218)T EC-14765 Where: T Calculated Coil Temperature:

317.9°F IA Current Flow at Ambient Temperature (1.32562 Amps)IF = Current Flow at Stabilized Temperature (0.94059 Amps)TA = Ambient Temperature (130.6°F)0,00218 Temperature Coefficient, Ohm/Ohm-°F The thermal aging of the V526-61 80-1 solenoid valves was performned to simulate~the effects of a 40-year design life plus accident, except for elastomers and non-metallic items, which were qualified for a mininum of 10-year life plus accident.

Following the Heat Rise Test, the measured temperatures were used to determine the thermal aging times of the various test specimen components.

The final thermocouple temperatures became the Actual Part Operating Temperatures that were used to calculate qualified life. The solenoid coil shell assembly was thermally aged 690 hours0.00799 days <br />0.192 hours <br />0.00114 weeks <br />2.62545e-4 months <br /> @ 41 5F (Reference QR 526-6180-1-1, Appendix D, Figure 1). The limiting components in' the coil shell assembly are the Coil Magnet Wire, Coil Insulation, and Coil Lead Wire, which received an effective qualified life of 40.52 years. These three components had the lowest activation energy (eV) with a value of 2.096eV.The coil materials of construction are identified in QR 526-6180-1-1 Appendix D, Figure 1 as: PART MATERIAL ACTIVATION ENERGY (eV)Coil Magnet Wire Polyimide 2.096 Coil Insulation Kapton 2.096 Insulating Tape Fiberglass 2.156 Epoxy Potting Stycast #2651 2.126 Coil Lead Wire Kapton 2.096 The silicone o-rings, an elastomer, with activation energy of 1. 150 eV were tested as part of a Coil-Shell Assembly test fixture which included an Electrical Conduit Seal Assembly (ECSA) connector manufactured by EGS attached to the solenoid housing. The o-rings received an effective qualified life of 15.64 years. The o-rings were thermally aged 855 hours0.0099 days <br />0.238 hours <br />0.00141 weeks <br />3.253275e-4 months <br /> @ 280'F (Reference QR 526-6180-1-1, Appendix D, Figure 2).Cycle Aging During Thermal Aging, Phase I of Cycle Aging was performed.

Solenoid Operated Valve V526-6-i-80-tI was cycled 8,289 times successfully (Reference QR 526.6180-1

-1 section 3.13.4). The test specimens were cycled with 60 psig water at 125 VDC at a rate that did not exceed 10 cycles per minute.Post-Thermal/Cycle Aging test results complied with test requirements and can be found in QR 526-6180-1-1 Appendix F, sheets 54 and 55. Test results are listed below: Attachment XI.3 LPL-EQA-35.01, Rev. 8 Test Post-Thermal/Cycle Aging Test Data 0Q014-01-01-01

/0Q0 14-01-01-02 Apply Voltage'to Solenoid Operator 125.418 / 125.072 VDC Apply Pressure to Pressure Port 'A' 60.0 psig Pull-In Voltage (Avg.) 43.340 / 54.146 VDC Drop-Out Voltage (Avg.) 15.494 / 23.206 VDC Leak Test 0.5 sccm / 0.4 sccm EC-14765 Phase 11 of Cycle Aging was perfonned following Hot Cyclic Testing. An additional 8,250 cycles during Phase It Cycle Aging of the valve was performed at ambient temperaturel The valve was cycled with 60 psig water a rate not exceeding 10 cycles per minute energizing the coil with 125 VDC. Operation of the valve was confirmed by the valve shuttling and water issuing from the outlet port when the valve is energized as well as observation of the position indication switches.Seismic Testing Complete successful seismic qualification testing is documented in QR 526-6180-1-1, Appendix F, Test report pages 091-189. A Resonance Search Test was performed within the range of 1 -100Hz. A Vibration Aging Test was perfonned and tag numbers OQO14-01-01-01 and OQO14-01-01-02 were subjected to an amplitude of 0.75g over the frequency range of 5 Hz to 100 Hz to 5 Hz at a sweep rate of 2 octaves per minute for a minimum of 90 minutes in each orthogonal axis (see QR 526-6180-1-1, Appendix F pages96-108). The SRV Alone Test was performed following Vibration Aging. Contact chatter was monitored throughout testing. Operability was monitored satisfactorily at 1, 5, 10 and 15 minutes during testing. An Operational Basis Earthquake (OBE) plus SRV excitations was performed in each of the X-Y and Z-Y directions using the Required Response Spectrum (RRS) method. The valve was cycled satisfactorily twice and operability was verified by a burst of flow from the outlet port. Safe Shutdown earthquake (SSE" in addition to SRV and LOCA excitations was also performed.

Post Seismic functional test results complied with test requirements and can be found in QR 526-6180-1-1 Appendix F, sheets 79 and 80. Test results are listed below: Test Post Seismic Results 0Q014-01-01-01

/_0Q014-01-01-02

_Apply Vol-tage-to Solenroid

...... 1.25.6. ,...VDC Operator Pull-In Voltage (Avg.) 39.4 / 46.13 VDC Drop-Out Voltage (Avg.) 19.87 / 19.56 VDC Leak Test .01 scfm / 5.2 scem Attachment XI.4 LPL-EQA-35.01, Rev. 8 LOCA TestAinD EC-14765 Valcor model V52600-6042-1 A was used to demonstrate, based on similarity, that LOCA requirements are exceeded (see MR526-6040-22-3 section 4.1.4). Two Valcor model V52600-6042-lA valves were exposed to a 30 day LOCA/MSLB test in which two initial transients were used. The first transient obtained a peak temperature/pressure of 413'F/73.7 psig in 31 seconds and the second transient obtained a peak temperature/pressure of445°F/64 psig in 17.5 seconds. Chemical spray consisting of 3000 ppm boron pH of 11.5 adjusted with sodium hydroxide was applied during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of testing at a rate of 0.15 gpm/ft2 (see Attachment X). The valves were successfully operated at nominal voltage, minimum voltage and maximum voltage throughout the LOCA/MSLB test.The valves that are installed in containment have an electrical Quick Disconnect connector manufactured-by EGS (QualTech NP) attached to the solenoid housing which prevents moisture/water from penetrating into instrument housings, junction boxes or the solenoid coil. The qualified connector is a 3/4" N.P.T., quick disconnect, 10 pin bayonet style with connector field wiring consisting of 16 AWG, Rockbestos, Firewall III SIS cable.It is assumed per calculation ECS04-013, Small Break Loss of Coolant Accident (SBLOCA) Alternative Source Term (AST) Radiological Dose Consequences for 3716 MWt Extended Power Uprate (EPU) that the plant is placed on Shutdown Cooling and secondary releases through the ADV's are stopped at a time of 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The SI-4052A and SI-4052B solenoid valves, normally de-energized and closed,,will be required for a very short duration (approx. 7-8 minutes maximum while placing SDC into service).

The function while energized is to open to equalize the SDC pressure across SI-405A and SI-405B. Once the pressure is equalized and SI-405A & SI-405B commence to open, the equalization solenoid valves can close.It has been determined that the Valcor model V526-6040-22 is qualified for a LOCA/MSLB event at Waterford 3 based on similarity of construction and LOCA testing for qualification test sample V52600-6042-1A exceeding the plant requirements as shown with the superimposed LOCA temperature and pressure curves found in Appendix Ill of MR526-6040-22-3.

Comparisons of the LOCA/MSLB Test Temperature and Pressure Profiles for Report QR526-6042-IA can also be found in this EQA (see Fig 4a& 4b).Final Inspection The test specimens were visually inspected at Trentec (testing facility) for evidence of damage, deterioration or deformation that might hinder proper valve operation.

The final inspection was satisfactory and the results can be found in QR 526-6180-I

-1, Appendix F on Page 011. All the lead wires were brittle, which was expected as they were effectively 40 years old (minimum).

Attachment XI.5 (LPL-EOA-35.01.

Rev. 8 Sirnilarity Analysis Table I Valve Similarities Valve Model Nominal Type Seal Body Bonnet Flow Pressure Design No. Size (in) Material Material Material Capacity Class Temp (*F)(Cv) (Notel)(Min)V526-6040-22 3/4 Pilot Stellite 6B ASNME ASME 4.0 1680 650 (Installed at Operated SAI82 -SA479 -WF3 SI-4052A Grade Type 316& B) F316 V526-6180-1 2 Pilot Stellite 6B ASME ASME 10.0 1500 576 (Test Valve) Operated SA516 -SA479 -Grade 70 Type XM- 19 V526-6042-IA I Pilot Stellite 6B ASME ASME 2.0 2500 680 (Test Valve -Operated SA240 -SA479 -LOCA) Type Type 316 1 316 EC-14765 Notes: 1. All valves have body nozzles that are Class 2500 cfpable. Only the nozzle bores and weld end preparations vary with changes in nominal size per MR526-6040-22-3 section 4.0.Table II C__ omparison oNon-Metallic Parts Valve Valve Valve Part Name V526-6040-22 V526-6180-1 V526-6042-IA Part Number Part Number Part Number Coil-Shell Assembly V52653-6042-I V52653-6042-1 V52653-6042-I Switch Assembly S1140-6-1

& S 1140-6-5 S1140-6-1 S1140-6-1 Terminal block S1140-14-6

& S1140-14-7 S1140-14-6

& S1140 S1140-14-6

&7 S1140-14-7 Leadwire (QDC/ECSA)

V 135-245 V 135-227 S 1140-36-14 (Part of QDC/ECSA) (Part of QDC/ECSA) (Part of QDC/ECSA)Electrical Connection Seal N/A N/A S101BD25 Leadwire (Bracket Terminal S 1349-2 S1349-2 S1349-2 Block Assembly)leadwire (Switch Assembly)

S1517-2 S1517-2 SI1517-2 O-Ring (Co.er tolfo usg)- ..s0-.S56............-S-lOIC-S+--50

............. .l.O.. $1 !O-Ring (Housing to Coil SIO1CS156 S101CS156 N/A Shell)Packing t O-Ring (Coil Shell S1140-49-1

& S1140-49-2 S1140-49-1

& S 1140 SI 140-49-1 & S1140-to Bonnet) 2 49-2 1,,tI Seal (Body to Bonnet) V52618-6t02-12 (K-Seal) V52618-6102-12 (K-Seal) Seal Weld Seal Metallic Disc/Seal Metallic Disc/Seal Metallic Disc/Seal Attaclunent XI.6-I 1LPL-EQA-35.01, Rev. 8 Valve Valve Valve Part Name V526-6040-22 V526-6180-1 V526-6042-1A Part Number Part Number Part Number Zener Diode NA S1 140-9-1 S 1140-9-1 Rectifier NiA N/A S1 140-8-1 Heat Shrink Tubing (Switch S1318-5 & S1318-3 S13185 & S1318-3 S1318-5 & S1318-3 Assembly)Protective Tubing (Switch S1325-2 S1325-2 S1325-2 Assemblv)Notes: 1. Per QR 526-6042-i A, the P/N V52600-6042-1 A qualification test valves were modified to change: 1)the o-ring compounds from EPR to silicone, and 2) the o-ring seal at the solenoid/bonnet in terface was EC-14765 replaced by a graphite seal. The o-ring material and graphite seal changes were made based upon thermal test data.The basis for similarity is discussed below: " The coil shell assemblies, P/N V52653-6042-1, used in the construction of the Valcor solenoid valves model V526-6040-22 installed at W3 for RC Loops I & 2 SDC Pressure Equalization

/ Containment Isolation Lines (SI ISV4052A & SI ISV4052B) are identical to the tested Valcor Solenoid Valve Model V526-6180-1 (See Ref, i -Section 4.1). As can be seen from Table II above, non metallic materials used in the solenoid construction of the above two valves including the Terminal Block, Leadwire, (Bracket Terminal Block Assembly / Switch Assembly), O-Ring (Cover to Housing / Housing to Coil Shell, Heat Shrink and Protective Tubing are all identical between the two SOV valves.* The differences in the solenoid valves include four position indicating switches in the model V526-* 6040-22 to two switches in the tested model V526-6180-1, however the switches are the same part number, P/N S1140-6-1.

The valve installed at Waterford 3 has a P/N S 1140-6-5 switch assembly, which is made of the same material as the S 1140-6-1, only has a different sensitivity.

The electrical connections are both made by EGS (QualTech NP) with similar materials (See Ref. i -Sections 3.1 and 4.1. 1). A zener diode which is not applicable in the model V526-6040-22 was included in the Thermal Aging Testing and LOCA testing test valves. The electrical portion was tested and qualified per Ref. h and the above noted differences will have no affect on qualification.

• The metallic materials of construction are not affected by thermal aging or radiation exposure, however they can be affected by LOCA chemical spray and saturated steam environments if they are not inherently corrosion resistant.

The ASME SA-516 Grade 70 Body on the model V526-6 180-1 has been coated to prevent corrosion.

The only other metallic item exposed to LOCA environment is the solenoid coil shell that is gray iron plated with nickel on both the tested and Waterford 3 installed valves. The materials on the model V526-6180-1 valve successfully completed LOCA test without incuring any corrosion on any metallic components (See Ref, i -Section 4. 1. 1. 1). The electrical

-..portion was tested and qualified per Ref. h and 'Metallic differences will have no affect on qualification.

• The assemblies of the tested and installed Waterford 3 valves are similar except variations in size and seal disc configuration, which is due to flow, temperature and pressure ratings as shown in Table I above. The model V526-6040-22 is designed as Normally Closed while the tested model V526-6180-1 Attachment XI.7 LPL-EQA-35.01, Rev. 8 is Normally Open. The design and fabrication of'both assemblies are in accordance with the requirements of the ASME Boiler and Pressure Vessel Code Section 111. The variation in nominal size EC-14765 and Normally Open/Closed configurations have a negligible effect on seismic qualification since only the bore of the body nozzle varies with the change in nominal size. Both valves have body nozzle diameters that are suitable for a Pressure temperature rating of Class 2500. However, the bore is defined depending on the nominal size required (See Ref. i -Section 4.2.3).* A detailed similarity evaluation was performed by Valcor (Ref h & i).Conclusion" The material, design and construction between the Valcor V526-6040-22 and the V526-6180-1 and V526-60402-I A are similar as indicated in reports MR526-6040-22-3 and QR526-6180-1-1.

The differences in valve body materials, valve size, valve rating or flow capacity are metallic differences only. This will have no affect on qualification." The Waterford 3 combined normal plus accident radiation environment is 3.33 1 E+7 gamma (see Section II) and Valcor radiation aged successfully the solenoid valves to 9.36E+7 gamma with no anomalies and no degradation noted, therefore the valves have demonstrated a qualification level of 2.8 1 times above the requirement.

• The solenoid assembly and 0-ring seals are of the same materials and method of manufacture as the solenoid assemblies and o-ring seals qualified for 40 years in QR526-6180-l-1.

Other seals have identical metallic materials which are unaffected by thermal and radiation aging.* Valcor successfully cycled the valves 8,289 times during thermal aging which significantly exceeds the I cycle every 18 month requirement while entering shutdown cooling (See Ref. i -Section 4.2.4)." Based on qualification test reports QR 526-6180-1-1, QR 526-6042-1, similarities presented in MR 526-6040-22 and discussion above, the following SOV is qualified for service at Waterford 3 in SDC lines (SI-4052A

& SI-4052B).

Model No. Part No. EMDRAC Dwg V526-6040-22 214167301 5817-13985 shl The qualified life on the valve subassembly (V52660-6040-22) is 40 years. The qualified life of the valve solenoid assembly (Vl 05-394-21'-14) is 40 years-with the exception of the O-rings. The qualified life of the Solenoid Assembly O-rings is 10 years.Attachment XI.8 LPL-EQA-35.01, Rev. 8 perature Service Condition

-(SI ISV4052A & Sl ISV4052B)Normally de-energized (NCFCND) inside RCB with fluid (water)= 300'F I EC-14765 Conip ID Status Fluid External Internal SI ISV4052A DEEN WATER 120F / 414°F 300°F / 400°F SI ISV4052B DEEN WATER 120°F / 414°F 300°F / 400°F These two SOVs are located in the RCB and are normally closed in the de-energized position.

These SOVs create a bypass around the Valve SI-405A(B) to minimize the void formed during the operation cycle downstream of SI-405A(B) before SI-405A(B) is opened during shutdown cooling operation.

The valves will also function as containment isolation.

The new solenoid valve, SI-4052A(B), will be opened for approximately 7 minutes before opening SI-405A(B). This sequence will allow RCS water from upstream of SI-405A(B) to compress the void between SI-405A(B) and SI-407A(B) before SI-405A(B) is opened; thus minimizing a pressure transient when SI-405A(B) is opened. N Based on a conservative energization time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> every 18 months, the following energized percentage times can be calculated:

Valve de-energized

-99.8%Valve energized

-0.2%Since the model V526-6040-22 is a pilot-operated SOV which uses the process fluid to assist in valve positioning, its coil generates less heat than equivalently sized direct-acting SOVs. The valve is a hard-seated solenoid valve with position indication.

During normal plant operation the valve will be de-energized (no voltage applied to the solenoid) and the main seal, consisting of a disc assembly, which seals against a metal seat in the body isolates the outlet port from the inlet port. Since the valves are infrequently energized and for short periods of time, no significant self heating will occur.Valcor has calculated a coil temperature of 31 8°F based on a heat rise of 12'F as indicated during a heat rise test performed (QR526-6180-1-1 Appendix 'D'). The valve was continuously energized with 125 VDC, operated in an ambient temperature of 130'F and supplied with a fluid (water) temperature of 306'F.A conservative service temperature (solenoid coil temperature) of 400'F (including 350'F SDC temperature

+ heat rise + additional margin) is~used to calculate qualified life while the valve is energized based on shutdown cooling entry temperature of 350'F plus I 2"F heat rise plus 10% margin. DC-powered solenoid valves may experience higher voltage when the station batteries are being maintained or charged.Float voltage levels are typically around 132 VDC and the equalizing voltage can be as high as 140 VDC fdF-Si-25NVDt syI ti Inreasn-g tlTe-vItage re r-hCeunent

-.additional ohmic heating. This effect is considered in the margin included for the service temperature.

During periods while SI-4052A(B) will be closed (de-energized) and isolated from the RCS during normal plant operations, the service temperature is conservatively assumed to he 300°F. This temperature was Attachment XI.9 LPL-EQA-35.01.

Rev. 8 ,chosen based on containment ambient temperaiture of I 20°F plus some allowaiice for sonic nior seat leakac4e 111- L,111h 1 SI-401 A( B).The service temperature of the elastoniers, 0-rings being ithe life limiting component, vwg. 2l4167301 items 27 lnd 43) is calculated based on thienrmocouple temperatures that were recorded:

during the heat rise test and shown below in Figure "A". The service temperatures for the O-iinus are much. lower based oin the eliastomer location within the valve aid the thermal conduction paths from the coil. The locations are depicted below as therniocouple locations 1-4. A conservative service temperature chosen ibr the. 0-rings is 240'F while the valve is open and I 80F while the valve is closed./ri'..'.rt A: I'i,: R~se r'ct Ihi rmroc Por;,iliofl 3nd In'in. Ic~ig~ij, l.Ii : EC-1.4765 I t.- A ." ?,":.. ".41 ,, 0..j :;. ... .ji -, ' *':? : i"' ./ "'2:: [ .............................

' q :--] : :...~. '... 1" [~ ~ ~ ~~ i'tr:;; :.: f ....' .

' .;: ..: ! ! J, 4! ...ý- T AoX.I X.,i C,-D Attachment XI. 10.

RCM TECHNOLOGIES Qualified Life Manual Calculation Report, Page 1 SYSTEM 1000 REVISION 16 December 09, 2010 17:08 QUALIFIED LIFE CALCULATION Item

Description:

V526-6040-22:

SI-4052A(B)

Solenoid Coil CALCULATION INPUTS Activation Energy: 2.096 SERVICE CONDITIONS Service Temperature 400F 300F AGING CONDITIONS Aqinq Temperature 212.78C Percent of Service Life 0.2%99.8%Aging Time 690 Hours CALCULATION RESULTS: 58.6746 Years Prepared By: Reviewed By:n Date: I 4 I 1 0 Date:_ 1r,2_'7'6 E C.- +7 (e"R .z a RCM TECHNOLOGIES SYSTEM 1000 REVISION 16 Qualified Life Manual Calculation Report, Page 1 December 09, 2010 17:06 QUALIFIED LIFE CALCULATION Item

Description:

V526-6040-22:

SI-4052A(B) 0-rings CALCULATION INPUTS Activation Energy: 1.15 SERVICE CONDITIONS Service Temperature Percent of Service Life 240F 0.2%180F 99.8%AGING CONDITIONS Apging Temperature Aping Time 280F 855 Hours CALCULATION RESULTS: 14.9875 Years Prepared By: j Date: I _Lj Reviewed By: Date: ,')(I Ec- i47(,s-n. 2 +

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811113* 0301303111 0311 Rpm1 M40. LOU 1004.710A YALoIO3Jf0 11130*V6) 7413 l0443 El 4*1 40330 101 340303 (0 10*8 FIN1 W.601 SOLNO NsA.31..4I0 AS APPLIIA31L ELECTRICAL SCHk.MATIC0484*

3 CAN DI DATE VALVE L rPmo / VALCOR INGINmaEIUNG COPPORi , ,,, ..... 40 .00 ,,, ,. ,1-.MR526-6040C-22-3 ua. -8040-u-* =, 0 --rktS o, , t, .r.or ,,.. " ....-a .... .00 1 .0130 APPENDIXII4870

-~~~~~~ 2141673010)40

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U ~ t5 1T 44*" Sw=01 vCT4.* C tt 31N-mv TA E 1. NUCLEAR HARDWARE STANOPRDII7 ED VUC ki.Utt POWEP. PuJlt vism 05J--V 0 -5.-Xv-MR52&6064 P ARE NT VALVE AIPPENDIX 4A I4I 'M~~~31 -A 04 4 ~Wl t 5==i=4 FOR REFEREIJqCE OkJL, ,SIP1o 2010 I~K 5 OC~' tSCICJE ~ X~L~!SX~V~5~-5-*1~a-i-~C1 j.fift--ý ý- .11 -I A 0-11 4==ý= L -VALCOR ENGINEERING CORPORATION IA-AS. tc-A4 %Ci*O L EPEAO1455 Z-0 LB so t4o..22-3 AI.5Al A D247VZaOO4-A

.SHEET All-V.I.4 PS LPL-EQA-35.01, Rev. 8 FIGURE 4a: LOCA/MSLB Comparision Profiles (Reference F: Report QR526-6042-1A)

Reference Calculation EC-S90-014-ROI S I-500 450 400 350 300 250 200 150 100 50 0 W3 Profile-Test Profile 46.3 days 10 100 1000 10000 Time -Seconds 100000 1000000 10000000 100000000 FIGURE 4b: LOCAJMSLB Comparision Profiles (Reference F: Report QR526-6042-IA) 0I 0.80 70 60 50 40 30 20 10 0.- W3 Profile Test Profile 1 10 100 1000 Timie- -- Secon-d s-10000 100000 1000000 40