Test Plan for Qualification of EA170-XX302 Series Limit Switches for Use in Nuclear Power Plants in Compliance W/Ieee Stds 323-74,382-72 & 344-75,for Outside of Containment Only.ML20050C863 |
Person / Time |
---|
Site: |
Sequoyah |
---|
Issue date: |
11/02/1979 |
---|
From: |
NAMCO |
---|
To: |
|
---|
Shared Package |
---|
ML20050C841 |
List: |
---|
References |
---|
RTR-NUREG-0588, RTR-NUREG-588 IEB-79-01B, IEB-79-1B, LP10767-2, NUDOCS 8204090423 |
Download: ML20050C863 (10) |
|
|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F9701999-10-14014 October 1999 Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections ML20217E4301999-10-12012 October 1999 Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations ML20211M7341999-08-30030 August 1999 Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times ML20211K1721999-08-30030 August 1999 Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves ML20209B7731999-06-30030 June 1999 Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196F2211999-06-24024 June 1999 Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20196G4701999-06-24024 June 1999 Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196G7961999-06-22022 June 1999 Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators ML20196G8071999-06-22022 June 1999 Revs to Technical Requirements Manual ML20195E9841999-06-0707 June 1999 Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1611999-04-29029 April 1999 Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20206E1391999-04-29029 April 1999 Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations ML20204E8501999-03-21021 March 1999 Plant,Four Yr Simulator Test Rept for Period Ending 990321 ML20204H4081999-03-19019 March 1999 Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual ML20199K6001999-01-15015 January 1999 Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection ML20195H6111998-11-16016 November 1998 Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting ML20154H7251998-10-0808 October 1998 Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1091998-08-27027 August 1998 Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F3001998-08-27027 August 1998 Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs ML20209J1631998-08-0707 August 1998 Rev 41 to Sequoyah Nuclear Plant Odcm ML20236G5961998-06-29029 June 1998 Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions ML20249C6371998-06-26026 June 1998 Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248F0051998-05-28028 May 1998 Proposed Tech Specs for Section 6, Administrative Controls Deletions ML20217N3511998-04-30030 April 1998 Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1681998-02-25025 February 1998 Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J6961998-02-13013 February 1998 Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20202J7601998-02-13013 February 1998 Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements ML20198T4311998-01-21021 January 1998 Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization ML20199F8231997-11-30030 November 1997 Cycle 9 Restart Physics Test Summary, for 971011-971130 ML20199K4571997-11-21021 November 1997 Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3191997-09-17017 September 1997 Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20203B9731997-08-0505 August 1997 Rev 1 to RD-466, Test & Calculated Results Pressure Locking ML20217J5581997-07-31031 July 1997 Cycle Restart Physics Test Summary, for Jul 1997 ML20210J1671997-04-30030 April 1997 Snp Unit 1 Cycle 8 Refueling Outage Mar-Apr 1997,Results of SG Tube ISI as Required by TS Section 4.4.5.5.b & Results of Alternate Plugging Criteria Implementation as Required by Commitment from TS License Condition 2C(9)(d) ML20137T0871997-04-0909 April 1997 Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria ML20137M8581997-04-0101 April 1997 Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits ML20137C8421997-03-19019 March 1997 Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel ML20136J0381997-03-13013 March 1997 Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks ML20134P8631997-02-14014 February 1997 Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b ML20134K9981997-02-0707 February 1997 Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs ML20138F2581997-01-17017 January 1997 Rev 39 to Sequoyah Nuclear Plant Odcm ML20134L9261996-11-0808 November 1996 Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable ML20129D2661996-10-18018 October 1996 Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units ML20129G7301996-09-26026 September 1996 Proposed Tech Specs 3/4.3.3 Re Fire Detection instrumentation,3/4.7.11 Re Fire Suppression Systems & 3/4.7.12 Re Fire Protection Penetrations ML20134J9991996-09-23023 September 1996 Fuel Assembly Insp Program 1999-08-30
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20196G8071999-06-22022 June 1999 Revs to Technical Requirements Manual ML20209J1631998-08-0707 August 1998 Rev 41 to Sequoyah Nuclear Plant Odcm ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20138F2581997-01-17017 January 1997 Rev 39 to Sequoyah Nuclear Plant Odcm ML20134J9991996-09-23023 September 1996 Fuel Assembly Insp Program ML20138F2531996-02-23023 February 1996 Rev 38 to Sequoyah Nuclear Plant Odcm ML20108B4121995-11-0303 November 1995 Rev 37 to Sequoyah Nuclear Plant Odcm ML20094Q2301995-10-30030 October 1995 ASME ISI Valve Testing Program Basis Document, Rev 0 ML20094Q1931995-10-30030 October 1995 Rev 1 to ASME Sys Pressure Testing Program Basis Document ML20094Q1971995-10-30030 October 1995 Rev 1 to SG Tubing ISI & Augmented Insps, Rev 1 to 0-SI-SXI-068-114.2 ML20094Q2111995-10-30030 October 1995 Rev 1 to ASME ISI Pump Testing Program Basis Document ML20094Q1761995-10-13013 October 1995 ASME Section XI Isi/Nde & Augmented Nondestructive Exam Programs, SSP-6.10,rev 2 ML20094Q1841995-10-13013 October 1995 ASME Section XI Isi/Nde Program Units 1 & 2, Rev 0 to 0-SI-DXI-000-114.2 ML20149L6811994-09-30030 September 1994 Concerns Resolution Program - Sequoyah Nuclear Plant ML20063D6691994-01-24024 January 1994 Rev 4 to Sequoyah Nuclear Plant Restart Plan ML20065Q6251993-10-13013 October 1993 Rev 31 to Sequoyah Nuclear Plant Odcm ML20056F3181993-08-20020 August 1993 Rev 0 of Post-Restart Plan ML20056G1841993-08-10010 August 1993 Rev 2 to Sequoyah Nuclear Plant Restart Plan ML20044F3081993-05-20020 May 1993 Rev 0 to Sequoyah Nuclear Plant Restart Plan. ML18036B1961993-01-27027 January 1993 Rev 2 to Nuclear Power Training Procedure TRN-31, Fire Brigade Training. ML20127P5461992-12-16016 December 1992 Rev 20 to Surveillance Instruction SI-114.1, ASME Section XI ISI Program,Unit 1 ML20127P6361992-12-16016 December 1992 Rev 19 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program,Unit 2 ML20114C8131992-04-17017 April 1992 Rev 27 to Odcm ML20101F2081992-02-0808 February 1992 Rev 16 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program Unit 2 ML20101F2011992-02-0808 February 1992 Rev 17 to Surveillance Instruction SI-114.1, ASME Section XI ISI Program Unit 1 ML19332D2241989-09-22022 September 1989 Rev 23 to Odcm. ML20245H1421989-08-15015 August 1989 Rev 22 to Offsite Dose Calculation Manual Changes ML20246H4861989-05-16016 May 1989 Rev 1 to Technical Instruction TI-115, Instructions for Sewage Mgt ML20244E2521989-04-28028 April 1989 Rev 14 to Surveillance Instruction SI-114.2, ASME Section XI Inservice Insp Program ML20246E7771989-04-25025 April 1989 Rev 14 to Surveillance Instruction SI-114.1, ASME Section XI Inservice Insp Program ML20206D3421988-10-15015 October 1988 Rev 13 to Surveillance Instruction SI-114.2, Inservice Insp Program ML20154J3221988-09-0909 September 1988 Procedure EA-OR-003-S, Sequoyah Nuclear Plant - Unit 1 Design Baseline & Verification Program,Supplemental Engineering Assurance Oversight Review Rept ML20150F9291988-06-17017 June 1988 Diesel Generator Voltage Response Improvement Plan ML20154L1421988-05-0909 May 1988 Rev 3 to Revised Sequoyah Nuclear Performance Plan ML20153H3891988-03-30030 March 1988 Rev 19 to Sequoyah Nuclear Plant Offsite Dose Calculation Manual ML20196G3301988-02-24024 February 1988 Limited Test Program for Determining Axial Load Capacity of Cast One-Hole Conduit Clamps ML20147E9511988-01-21021 January 1988 Revised, Procedures Generation Package ML20153H3851988-01-0505 January 1988 Rev 18 to Sequoyah Nuclear Plant Offsite Dose Calculation Manual ML20147E5691987-12-17017 December 1987 Rev 4 to Special Maint Instruction SMI-0-317-61, Instrumentation Features Walkdown,Rework & Insp Instructions for CAR 87-014 ML20237C5451987-10-28028 October 1987 Rev 17 to Offsite Dose Calculation Manual ML20236E6931987-10-17017 October 1987 Rev 2 to Engineering Organization & Operating Procedures, TVA Employee Concerns Special Program ML20235X0551987-10-10010 October 1987 Rev 0 to Sys Operating Instruction SOI-74.2, Removal of RHR for Repair of 2-FCV-74-2 ML20235X0651987-10-10010 October 1987 Rev 0 to Special Maint Instruction SMI-2-74-1, Repair of 2-FCV-74-2 ML20237H2051987-08-28028 August 1987 Rev 0 to Civil Engineering Branch Instruction CEB-CI 21.89, Mod Priorities for Pipe Supports on Rigorously Analyzed Category I Piping - Sequoyah Unit 2 ML20207G5821987-08-24024 August 1987 Rev 14, Balance of Plant Temp Monitoring Sys ML20237L3651987-08-21021 August 1987 Unit 2,Regeneration of Support Design Calculations on Rigorously Analyzed Piping,Program Plan ML20236Q1771987-08-0707 August 1987 Rev 9 to Surveillance Instruction SI-114.1, ASME Section XI Inservice Insp Program. Rev Corrects Deficiencies Shown in Caqr CH5870006 & CH5870010,adds Punchlist & Incorporates Icf 87-708 ML20236N7601987-08-0606 August 1987 Revised Radiological Emergency Plan Implementing Procedures, Including Rev 13 to IP-8, Personnel Accountability & Evaluation & Rev 6 to IP-15, Emergency Exposure Guidelines ML20236M7181987-07-28028 July 1987 Rev 1 to WP-17-SQN, Vendor Weld Quality, Welding Project, TVA Employee Concerns Special Program ML20236M7351987-07-24024 July 1987 Rev 5 to 80503-SQN, Document Distribution Control, Element Rept,Tva Employee Concerns Special Program 1999-06-22
[Table view] |
Text
-
. r j
.r ..,.
W . ~.*0
. NAMCO CONTROL S ..
FS$7 TTLER SOULEV ARO e MENTOR, OHto 44000 e (216) 946 6900 eTELEX 24 1566 i.
, gg.
February 23, 1981 Mr. Leon Stefanck W10D209 , ,, ' f.
Tennessee Valley Authority 5
400 Commerce Avenue ,
Knoxville, Tennessee 37902 ~. .
Subject:
Switches for Use in Nuclear Power Plants [ .
.h
Dear Mr. Stefanck:
Thank you for your recent request for information about our limit switches for use in nuclear power plants. ..
t We are enclosing a copy of our Series EA80 General Catalog. We ave adapted two of our switch lines to make them suitable for use in a nucicar power plant. The two switch lines are the EA170 (D2400X) series shown on pages 11 through 18 of the catalog and EA700 (SL) series shown on pages 23 through
- 30. .. .
The switches shown in the catalog are standard units, but the nucicar models . .'g -
are mechanically and electrically the same as these shown. They vary only in the special materials which are used in their fabrication in order to make them suitabic for use in a nuclear power plant environment.
We are enclosing lists of the part numbers for the three types of switches in each line. Taking the D2400X series first, the EA170 __100 part numbers represent our standard switch and are cross-referenced with the old D2400X part numbers. This switch has a NEMA 4 enclosure and is suitable for'use -
in an ambient of' 900C, but is not suitabic for other than a general use, and is not satisfactory for use in areas that will see any unusual environ-mental conditions. This switch has been scismically qualified to IEEE-344-1975. v-The EA170 __302 part numbers are shown on the second sheet, and these are modifications of the standard switch. These switches are also scismically ~
qualified and are suitable for use in areas outside of the containment area with a cumulative radiation dosage of 2 X 10 8 rads. -
The EA180 part numbers are shown on the last page. These are the switch models that are qualified to IEEE-323-1974, IEEE-344-1975 and IEEE-382-1972.
8204090423 820407 PDR ADOCK 05000327 P PDR
- b. e 9
NAMCO CONTAcx S 2-
. .s ",
e*
Tennessee Valicy Althorit/ - February 23, 1981 -
- - . ... x., .
These units differ only in the materials used in their construction and are chosen to withstand the environmental conditions that may exist in the containment area. .
The~SL (EA700) series switch is also available in three models for the various locations as described above. The EA700 represents the standard switch. The EA750 series is the switch modified for areas outside of the containment, and the EA740 is the qualified switch for use inside of the containment area.
'.' As we discussed with you on the telephone, the EA700 is a standard limit s switch, and is really not suitable for nuclear use. The switch is seis-mically qualified to IEEE-344-1975 by similarity, since the EA740 is quali-fied, and. the latching mechanism is the same.
The TA700 switch has a NEMA 4 watertight enclosure. It has a maximum 6
"r -
' ambient rating of 90 c and can tolerate a radiation level of 1 X 10 rads.
0 The levers for use with these switches are shown on pages 35 through 38 of the ~
catalog. For use on switches inside of the containment area, we would re-commend the use of 1cvers with bronze arms and beryllium copper rollers.
If you require any additional information, please contact me. .
Tours very truly, 1
.L.-
Robert H. Kantner Staff Sales Engineer NAMCO CONTROLS
&l g' .-
Enc.
cc: G. S. Patton 9
[ .
O O
'
- 4 "'Nm,ess.. 'N- Onk,gg gy ,
s
1*
- . l' mmo ecxvmcx_s EA170 (D2400X) SERIES CATALOG PART NUMBERS
)
STANDARD SWITCH OLD PART NUMBER SHOWN IN ( ) '
SEISMICALLY QUALIFIED TO IEEE-344-1975_
l 100 TRIP TRAVEL CCW CW MOUNTING _ .
EA170-12100 (D2400X-SR)
Standard EA170-11100 (D2400X)
EA170-21100 (D2400X-1) EA170-22100 (D2400X1-SR)
Style 1 EA170-32100 (D2400X2-SR)
Style 2 EA170-31100 (D2400X-2)
SHORT TRAVEL SWITCH 6h0 TRIP TRAVEL CW CCW MOUNTING '
EA170-14100 (D2400X-ST) EA170-15100 (D2400X-ST-SR)
Standard EA170-25100 (D2400X-ST1-SR)
Style 1 EA170-24100 (D2400X-ST-1)
EA170-34100 (D2400X-ST-2) EA170-35100 (D2400X-ST2-SR)
Style 2 REVERSE SHAFT SWITCH 10 TRIP TRAVEL ,
CCW CW
'_ MOUNTING EA170-41100 (D2400X-R) EA170-42100 (D2400X-R-SR)
St,andard EA170-52100 (D2400X-R1-SR)
Style 1 EA170-51100 (D2400X-R1)
EA170-61100 (D2400X-R2) EA170-62100 (D2400X-R2-SR) 3, Style 2 REVERSE SHAFT SWITCH
, 6h0 TRIP TRAVEL CW CCW MOUNTING EA170-44100 (D2400X-ST-R) EA170-45100 (D2400X-ST-R-SR) l Standard EA170-55100 (D2400X-ST-R1-SR)
Style 1 EA170-54100 (D2400X-ST-R1) .
EA170-64100 (D2400X-ST-R2) EA170-65100 (D2400X-ST-R2-SR)
Style 2 NOTE:
For non-nuclear applications, a 1 N.O. - 1 N.C. switch is available in our EA080 Series.
~. . ~ . . . . _
R; vised 4/18/79 - - . _ _ _
,s -
.(
],, ,-b. , NAMCO CCvvrRCx.S
. . .s.-
'.~. T-
.; p.,, .
.y-
,.-s q,EA170- 302 CATALOG PART NUMBERS I* -li. SW5TCHES FOR USE OUTSIDE OF CONTAINMENT AREA a . .
." h + ' 15EIdiICALLY QUALIFIED TO IEEE-344-1975 AND
. 4,,
PARTS I AND II OF IEEE-382-1972**
8 AMBIENT RADIATION LEVEL 2 X 10 ,
' 100 TRIP TRAVEL CW CCW MOUNTING EA170-11302 EA170-12302 Standard Style 1 EA170-21302 EA170-22302 Style 2 EA170-31302 EA170-32302 SHORT TRAVEL SWITCH
~~
610 5 TRIP TRAVEL CW CCW MOUNTING Standard EA170-14302 EA170-15302 Style 1 EA170-24302 EA170-25302 Style 2 EA170-34302 EA170-35302
CW CCW MOUNTING
> Standard EA170-41302 EA170-42302 Style 1 EA170-51302 EA170-52302 Style 2 EA170-61302 EA170-62302
- REVERSE SHAFT SWITCH 615 0 TRIP TRAVEL CW . CCW MOUNTING _
Standard EA170-44302 EA170-45302 Style 1 EA170-54302 EA170-55302 Style 2 EA170-64302 EA170-65302
- Not available in EA180 Series.
- Latest Qualification March 28, 1980, Report QTR-107 .
a
,,$ 3e n- .
. c-s,
.f.t,;
NAMCO CCMACX.S
.t- ~
' 7
. . , , ' ' . /'.' / ' .'
g ,., , ., 4 ,
, j';f ~[ , . .,/ 'i f-
~ --
.g
, ya ;
2
'h .
EA1BG SERIES (REF. D2400X)
SWITCHES FOR NUCLEAR ENVIRONMENT SWITCHES ARE QUALIFIED TO IEEE-344-1975, 323-1974 & 382-1972*
100TRIP TRAVEL CW CCW MOUNTING EA180-11302 EA180-12302 Standard Style 1 EA180-21302 EA180-22302
. Style 2 EA180-31302 EA180-32302 SHORT TRAVEL SWITCH 6h0 TRIP TRAVEL .
CW CCW MOUNTING EA180-14302 EA180-15302 Standard EA180-24302 EA180-25302 Style 1 EA180-34302 EA180-35302 Style 2
- Latest Qualification !! arch 5,1980. Report QTR-105 s
R3 vised 2/20/81 _ _ _ _ _ _ _
-'mo ccxvmos_s p
,,, ,, ,, 1=
- .. zr ,e
.s- ,. .
- EA700 (SL) SERIES CATALOG PART NUMBERS
, g..,.
-S'",.. ? i STANDARD SWITCH
(
- ..F l OLD PART NUMBERS SHOWN IN ( ) *
'h i
- iSEISMICALLY QUALIFIED TO IEEE-344-1975 MOUNTINC CW CCW Standard EA700-10000 (SL2C) EA700-10001. -(SL2C-Z)
Wide (W) Mtg. EA700-40000 (SL2C-W) EA700-40001 (SL2C-W-Z) long (L) Mtg. EA700-70000 (SL2C-L) EA700-70001 (SL2C-L-Z)'
Standard EA700-20000 (SL3C) EA700-20001 (SL3C-Z)
Wide (W) Mtg. *EA700-50000 (SL3C-W) EA700-50001 (SL3C-W-Z)
Long (L) Mtg. EA700-80000 (SL3C-L) EA700-80001 (SL3C-L-Z)
WITH B2 CAM FOR CW & CCW OPERATION MOUNTING CW & CCW -
Standard EA700-10100 (SL2C-B2)
Wide (W) Mtg. EA700-40100 (SL2C-B2-W)
Long (L) Mtg. EA700-70100 (SL2C-B2-L)
Standard EA700-20100 (SL3C-B2)
Wide (W) Meg. EA700-50100 (SL3C-B2-W)
Long (L) Meg. . EA700-80100 (SL3C-B2-L) s l .
~
Reviend 12/1/77 ,
-- . . - - - _._ m , , _ , . . _ . - . _ _ _ - - - -
' *=..
o,
. . e :. y . . . f
,k, .,' ,
NAMCO CONTTWES
. . .s.' .- s
. * 's g
?.
EA750 (SL) SERIES CATALOG PART NUMBERS SWITCIIES FOR USE OUTSIDE OF Tile CONTAINMENT AREA SEISMICALLY QUALIFIED TO IEEE-344-1975 AND- .
PARTS I AND II OF IEEE-382-1972.*
AMBIENT RADIATION LEVEL 2 X 108-MOUNTING CW CCW Standard EA750-20000 EA750-20001 Wide (W) Mtg. EA750-50000 EA750-50001 -
Long (L) Mtg. EA750-80000 EA750-80001
'i WITH B2 CAM FOR CW & CCW OPERATION . .
MOUNTING CW & CCW Standard EA750-20100 Wide (W) Mtg. EA750-50100 Long (L) Mtg. EA750-80100 -
t l
l l
l
.
- Latest Qualification March 28, 1980. Report QTR-110
(
' " h e+ we m.h ,,%, p.
l .
, _, MMCO CONTFADt_S y, tg . t6
(
1 EA740 (SL) SERIES CATALOG PART NUMBERS SWITCHES FOR NUCLEAR ENVIR0tMENT Switches are Qualified to IEEE-344-1975, 323-1974 and 382-1972*
-~-
' ^
.b.' ' ' * *
. . . .e .... ,
{ y.
. Standard EA740-20000 .. '.EA740-20001 i- '
't Wide (W) Mtg. EA740-50000 .,, . q.;;,f . EA740-50001 It , .- (h' ;> Jg , . .. ,
~
Long (L) Meg. EA740-80000 '",, EA740-80001 , , ,
~*-
.s c- ~. g.. L,. ,;
.y w.'.
. r .
. .s:. q .:. ..
. c e.,.;gy .. i. . ,,- . . - c..:
- .' W :: (. .
- d.,? }.l'.
. . ,:.u WITH B2 CAM FOR CW & CCW OPERATION MOUNTING CW & CCW EA740-20100 Standard Wide (W) Mtg. -
EA740-50100 Long (L) Mtg. EA740-80100 l
l Latest Qualification October 2, 1980. Report QTR-111.
2/20/81
/ _.
Procedure No.
.f - ATt-lOOD I.
fl o P !t I L I. C O . , T tJC . 201-39500
~ f S A Lt:t t , i tAS S . 01970
'l-r'
. ~ ~ - ' ~ ~ ' Date t!ANUFACTUitIt!ri PitOCCDURE OR BCPoltT May 1, 1979--
/ l.,u . . . . . . . _.
A-Mr 4'L
(/ g.i.3,g VALVE ACTUATOR QUALIFICATION
- TEST REPORT l
N/
Revisions - - ---
(1) (2) (3) (4)
-Ori ginal Issue (Rev. 0)__-. .
, _ _ _ _ _ Initials __-__
Signature Title Date . - . . . - .
Date 1 Oric inat. ora -
itzo TECT- Of b, --- --- -- _- - - - -
[1L nht. . . .
// 3[ buGNEER_.
M9 - - - - - "
llov iewe rd - - -- _ -- -- - --
A,fy,T gbu' f'O If g.n.n
[W --- -- ----
Re vi ewo r : --- _- - - --
1 -
,