ML20212M591

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Rev a to Procedure 328, Qualification Testing of Relay Assemblies,219 Frame & 236 Frame Per IEEE Std 323 - 1974. Related Info Encl
ML20212M591
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 05/29/1979
From:
STRUTHERS-DUNN, INC.
To:
Shared Package
ML20212M416 List:
References
328, NUDOCS 8703120089
Download: ML20212M591 (79)


Text

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STRUTH ERSoDUNN INC.

PITM A N, N.J.

2 '.

STRUTHERS DUNN TITLE STRUTHERS-DUNN PROCEDURES FOR DATE

/[' PROCEDURE (S.D.P.)-

NUMBER 328 QUALIFICATION TESTING OF RELAY ASSEMBLIES, 219 FRAME AND 236 FRAME 3/1/79 PER IEEE STD 323 - 1974

- APPLICABLE DOCUMENTS APPLICABLE DR AWINGS IEEE STD 323 - 1974 S-D TEST PLAN FOR QUAL.TO IEEE 323 -

1974, ADDENDUM JUNE 27, 1978.

COMSIP CUSTOMLINE P.O.E-6008-4, Rev.3 8/29/78;SC 6008-45 (Q) 2/1/79 ORIGINAL DOCUMENT PREPARED BY: - > // 4

  • ~

APPROVED BY AND DATE: '

CHANGE RECORD Revision Date Description of Chonge Revise d By: A d Do e '

A 5/25/75 Per Memo W. Ege 5/10/79 -

<edI{

(5S Para. 3.3 (Inspection Routine) f2l}/ ,

Deleted: '

  • Socket used during high temp. aging 4.7.3 only.

Added:

One 219BBX221 (#7) mated with CX3782 throughout test.

Changed:

Test No. 10 - from "one ea. type" to

"#1 - #13".

Test No. 11 from "one ea. type" to "3".

Test No. 16 from "each type" to #5" Test No. 17 - from "each type" to i "#16".

l Test No. 18 added Sample Identif. No.

19 (no change).

Para. 4. 7.1 Iligh Temp. Agina I (Load Life)

! Changed: ,,

  • Sample "#13 - #14 to Sample #13 0703120089 870219 PDR ADOCK 05000498 E PDR 1 6

STRUTHERS DUNN INC.

PIT M A N, N. J.

STRUTHERS'DUNN TITLE STRUTHERS-DUNN PROCEDURES FOR DATE PROCEDURE (S.D.P.) QUALIFICATION TESTING OF RELAY e'\ U 328 ASSEMBLIES, 219 FRAME AND 236 FRAME PER IEEE STD 323 - 1974 3/1/79 APPLICABLE DOCUMENTS APPLICABLE DR AWINGS IEEE STD 323 - 1974 S-D TEST PLAN FOR QUAL. TO IEEE 323-1974, ADDENDUM JUNE 27, 1978.

COMSIP CUSTOMLINE P.O. E-6008-4,Rev 2 8/29/78;SC 6008-45 (Q) 2/1/79 ORIGINAL DOCUMENT PREPARED BY :

APPROVED BY AND DATE:

CH ANGE R ECOR D Revision Date Description of Change Revised By:

And Dot A 5/25/70 Para. 4.7.2 High Temp. Aging

( (Mech. Life)

Changed:

Seismic testing midway all samples to Seismic Testing midway Sample #5, #16,

  1. 19.

Added:

Append. I Acton TP 14812 Append. II Acton TP 14552 B 12/12/7 ) Changed Acton TP 14812 to Append.I -

and TP 14552 to Appendix II to agree with Para. 4.5 and 4.6 references.

C 6/4/8C Change P/N from CX3872 to CX3966NE 3 d*' ' 4"  : - ) [ ' t** *

"! 1 "

on Page #3 para. 3.3 on Page #12 para. 4.7.3 D 3/30/82 Add Addendum 1, Rev. I which consists '

of: Sept. 21, 1981 ltr. -

J. Carr to Comsip Inc. and a six page procedure consisting of Section I and Section 2.

E 8/5/82 Feature numbers changed - all types. [Q,g v '

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( Per Wm. Ege. v 7;,

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STRUTH ERS-DUNN INC.

PIT M A N, N. J.

STRUTHERS 0UNN TITLE STRUTHERS-DUNN PROCEDURES FOR DATE PROCEDURE (S 0.P.) QUALIFICATION TESTING OF RELAY

\< NUMBER 328 ASSEMBLIES, 219 FRAME AND 236 FRAME 3/1/79 PER IEEE STD 323 - 1974 APPLICABLE DOCUMENTS APPLICABLE DR AWIN GS IEEE STD 323 - 1974 S-D TEST PLAN FOR QUAL. TO IEEE 323-1974, ADDENDUM JUNE 27, 1978. ,

COMSIP CUSTOMLINE P.O. E-6008-4,Rev.

3, 8/29/78 SC 6008-45 (Q) 2/1/79 ORIGINAL DOCUMENT PREPARED BY:

APPROVED BY AND DATE:

e CHANGE RECORD Revision Dcte Description of Chonge Revise d By: A d Do s F 11/4/82 Addendum 1, Rev.1, Section 1 BG$( h4

(, Changed:

Sample No.'s 5,7, and 8 to 8,10, and 12 g g-sz (Page titled Vinyl Pad)

Sample No,'s 9,10, and 12 to 5,7,and 9 (Page titled Schedule for Test Units -

Silicone Pad)

Above requested By J. J. Carr.

G 11/10/82 Per Memo W. Ege 11/8/82 ?dr$b T

/'- # -d '

Page 1B (Rev. F)

Changed:

Addendum 1, Rev. 1 to Addendum 1, Rev. 2 Added:

Page 14A "10*C Rule Plot".

Addendum 1 Changed:

a) Rev.1 to Rev.2 (all applicable ref-erences )

b) t1 and t2 to T1 and T2 (Sheet en- ,

l ( titled Vinyl Pad Aging) l t

_ _ _t y . _ _ _ ____ _ _ _ _ _ __ _ _ _

STRUTH ERSoDUNN INC.

PIT M A N, N. J.

STRUTHERS DUNN TITLE STRUTHERS-DUNN PROCEDURES FOR DATE PROCEDURE (S.D.P.) QUALIFICATION TESTING OF RELAY 3/1/79 C NUMBER 32d ASSEMBLIES, 219 FRAME AND 236 FRAME PER IEEE STD 323 - 1974 APPLICABLE DOCUMENTS APPLICABLE DRAWINGS IEEE STD 323 - 1974 S-D TEST PLAN FOR QUAL. TO IEEE 323-1974, ADDENDUM JUNE 27, 1978.

COMSIP CUSTOMLINE P.O. E-6008-4, Reu 3, 8/29/78: SC 6008-45 (Q) 2/1/79 ORIGINAL DOCUMENT PREPARED SY:

APPROVED BY AND DATE:

CHANGE RECORD Approved By Revision Date Description of Change Revised By: And Date; G 11/1Q432 Addendum 1

< Added:

a) Sheet entitled " Vinyl Pad Aging".

b) 10*C Rule Plot " Vinyl Pad -

Artificial Aging at 85'C".

l H 1/2&B3 Per Memo Jim Carr 1/13/83 (Revised , ,{ g upon request of Bechtel. Delete _ g ,g

  1. 12 from SDP. Not thermally aged) :

Addendum 1.

Title Page:

Changed Was: Rev. 2 Is Now: Rev. 3 Sheet Titled " Addendum 1 - Rev. 2-Section 1 - Vinyl Pad".

Changed Was: Rev. 2 Is Now: Rev. 3 Changed Was: three relays No. 8,10,12

( Is Now: two relays No. 8 and 10.

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{ S. D. R # 328 TITLE:SEE TITLE PAGE DATE:

3/1/79 TABLE OF CONTENTS PAGE NO, 1.0 Scope 3 2.0 Description of Test Samples 3 3.0 Test Program 3 to 6 3.1 Qualification 3 3.2 Sample size and Identification 3 3.3 Inspection Routine 3, 4, 5 3.4 Test Witnessing 6 3.5 Test Report 6 4.0 Test Procedures 7 to 14 4.1 Pick-Up and Drop-Out. Voltage 7 4.1.1 Operation Delay on Operate 8 4.2 Operate and Release Time 8, 9 4.3 contact Resistance 9 4.4 Dielectric Strength 9 4.5 Radiation Testing 9 4.6 Seismic Testing 10 4.7 High Temperature Aging 10

',, 4.7.1 High Temperature Aging-Load Life 10, 11 4.7.2 High Temperature Aging-Mech. Life 11, 12 4.7.3 High Temperature Aging-Non-Switching 12, 13 4.8 Humidity 13, 14 Appendix I Acton TP'14812 l Appendix II Acton TP~l4552 l

STRUTHame DUMN INC.

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( S. D.R a 3 28 TITLE:SEE TITLE PAGE DjT{p79 j

1.0 Scope. This procedure outlines the detailed methods and requirements for Qualification Testing in accor-dance with S-D Test Plan for Qualification to IEEE 323-1974, Addendum June 27, 1978 with exceptions as indicated herein.

2.0 Description of Test Samples The following relays are described as Heavy Duty, General Purpose, Plug-In:

S-D P/N Features 219BBX221 Coil 125 VDC, contacts 10A,120 VAC,2N.O.2D.T.

219DXB120 Coil 125 VDC, contacts 10A,120 VAC,4N.O.2N.C.

The following relay is described as Heavy Duty, General Purpose, "On" Delay 0.2-20 Seconds:

S-D P/N Features 236ABX135 Coil 125 VDC, Contacts 10,120 VAC,1 N.O.,2D.T.

3.0 Test Program

( 3.1 Oualification. Qualification inspection shall be per-formed on sample relays produced with equipment and procedures normally used in production.

3.2 Sample Size and Identification. Twenty-one (21) relays shall be tested. Samples as follows:

Twelve (12)- 219BBX221 (Samples #1 through #12)

Six (6) - 219DXB120 (Samples #13 through #18)

Three (3) - 236ABX135 (Samples #19 through #21) 3.3 Inspection Routine. Samples shall be tested as specified herein in the sequence shown per Table I when mounted in their applicable mating sockets as follows:

Relay P/N 219BBX22r with Socket P/N CX3964 /*CX3966NE Relay P/N 219DXB120 with socket P N/ CX3965 Relay P/N 236ABX133 with Socket P/N CX3964

  • One 219BBX221 (#7) mated with CX3966NE throughout test.

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( S. D. R # 328 TITLE:SEE TITLE PAGE D AT E : 3 /1/79 l

3.3 (Cont.) l Table I - Qualification Inspection i Test Group I - All samples #1 through #21 1.(a) Pick-Up and Drop-Out Voltage 4.1 (as applicable)

(b) Operation Delay on Operate 4.1.1 (as applicable)

2. Operate and Release Time 4.2 (as applicable)
3. Contact Resistance 4.3
4. Dielectric Strength 4.4
    • 5. Radiation 4.5
    • 6. Seismic Testing 4.6
7. Repeat Tests 1.2.3.4 above Test Group II - Six samples: Four 219BBX221 (#1-2-3-4)

Two 219DXB120 (#13 - #14)  ;

8. High temperature aging 4.7.1 (Load Life 10A, 120 VAC l Res. @ +106 C) '

Test (a) Slow Speed,Two 219BBX221 (#1 - #2)

One 219DXB120 (#13)

Test (b) High Speed,Two 219BBX221 (#3 - #4)

One 219DXB120 (#14)

( 9. Repeat Tests 1.2.3.4 Group I at midpoint of 8(a) (b)

10. Repeat Seismic Testing at Midpoint of 8(a)1 -#13 s.
11. Repeat Seismic Testing at midpoint of 8(b) #3 -

12 Repeat Seismic Testing af ter 8(a), (b),all samples in Gr p 13 Repeat Tests 1.2.3.4, Grp. I

    • Tests performed at outside facility.

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( S. D. P. at - 328 TITLE:SEE TITLE PAGE DATE:

3/1/79 3.3 (Cont.)

Test Group III - Five Samples:Two 219BBX221 (# 5-# 6)

Two 219DXB120 (*15-d16)

One 236ABX135 (#19)

14. High Temperature Aging 4.7.2 (Mechanical Life @+106 0C)

Test (a) Slow speed,One 219BBX221 (#5)

One 219DXB120 (#15)

Test (b) High Speed,One 219BBX221 (#6)

One 219DXB120 (#16)

Test (c) Mid-Range,One 236ABX135 (#19)

15. Repeat Tests 1.2.3.4 Grp I at mid-point of 14(a) (b) (c)
16. Repeat Seismic Testing at mid-point of 14(a), #5
17. Repeat Seismic Testing at mid-point of 14(b), #15
18. Repeat Seismic Testing at mid-point of 14(c) #19
19. Repeat Seismic Testing af ter 14(a) (b) (c) all samples /
20. Repeat Tests 1. 2. 3.4, Grp. I in Grp.

Test Group IV - Eight Samples:Four 219BBX221 (#7-8-9-10)

Two 219DXB120 (#17-#18)

Two 236ABX13 5 (#20-u21)

21. High Temperature Aging 4.7.3 (NO Contact Load @+106 C)

Test (a) Ene rg. continuously,Two 219BBX221 (#7-#8)

One 219DXB120 (#17)

One 236ABX135 (#20)

Test (b) De-energ. continuously,Two 219BBX221 (#9-#10)

One 219DXB120 (#18)

One 236ABX135 (#21)

22. Repeat Tests 1.2.3.4, Grp. I
23. Repeat Seismic Testing
24. Repeat Tests 1. 2.3.4, Grp. I l

Test Group V - Two Samples - 219BBX221 (#11 - #12)

25. Humidity, 4.8
26. Repeat Tes ts 1.2. 3.4, Grp. I
27. Repeat Seismic Testing
28. Repeat Tests 1.2.3.4, Grp. I i

STRUTMERS-cUNNINC.

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( S. D. R # 328 TITLE:SEE TITLE PAGE D AT E: 3/1/79 3.4 Test witnessing. S t ruthe rs-Dunn , Inc. is required to allow Bechtel/Comsip free access to all test facilities.

Five (5) days prior notification is required before actual test sequences are performed to allow attendance of Bechtel/Comsip representatives.

3.5 Test Report. The report shall present results data and all information necessary to show completion of testing in accordance with this SDP. In addition, a monthly status report is required during test.

Upon completion of testing, a copy of the finished report shall be forwarded to Comsip Customline Corp.

for review.

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9 S. DIP.a 328 -TITLE:SEE TITLE PAGE D AT E : 3 /1/79 4.0 Testg?rocedures I 4.1 Pick-Up and Drop-Out Voltage 219BBX221; 219 DEB 120 with the relays in the de-energize stato, ' a variable source of DC; voltage shall be applied to tye *ccil -

terminals and, facreased gradually until each of the normally open centacts close and the armature' seals in.

Voltage shall be increased from pick-up point to 140 VDC and the contacts observed to determine >the presence cf

" break" and"re-make." Voltage shall then be reduced gradually until each of the n'armally 61osed contacts re-close and the armature open.t . Voltage shall be reduced to zero and the contacts observed to determine the presence of " break" and "re-make".

Indicating lamps shall be used'to monit6r contact operation.

Pick-up (voltage at which last normally open contace'

( closes and armature sea?.s in) and drop-out (voltage at which last normally closed contact re-closes and

{

armature opens) shall be recorded. O Relays must pick up and make positive contact within the value specified per P.O. E-6008-4, Rev.3: -90 voC.

or less and shall be capable of opercation at 90: Vrc through 140 VDC.

Drop-out voltage is not specified.

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Contacts shall not change state once pickup or drop-

out has occurred. Upon establishing these points, j relays shall be operated intermittently from pick-up .

j- to 140 VDC to insure proper operat2on.

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( S. D. R # 328 TITLE:SEE TITLE PAGE D ATE : 3 /1 '79 4.1.1 Operation Delay on Operate 236ABX135 The relay samples shall be tested for operation throughout the voltage range specified per P.O. E-6008-4, Rev. 3, 90 VDC through 140 VDC, at both the high and low settings (0.2 seconds - 20 seconds).

The relays shall perform within the recuirements specified per S-D Catalog 676 as follows:

90 VDC shall be applied to the input terminals and the relay shall time-out within 0.2 seconds maximum on the low setting and between 20 and 30 seconds on the high setting.

Following a timing cycle the relays shall be de-energized for a period of 40 to 45 milliseconds.

Voltage shall be re-applied and the relay shall re-cycle as specified. Recycling shall be repeated five (5) times at both low and high settings and

values recorded. Relays shall time out and maintain a repeat accuracy of 5% at constant voltage.

Output circuits shall be monitored to insure proper switching action.

The above tes t shall be repeated with 140 VDC applied

< to the output terminals. Relays shall operate within 4 -

the parameters specified above.

4.2 Operate and Release Time 219BBX221; 219DXB120

, Each contact set shall be tested to determine time by viewing contact closure by means of an oscilloscope connected to suitable test circuitry. Contacts under i test shall carry 0.5A at 6 VDC and nominal voltage f

. 125 VDC, shall be applied to the relay coils.

Operate time is the time that elapses between applicatior fg of nominal voltage and the closing of the last nor-l mally open contact. Release time is the time that l elapses between disconnection of nominal voltage and l the re-closing of the last normally closed contact.

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/ [' Velues shall be recorded.

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(- S.D. Rat 328 TITLE:SEE TITLE PAGE D ATE : 3 /1/79 4.2 (co nt. )

Timing shall be within the, values specified per S-D Catalog 676. Operate time shall be within 25 milli-seconds, maximum. Release time shall be within 20 milliseconds maximum..

i 4.3, Contact Resistance. Measurements shall be made with the contacts carrying a resistive current of 0.5A at 6 VDC using the Voltmeter-Ammeter Method. Ten (10) seconds prior to making measurements, the contacts under test shall carry the specified load. When .

measuring normally open contacts, the relay coils shall be energized with nominal voltage, 125 VDC.

Values shall be recorded.

Contact resistance shall be within .05 ohms maximum prior to load life and .10 ohms maximum during and after load life,.

4.4 Dielectric Strength. 'With the relays stabilized at

( '

normal atmospheric conditions, the following voltage potentials shall'he tapplied at the points indicated for a period of one '(1) minute at each test point.

(a) Between contacts and case'2200 Vrms.energ.and deenerg.

f (b) Between Coil / Input and Case 2200 Vrms, de-energized (c) Between Coil /Inpat and contacts 2200 Vrms de-energized (d) Betwe,en open contacts (gap) 1500 vrms-energ.and deener g.

Conformance or non-conformance shall be indicated by a t

check entry in the test data.

There must be no, arc-over (0 2 r 'ischarge) flash-over (surface discharge) or b r e'.; do' + (puncture discharge) causing a leakage curren, in ..re ess of 1.0 Ma.

4.5 Radiation. Testing shall be conducted at a level of 1X10 J RADS. This test will be conducted by an outside facility, namely, Actop Environmental Testing Corp.

533 Main Street, Acton, Ma., 01720 Test procedures prepared by this facility form Appendix I of this S.D.P.

( .mutnu. oun= inc.

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( S. D. R at 328 TITLE:SEE TITLE PAGE D AT E : 3/1/79 4.6 Seismic Testing. Testing shall be performed in accor-dance with Comsip P.O. SC-6008-45 O as follows. Floor Response Spectra 10466-C-04A03S, 04A03B, 04A04S, 04A04B. Samples shall be tested at 2.0 g ZPA in the vertical and horizontal directions after determination that no resonant frquencies exist over the range of 1 to 40 Hz. This testing is to be conducted at an outside facility, namely, Acton Environmental Testing Corp.

533 Main St., Acton, Ma.01720. Test procedures prepared by this facility form Appendix II of this S.D.P.

4.7 High Temperature Aging Note: High Temperature Aging 4.7.1, 4.7.2, 4.7.3

a. It will be necessary for purposes of visual examination, to cause variations in the test tempera-ture (+106 C) during the check periods. These portions of test shall be conducted in a minimum amount of time so as not to allow significant variations to occur.

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! b. Any change in relay characteristics occurring during the Aging test which could affect their overall perfor-mance shall be noted on a test log sheet provided for this purpose.

! 4.7.1 High Temperature Aging (Load Life) i .

219BXX221 #1 - #2 - #3 - #4 1

219DXE120 #13 - #14 All contacts shall be allowed to make, carry and break their full rated load, 10 Amperes, at 120 Volts AC in a non-inductive, resistive circuit. Tast loads shall be so arranged that the specified current flows through each pole. A separate load shall be provided, for l each contact and the moving contacts shall be connected to the power source. All loads shall be connected between the contacts and the power supply ground or

! neutral. Nominal voltage, 125 VDC, shall be applied l to the relay coils. The test samples shall be sus-l pended in mid-air by means of a thermal ingulating material at an ambient temperature of +106 C.

l STflWTHEft9'DUMN BMC.

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( S. D. R *t 3 28. TITLE:SEE TITLE PAGE D AT E :3/1/79 4.7.1 (cont.)

Relays shall be checked once during each forty-eight (48) hour period up to the point of completion, 245 days, or until failure, whichever occurs first. Failure is defined as incapability of contacts to make, carry and/or break the specified test current, excessive contact wear, excessive contact material deposits, excessive deposits due to outgassing of cover material, parts distortion and/or mechanical damage.

Cycling rate shall be as follows:

(a) Slow Speed-10 cph (equal on/off)#1-#2-219BBX221

  1. 13 219DXB120 (b)High Speed-1 cpm (equal on/off) #3-#4-219BBX221
  1. 14 219DXB120 Midway through Load Life, the relays shall be subjected to the following tests: Pick-up and Drop-out Voltage 4.1, Operate and Release Time 4.2, Contact Resistance 4.3, Dielectric 4.4 and
  • Seismic Testing

( 4.6. Data shall be recorded.

  • Samples #1 - #3 - 219BBX221
  • Samples #13 - 219DXB120 Upon completion of Load Life, the relays shall be subjected to seismic Testing 4.6, and the tests of Para. 4.1 through 4.4 above shall be repeated and data recorded.

4.7.2 High Temperature Aging (Mechanical Life) 219BBX221 #5 - #6 219DXB120 #15 - #16 236ABX13S #19 The test samples shall be suspended in mid-air by

) means of a thermal insulating material, at an ambient temperature of +106 0C.

Contacts shall be allowed to make and break in their proper sequence, but are not loaded. Nominal voltage, 125 VDC, is applied to the relay coils / inputs. Relays sha ll be observed once daily (except Sundays) up to the point of completion, 245 days, or until failure, whichever occurs first.

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( S.D.P.m 328 TITLE:SEE TITLE PAGE D ATE : 3/1/79 4.7.2 (cont.)

Failure is defined as inability to make and/or break contact in proper sequence, loss of spring tension to a severe degree, radical adjustment change and/or parts breakage.

Cycling rate shall be as follows:

(a) Slow speed-1 cmp (equal ~ on/of f) #5 219BBX221

  1. 15 219DXB120 (b) High Speed-l cps (equal on/off) #6 219BBX221
  1. 16 219DXB120

'(c) Mid-Range-2 cpm (25 sec.on/5 sec.of f) #19-236ABX135 Midway through Mechanical Life, the relays shall be subjected to the following tests: Pick-up and Drop-out Voltage 4.1 (as applicable) operation 4.1.1 (a s applicable) , Operate and Release Time 4.2 (as applicable)

Contact Resistance 4.3, Dielectric 4.4 and

  • Seismic Testing 4.6 Data shall be recorded
  • Sample #5 - 219BBX221 Sample #19 - 236ABX135 Sample #16 - 219DXB120

( Upon completion of Mechanical Life, the relays shall be subjected to Seismic Testing 4.6 and the tests of Para. 4.1 through 4.4 above shall be repeated and data recorded.

4.7.3 High Temperature Aging (Non-switching) 219BBX221 #7 - #8 - #9 - #10 See Note 219DXB120 #17 - #18 236ABX13 5 n20 - #21 The test samples shall be suspended in mid-air by means of a thermal insulating material at an ambient temperature of +106*C and maintained at the following conditions.

  • (a) coil energ.continously, no cont. load #7-#8-219BBX221 n .. " "

n "

  1. 17 219DXB120
  1. 20 236ABX135
  • @ 125 VDC NOTE. Sample #7 mated with CX 3966NE (b) Coil de-energ. continuously, no cont. load #9-#10-219BBX2 21
  1. 18-219DXB120
  1. 21-236ABX135 STRUTHERS-OUMN INC.

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h S. D. P. # 328 TITLE:SEE TITLE PAGE DATE: 3/1/79 4.7.3 (cont.)

Relays shall be checked once during each forty-eight (48) hour period, up to the point of completion, 245 days, or until failure, whichever occurs first.

Failure is defined as "open" contacts of energized relays, open or shorted turns of energized coils, excessive deposits due to outgassing of cover material and/or parts distortion.

Upon completion of High Temperature Aging (non-switching) the relays shall be subjected to the follow-ing tests: Pick-up and Drop-out Voltage 4.1 (as appli-cable), Operation 4.1.1 (as applicable), Operate and Release Time 4.2 (as applicable), Contact Resistance 4.3, Dielectric 4.4 and Seismic Testing 4.6. Data shall be recorded.

Upon completion of Seismic Testing 4.6, the tests of Para. 4.1 through 4.4 above shall be repeated and data recorded, f

\ 4.8 Humidity (Method 106D, MIL-STD-202E) 219BPX221 #11 and #12 The test samples shall be mounted in mid-air by means of twine and positioned so that one does not contact the other and both receive the same degree of humidity.

Distilled water, having a pH value between 6.0 and 7.2 at 23 C shall be used to obtain the specified h umidity.

The test samples shall be subjected to ten (10) continuous cycles, each as shown per Figure 1.

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( S. D. P. a 328 TITLE:SEE TITLE PAGE D ATE: 3/1/79 4.8 (Cont.)

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-lo ' I O 2 4 6 8 to 12 I4 16 18 20 22 24 26 Figure 1 HOURS Upon completion of the tenth and final cycle, the samples shall be removed from the test chamber and allowed to condition for a period of twenty-four (24) hours at room ambient conditions.

The following tests shall then be performed: Pick-up and Drop-out Voltage 4.1, Operate and Release Time 4.2, Contact Resistance 4.3, Dielectric 4.4 and Seismic Testing 4.6. Data shall be recorded.

Upon completion of Seismic Testing 4.6, the tests of Para. 4.1 through 4.4 shall be repeated and data recorded.

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S. D. R a 328 TITLE:SEE TITLE PAGE DATE: 3/1/79 l

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APPENDIX I Acton TP14812 l

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i, 97RWTMERG DUMN INC.

t

'No. 14812

. r, ,

Test Procedure FOR RADIATION TESTING OF RELAYS & SOCKETS FOR STRUTHERS-DUNN, INC.

10 {

Preparedby:f'!. . ,dH[ tk- Date t/

1 301 79 R.Lamothe, Senior Scientist i /

Acton Environmental Testing Corporation 533 Main St. , Acton, Mass.

Approved by: / /

R~.S.Gilfoy, ChieVDynafnics Engineer

-Date 2 3 .4 a . 2 9 Acton Environmental Testing Corporation Approved by:)JL,m ._ / / ,./ f e;f.e-# ~

Date $ /#/29

. Marvin L'. Tolf, &Fesident' Acton Environmental Testing Corporation Approved by: Date - -

Struthers-Dunn, Inc.

RL/hmf 4/20/79 .

( c ~ .. o ~ ~ c ~ , . c

.* I ~

ACTON jI '"

( /e o.... . ..o~

a ,,

TABLE OF CONTENTS i

SECTION PAGE l'.0 APPLICABLE DOCUMENTS 1 2.0 TEST ITEMS 2 3.0 BASELINE FUNCTIONAL TEST 3 4.0 TEST REQUIREMENTS 4 .

5.0 TEST PROCEDURES 5

- 6.0 FUNCTIONAL TESTING 6 7.0 TEST REPORT 7

.( .

1

~

14812 Test Procedure No.

( tuvmosururAs.

Page p7,,,,J y mmo a

. k

.n 1.0 APPLICABLE DOCUMENTS i

Acton Environmental Testing Corporation Quotation No. L-12273 dtd 2/14/79 f

-s

.(

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l

. Test Procedure No. I48I2

( ENVIRONM ENTA1.

Page I

.( ,ero, ', resnNa

.4 k CORPORADON

d n  ;

3.0 BASELINE FUNCTIONAL TEST A representative from Struthers-Dunn Inc. will provide and perfoim a baseline functional test to insure that the units are operating properly and to determine their baseline operating parameters for comparison with post radiation func-tional tests.

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( .3 4.0 TEST REQUIREMENTS The purpose of this test program is to subject the components in section 2.0 to radiation tests as specified

- in section 4.0 below to determine their ability to with-stand such environments without evidence of electrical or mechanical damage or deterioration or loss of their ability to operate properly during or after the simulated radiation .

. environment.

(

i Test Procedure No. I48I2 l tw=owevrAt.

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  • 5.0 ' RADIATION TESTING The components will be shipped to the Frank H. Neely Nuclear Research Center of Georgia Institute of Technology for radiation testing. The items shall be unpacked and ,

placed in the appropriate radiation facility. The testCN'-

5 17 items shall be exposed to a -tota.1 dose of 1X10 0[s"ofh ra 4

gamma radiation at a dose rate between 3-5X10 rads / hour.

Radiation test method and certification will be provided -

by the facility.

Following completion of the radiation test, the items will be returned to Acton Environmental Testing Corporation.

(

4 Test Procedure No. I40I2 twouemat.

l'ij; ACTON ",

) coaronAn m

l l

( '

'6.0 FUNCTIONAL TESTING The functional testing will be performed by a representative of Struthers-Dunn Inc. at the Acton

, . Environmental Testing Corporation facility.

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f Test Procedure No.

EWMONMEP(7AL

?{,,;r..,~. e.g. s l ( ) coneoaanon -

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( 7.0 TEST REPORT

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The test report.will include a detailed description of test items, recuirements, procedures and test results.

Test Procedure No. I40I2 i

ENVIRONMENTAL ACTON I

[.) I

  • comPonAtioN

,( S. D. R # 328 TITLE SEE TITLE PAGE DATE: 3/1/79 l

l i

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l APPENDIX II l Acton TP 14552 l

l 4

STRWIMERG-DUNN $NC.

t

e No.-14552

(. Rev. 1 i

Test Procedure SEISMIC VIBRATION TESTING OF VARIOUS RELAYS FOR STRUTHERS-DUNN, INC.

UNDER PURCHASE ORDER NO. 94033 Prepared c

Bruce Espos' h d Engineer ro, Project

__Datha.m4d/99[ /'

. Acton Environmental Testing Corporation

{ 533 Main St., Acton, Massachusetts

't I,.., ,*'d-  !.

Reviewed by:kichard Gilfoy, Chief Dyna'mics EngineerDate2'//2e 98 Acton Environmental esting Corporation Approved by: b'd' ,td p ! [, / A.. Date /2 7/ 78 Marvir. L. Tolf, Presidpnt '

Acton Environmental Te ting Corporation Approved by: Date -

, Struthers-Dunn Inc., Pitman, NJ i

12/27/78 BE/hmf

, c=vemo ws=ta6 l

. h ,e m e, a ACTON v

( someonssoon

  • + i' .

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REVISION RECORD REVISION PAGE PARAGRAPH CHANGES OR APPROVED DATE NUMBER NUMBER NUMBER ADDITIONS ~ -

BY 12/27/78 0 ---------FIRST ISSUE-------------------------------

, 3/30/79 1 1 1.0 Added last section

. 3 3.0 Added footnote 4 3.3 Added footnote 6 Figure 1 Changed RRS V

. ( .

P' 6

i 4

cuwR ow turat No; 14552

,.< k.T' r.

TEST 1No d 4 CORPORATION i

5

P e-1.0 TEST ITEMS The following items will be submitted by Struthers-Dunn Inc. for .

seismic vibration testing at Acton Environmental Testing Corporation.

12ess:_219g@329?_j,12gygC,_gglay,,_gtay!gg_(@3393g

,@_ges.2190X8114 125VDC Relay,,,_ graying,(C43939

_3_ecs:_23geg3128__12gygC.Iimg_gglay_gglay. gray!gg_!g28g3g

. .  !! _ec s :._C 3;ggs _ _ _ _ _ _ _ _ _ _ _ __S gs ge t. _g taying _!ag g222

_1_es _C3sug__$_9,g.8_E____Sggggt graying _!Cgg22g.

_@_ess:.C33gi@_____,______,Sggggt_gtaylgg,(e{g223, All of the above items will initially be submitted as Batch I and subjected to the seismic vibration testino specified in section 3.0 .

below and then returned to Struthers Dunn. Batch 11 consisting of 3 of the 219BBX207 Relays,2 of the 2190XB114 Relays,1 of the 236ABX128 Relays, 4 of the CX3865 Socketsy,4h: nWI 1 C%M72 CX3 Socket and # of the CX3948 Sockets will be resubmitted to AETC at a later date and re-( '

subjected to seismic vibration testing and then returned to Struthers Dunn. Batch III consisting of the same items of Batch I will be re-submitted again and resubjected to seismic vibration testing, com-pleting the test program.

l 5

14552 N"'

Rev 1 envinomaacNTA'

..-  %' TESTING Pege 1

..t acToNs'1 d l

connonATioH I

'{ 2.0 TEST REQUIREMENTS The purpose of this test is to subject the relays specified in section 1.0 above to the seismic vibration test specified in section 3.0 below tb determine their ability to withstand such vibration without evidence of mechanical damage, deterioration, contact chatter in excess of two (2) milliseconds or loss of the relays ability to operate properly, i I

( .-

1 l

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No. 14552

, ENVIRONMENTAL i ( -

2 j

5 ,,,,u' , nsvna P*9*

COR M ADON I

W

. 3.0 TEST PROCEDURES

  • 3.1 Test Mounting -

The relays under test will be mounted to a test fixture which will be securely attached to the biaxial table of the AETC 45' seismic test facility. The use of the 45' biaxial table results in equal horizontal and vertical components.

3.2 Test Monitorino The relay will have contacts monitored for contact

! chatter in excess of 2 milliseconds.

~

One control accelerometer will be mounted on the test fixture.

( 3.3 Multiple Frequency Test A biaxial multiple frequency excitation will be applied to the relays under test for a period of thirty (30) seconds. The level of periodic pseudo-random excita-tion will be such that the Test Response Spectrum (TRS),

from the control accelerometer will envelope the appro-priate Required Response Spectra (RRS). The relays under test will receive the input six times in each of four bi -

axial directions of excitation.

14552 No.

Rev 1

( ,.

rummonueurAL Page 3

' ' ACTON

, .. I CORPORATION

es The level of the first five inputs in each biaxial

( direction will' be such that the TRS from the control accelerometer computed at the Q=10(5% damping) will envelope the OBE*RRS shown in Figure 1. The level of the sixth input in each biaxial direction will be such that the TRS computed at Q=10 (5% damping) will envelope

. the SSE RRS shown in Figure 1.*

The relays under test will be subjected to the three different tests below, while the multiple frequency ex- ,

citation described above is applied:

- Non-operating mode

- Operating mode

- Transition .

( *

  • If chatter or failure occurs at the OBE leved the h put w B1 be.

icwered to level A of Figure 1 for both the OBE & SSE t ests. If chatter or failure occurs at the SSE level, the hput will be lowered to level B of Figure 1 for the SSE test. If chatter or failure occurs at level B the SSE level will be lowered to the OBE level of Figure 1. ,_

e 14552 No.

Rev 1 NMR@MEMAL ACTON l

k COR POR ATION i

'( 5.0 TEST REPORT The test report will include but not be limited to a detailed description of the test item, requirements, pro-cedures, mounting, monitoring, test descriptions and test results. The test results s'ection of the final report will -

include the ,X-Y plots of the Test Response Spectra for the control accelerometer. A test equipmer.t list and photographs of the test setup and accelerometer locations will also be

included in the test report. The test report will be pre-sented in the same general format as this test procedure.

( .

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9 14552 No.

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6 e-STRUTHERS-DUNNlINC.

PITMAN, NEW JERSEY 08071 C Manufacturers of Relais and Solid State Controls Telephonei609 5894500 T%XiSt0 M61510 September 21, 1981 Comsip Inc.

Customline Division P.O. Box 152 1418 East Linden Avenue Linden, NJ 07036 Attention: Mr. R. Sylvester, Pro' ject Coordinator

Subject:

P. O. E60084 S. O. 40998-A-F 10466-E-093-0060-04 S. O. / 008 Bill Ritter'_s Note of 7/24/81 Gentlemen:

( This is in regard to the July 24, 1981 correspondence sent to us which states that our submittal of an addendum to our qualification test procedure SDP328 has been disapproved by Bechtel Power Corporation. Our submittal was made with my letter dated February 26, 1981.

As you know, the basic SDP328 previously had been reviewed and approved by Bechtel, thus, this letter will address only the addendum even though comments and questions are noted on the already approved SDP. .

Attached is a revised addendum to SDP328. This revised addendum addresses the questions and comments made by Bechtel on the original addendum and incorporates corrections, additions, changes and clarifications as needed.

I trust this will be acceptable to Bechtel and I hope a much quicker response of their approval can be obtained.

Very truly yours, T UTHERS- IN INC.

a es J.

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STRUTHERS-DUNN, INC.

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'c TEST PROCEDURE S.D.P. 328 .

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ADDENDUM I - REVISION 3

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-SECTION I - VINYL PAD Paragraph 1 - High Temperature' Aging The vinyl pad, only, will be thermally aged at 85 C.

Periodic tests of sample pads will be performed to determine their capabilities.

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SbHEDULE FOR TEST UNITS '(VINYL PADS)'

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Aging P,roven

-Aging-

' Period ' Temperature '; Life 132 Days 85 C 5 Years

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267 Days 85 C 10 Years l',066 Days 85 C 40 Years After each aging period, the vinyl pads selected for installation into test relays, will be mechanically aged first. This will be accomplished by installing them into non-aged relays and then subjecting the relays to a one million mechanical cycle test.

E After mechanical aging the vinyl pads will be removed from the non-aged relays and installed in the aged relays.

The two aged relays are serial numbers 8 an d 10 .

These are relays from the initial program, thus, they have been aged to a 40 year life already.

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Relays 8 and 10 will be subjected to seismic tests.in accordance with Paragraph 4.6 of S.D.P 328.

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p SCHEDULE FOR TEST UNITS CSILICONE PAD 1 Aging Aging' - Proven Period ' Temperature ~' NIli'f e 8 days 160 C 40' years After aging, the silicone pads selected for use in the test relays will be mechanically aged, first. This will be accomplished by

, installing the_ silicone pads in non a'ged relays and then subjecting

, them to a one million mechanical cycle test.

Af ter mechanical aging the' silicone pads will be removed from the non-aged relays and installed in the aged relays. The three aged

( ,

relays are serial numbers 5, 7 and 9 '.'

[ These relays are from the initial program, thus, they have been aged l

to a 40 year life.

l l

l Relays 5, 7 and 9 will be subjected to seismic tests in accordance with paragraph 4.6 of S.D.P.328 l

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SECTION II - SILICONE RUBBER PAD Basic Assumptions __

3 A - The radiation requirement of 1X10 rads does not adversely affect the life and characteristics of the silicone rubber.

Verification for this is provided in EPRI-NPel558 Project 890-1, final report dated 1980, Appendix C tables and graphs of radiation endurance data.

Page C-3, Figure C-3 shows silicone rubber having only " incipient 6

to mild danagd'from radiation levels to almost 10 1,.ds.

B - The 10 0 C rule for the arrenhius plot is a safe figure to use because it is widely known that silicone rubber has an electron-i volt activation energy level greater than 1.0, k

  • Verification for this statement follows:

The specific silicone rubber being used is CORRlastic manufactured by CHR Industries, Inc., an' Armco Company, New Haven, Connecticut.

A specification sheet on their product is attached.

COHRlastic shows insignificant-changes in durometer, tensile and elangation for our application after twenty-two hours at 205 C.

At this temperature it would take only 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to artificially age the equivalent of 40 years at 50 C ambient per the 10 C rule for half life. (See attached graph entitled "10 C COHRlastic Silicone Rubber Artificial Age").

We chose to age at only 160 C which intersects the aging time at 7.1 days. We actually aged the parts for 8 days.

t

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, B 'It may be of inte're'si to calcul' ate the E (activation energy

.t level) for this time - temperatbre relationship:

4

<40 years tl=

t = Conditioning time; 8 days X 1 yr. = 0.0219 yrs.

2 365 T = 50 C = 323 K T = 160 C = 433 K 2

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-k = 0.8617 X 10

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-3.82127 = 3.68888 + E

.8617X10-4 3 0023094 .003095

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(-

- .8617 10 4 (.0007865, E = 0.823 ,

Thus, we are aging as though the material had a low activation energy level, yet EPRI-NP-1558 appendix B shows all silicone i

L compounds run over 1.0.

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No. 14552- ,

l 1

Test Procedure ,['

SEISMIC VIBRATION TESTING OF

'VARIOUS RELAYS FOR STRUTHERS-DUNN, INC. ,

UNDER PURCHASE ORDER NO. 94033 i

J Prepared e @oM Bruce Esposi(o, Project Engineer Dathce,m/fd/99[

/~

, , Acton Environmental Testing Corporation 533 Main St., Acton, Massachusetts Reviewed by: zy ,b,!!A /$ Da te2 '/MT. 98 Richard Gilfoy, Chief Dyna'mics Engineer

! . Acton Environmental esting Corporation Approved by: h'h/ pid , (/A ' Date / 2 2 7 8 .

MarvinL.Jolf, President l Acton Environmental TAting Corporation l '

Approved by: / Date Struthers-Dunn Inc., Pitman, NJ l

,. 3 .h b

/ ,

1 --

l 12/27/78 l

BE/hmf

, CNvemONMENT AL ff N

, l ACTON h Comport ATeON

1.0 TEST ITEMS The following items will be submitted by Struthers-Dunn Inc. >

for seismic vibration testing at Acton Environmental Testing Corporation (AETC):

12 pcs. 219BBX207 125VDC Relay Drawing fB43038 6 pcs. 2190XB114 125VDC Relay Drawing #C43039 3 pcs. 236ABX128 125VDC Time Delay Relay

, Drawing #B28338 14 pcs. CX3865 Socket Drawing #A43222 1 pc. CX9992 $

_ _ _ Socket

_ _ _ Drawing

_ . . . . _ _ _ _ _ _ _________________________________ _ _ _$_ #C43228

@6 l 6 pcs. CX3948 Socket Drawing #A43223 l

4 L .

\

l gg,, 14552 ENVIRONMENTAL TESDNG Page h.*pACTOrJ (.

~

) con ~nr on 1

,{

3.0 TEST PROCEDURES f

3.1 Test Mounting b)b The relays under test will be mounted to a test fixture which will be securely attached to the biaxial, table of the AETC 45' seismic test facility. The use of the 45' biaxial table results in equal horizontal and vertical components. ,

t 3.2 Test Monitoring I

The relay will have contacts monitored for contact chatter in excess of 2 milliseconds.

One control accelerometer will be mounted on the test fixture.

3.3 Multiple Frequency Test A biaxial multiple frequency excitation will be

- applied to the relays under test for a period of thirty

~~

(30) seconds. The level of periodic pseudo-random excita-tion will be such that the Test Response Spectrum (TRS),

from the control accelerometer will envelope the appro-priate Required Response Spectra (RRS). The relays under test will receive the input six times in each of four bi-axial directions of excitation.

14552 No.

( ENVIRONMENTAL Page S  ?- TEsmo l ACTON

{

CORPORATION t

a The level of the first five inputs in each biaxial

{

' direction will be such that the TRS from the control accelerometer c puted at the Q=10(5% damping) will envelope the OBE RRS shown in Figure 1. The level of the sixth input in each biaxial direction will be such that the TRS computed at Q=10 (5% damping) will envelope the SSE RRS shown in Figure 1.

The relays under test will be subjected to the three different tests below, while the multiple frequency ex-t citation described above is applied:

- Non-operating mode j - Operating mode

- Transition 0

-. m l

l 14552 No.

l

( ENMRONMENTAL 4

[ mm~,

CORPORATION Page

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- -Wyle Report on Surge Withstand Testing of Struthers-Dunn Relays, *
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a ATTACHMENT /

ST.HL-AE-/4/7 2 tasa m n Foa cEviEn .N r a

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  • ME CMANICAL
  • SALANCE OF PL ANT .

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  • S OILE RINSSS l PLANT UTILITet S l

0 PL ANT Of stGN /  !

  • CONTROL SYSTEMS
  • E LECTRICAL WIRING CON OU47
  1. PAINT 8NG & COATINGS
  • C8vlL/STRUCTUR AL
  • NUCLE AR eSTRESS e ARCHITECTUR AL

. STAR,UP

  • CONSTRUCTION O NOT REC'O BV ENGRG
  • CLIE NT l

IDENTIFYING TITLE OF THIS DKUMENT l

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IMPORTANT

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l WOR K M AY PROCE E D V '

d' 2 RE vase ANO RESUBMs7 , [

WORK M AY PROCE E O '

I SUBJE C T T O INCORPO R ATiON OF CH ANCE S

'SE HTEL I tNO#C AT E O ENERGY 30 aE vise A~0 at Sv.M,i cone.

WORK M Av NOT PROCE E O 4C REveEW NOT REOuiRE D WOR K M AY P ROCE E O O OiSTminutiON at O O MO96012 f 3/B61

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l A rrAcHMcA.17 -A

- M- e..- - ,.-m.. , .. 'i October 29,1985 Reference.No.: 4801IH.02 Spang Power Control .

P. O. Box 457

' Sandy Lake, PA 16145

' Attention: Mr. Marvin T. Baker

Subject:

Results of. Surge Withstand Capability Testing of the Struthers Dunn 219XBX242-NE Isolation Relay for Spang Power Company.

References:

1) Spang Power Control request for proposal, dated 7/12/85.
2) Wyle Laboratories' Technical Proposal for Relay Test Program for Spang Power Control, No. 543/4023/GH, dated 7/23/85.
3) Spang Power Control Purchase Order No. K2200 F153,
4) Wyle Laboratories' Test Procedure 48011, " Test Procedure for Surge Withstand Capability Testing of an Isolation Relay for Spang Power Control," dated 10/24/85.
5) Wyle Laboratories' (Eastern Operations) Quality Assurance Program Manual.

Gentlemen:

In accordtsce with the referenced documents, the Surge Withstand Capability Testing of the Struthers Dunn 219XBX242 NE Isolation Relay has been completed. The test specimen l relay was subjected to the precribed Surge Withstand Capability tests and successfully demonstrated the ability to maintain coil integrity and relay operability throughout the test. A visual inspection following the test revealed no noticeable changes from the initial pretest inspection.

'~

The data collected during the SWC test is presented in Attachments I through 4 a'nd are briefly described below:

o Attachment I contains Photographs I and 2 showing the SWC test setup.

o Attachment 2 contains the Oscillograph recording of the Energized Coil

_ Configuration of the SWC test. -

o Attachment 3 contains the Test Specimen inspection Sheet, Data Sheets, and the Instrumentation Equipment Sheet from the SWC test.

l' o Attachment 4 coatains Wyle Laboratories' Test Procedure 48011,' dated '

October 23,1985.

RLv. h. Coutcrev for fue ISIa t .

SEE N5 s 3, s s,

  • 7.

PANEL i M ~

P. O.14926- #304 ITEM i 8 DOC. CAT. 26, f.

(

PAcc / W N 7000 Gowrnors Drie West. P 0. Dos 1008 Huntsville. Alabems 30807 St010051837 4411 Sf

_V b_ _ _ _ _ _ _ _

A TTAcH. A Mr. Marvin T. Baker Page 2 ,

Spang Power Control October 29,1985 Should you have any questions or comments, please feel free to contact the undersigned. -

Sincerely, WYLE BORATORIES Easter perations W nm D.Q.A-m sol 14gs Dary $. Johison ' '

' co e E/Hauer or Contracts Administrator Project Engineer

- ~

b. MM o Me -x-rf

/Flavous 1./ffinson G. Wayne Hight ' '

NEQ Test Fepartment Manager Manager Quality Assurance PANEL # AJA P. O.14926- #SoV ITEM i S DOC. CAT. 26. A wa- es Rev A

Arnen-A ATTACHMENT 1 f

PHOTOGRAPHS

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4 l PANEL f NA P. O.14926- # 30 Y ITEM i 6 nOC. CAT. 2 4,1 PA &E 8 C# A0 Fev A

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P. O.14926- "'/80 Y PHOTOGRAPH 2 6 DOC. CAT. 2/,,2 ITEM i THE SWC TEST SETUP O M Y ##

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A TTAcu - A ATTACHMENT 2 OSCILLOGRAPH RECORDING PANEL # NA P. O.14926- #80 #

ITEM # 8 DOC. CAT. 26 E pg, 5" es fS Rev A

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. . A rr-AC H - A DATd SHEET SPANG Power Company Customer WYLE LABOR ATORIES Specimen isolatien Relav Part No. 219XBX242-NE M *F 48011

.Te m aab No Spec. WLTp 48011 Yes Photo Report No. 48011-1 Para. 3.2 Test Med. Air Start Date 10/25/85 SIN Item 1.0 Specimen Temp. Ambient GSI N/A Test Title EAssues FUNCTIONAL TEST Acceptance Criteria not applicable, data collected for information only.

VISUAL INSPECTION  !

1. Holded Parts: nt
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l RESISTANCE MEASUREMENT READING l

- Coil Resistance (continuity check): r,, ff, y Q l OPERABILITY TEST

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- Applied Coil Voltage (measured): 12 A.O VD0_ l

- Coil Pulled in Chanoine Contacts 1

State when enercized! YES  :

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AWACHMENT 3 A r rACH - A DATA SHEET SPA M Power Company Customer ME LABORATORIES Specimen Isolation Relay Part No. 219xBX242-NE Amb. Temp. 77*F Job No. 48011 Spec WLTP 48011 Photo Yes Report No. 48011-1 Para. 3.3 Test Med. Air Start Date 10/25/95 S/N Item 1.0 Specimen Temp. Ambient GSI N/A ,

Test Title SURGE WITHSTAND CAPABILITY (SWC) TEST ACCEPTANCE CRITERIA: The integrity of the relay coil shall be maintained when a test wave per ANSI /IEEE C37.90-1978. Paragraph 9.3. and IEEE 472-1974 Paragraph 2 is applied to specific relay points.

BETWEEN CIRCUITS CONFIGURATION READING

- Coil Resistance - Post-Test A- 6. A4 K9 Post-Test B: C. R3 KD Post-Test C: 6.9'2. KD Post-Test D: (,.86 K D Roh e p A \s % <er kseb heNowe y Be%en C kts. %f.3 a vahn ACROSS N.O. CONTACTS CONFIGURATION

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- Energized Coil Operation Maintained when Surge Applied: YES PANEL # n n, l P. O.14926 . DOY Tested Byd le Date: /o-25-Br ITEM i 8 DOC. CAT. 26, f witness YIhEE Date: /o.25 75-Notice of Sheet No. I of I Anomaly McN # Approved .b b / o /r ds<

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S/N Item 1.0 SpecimenTemp. Ambient GSI N/A Test Title POST $WL FUNCTIONAL TEST Acceptance Criteria not applicable, data collected for information only.

VISUAL INSPECTION

1. Molded Parts: rf
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TEST PROCEDURE A rre m - A l l'

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October 23,1985

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TEST PROCEDURE FOR SURGE WITHSTAND CAPABUIIT TESTING OF AN ISOLATION RELAY FOR

, SPANG POWER CONTROL APPROVED BY PROJECT MANAGER- .

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/ . . Jo o APPROVED BY QUAUTY ENGINEER- / ht# . '

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COPYRIGHT SY WYLE LABORATORIES THE RIGHT TO REPRODUCE. COPY. EXHIBIT. OR OTHERWISE UTILIZE ANY OF THE MATERIAL

- . - - - _ _ __ _rv5ZC(#d 3_cafLRDD_OffSFtDOt90MCOJO9J@A @F wvLE LA_80RATORIES IS PROMIBITED. THE ACCEPTANCE OF A PURCHASE ORDER IN CONN

ATTACHMENT 4

. . Pasa No. li A rrAcH- A Test Procedure No. 48011-00 FOREWORD i

This document is divided into three (3) major sections:

e Scope e Test Requirements e Test Program J The section on SJco duir.es the objectives, tasks, applicable test standards and specTacations, 1 and an equipment description. The equipment description includes performance and functional specifications, along with the number of each to be tested. This section also includes a test sequence listing.

The section on Test Requirements defines all the parameters to which the equipment is to be tested. These parameters are based on the equipment's location and application in the nuclear power generating station. The acceptance criteria for the test program is

_ also provided in this section.

The section entitled Test Program provides the analysis and defines necessary test programs which meet the scope and test requirements defined in the first two sections.

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Paga No. iii 4 TTACH A Test Procedura No. 48011-00 TABLE OF CONTENTS Page 1.0 SCOPE 1 1.1 Objective 1 1.2 Applicable Documents -

1 1.3 Equipment Description 1 1.4 Test Sequence 1 2.0 TEST REQUIREMEN'IS 3 2.1 Acceptance Criteria 2 2.2 Test Temperature 2 3.0 TEST PROGRAM 4 3.1 Test Specimen Identification / Inspection 2 3.1.1 Test Specimen Preparation 2 3.2 Funetional Tests 2 3.2.1 VisualInspection 2 3.2.2 Relay Coil Resistance Measurement 3 3.2.3 Relay Operability Test 3 3.3 Surge Withstand Capability (SWC) Test 3 3.3.1 Purpose -

3 3.3.2 Transverse Mode 3 3.4 Post-SWC Functional Test 4 Figure 1 Surge Withstand Capability Test. Between 5 i- A Circuits Configuration (/(Transverse Mode only) >

Figure 2 Surge Withstand Capability Test, Across N.O. 6 l Contacts Configuration Figure 3 Surge Withstand Capability (SWC) Test, 7 I

Energized Coil Configuration PANEL #

MA P. O.14926- OM S nOC. CAT. 24.'2 l TEM i p, gg 73 ,,gg l WYLE LABORATORIES HuntsviHe Facihty Rcv A M

ATTACHMENT 4 Paga No. 1 g 7gg_ A -

Test Procedura No. 48011-00 1.0 SCOPE This document has been ptwpared by Wyle Laboratories for Spang Power Control and encompasses Surge Withstand Capability Testing (SWC) of the Struthers Dunn 219-XBX242-NE Relay for Bechtel Construction, Inc.'s South . Texas Project.

1.1 Objective The purpose of this procedure is to present the requirements, procedures, and sequence of Surge Withstand Capability Testing of the Struthers Dunn 219 XBX242-NE Relay.

1.2 Applicable Documents 1.2.1 Wyle Laboratories Technical Proposal for Relay Test Program for Spang Power Control, No. 543/4023/GH, dated 23 July 1985.

1.2.2 ANSI /IEEE Standard C37.90-1978, "IEEE Standard Relay and Relay Systems Associated with Electrical Power Apparatus".

1.2.3 IEEE Standard 472-1974, "IEEE Guide for Surge Withstand Capability (SWC)

Te sts".

1.3 Equipment Description

. This test procedure encompasses testing of the following relay:

Coll Catalog ite m Description Voltage Manufacturer Number 1.0 A Relay 125 VDC Struthers Dunn 219 XBX242-NE A

~

.~ 1.4 Test Wm The test program shall be performed in the following sequence:

o Test Specimen Identification and Inspection o Baseline Functional Test _

o Surge Withstand Capability Test o Post-SWC Functional Test PANEL f P. O.14926- O rrm a 8 DOC. CAT. 24.2 PAdvaE~ 17 or= 23 WYLE LABORATOMEs Huntsville Facihty Rev A

ATTACHMENT'4 Paga No. 2

,j Tcst Proc: dura No. 48011-00 2.0 TEST REQUIREMEN'IS 2.1 Acceptance Criteria _

The integrity of -the relay coil shall be maintained when a test wave per ANSI /IEEE C37.90-1978, Paragraph 9.3, and IEEE 472-1974, Paragraph 2, is app 3ed to specific relay points Juring the SWC Test.

2.2 Test Temperature The SWC Test shall be performed at normal, ambient temperature.

3.0 TESTPROGRAM 3.1 Test Specimen Identification / Inspection An inspection shall be performed upon receipt cf the test specimen at Wyle l Laboratories. This inspection will ensure that the test specimen is as described in Paragraph 1.3. Applicable manufacturer, model, part, and serial numbers shall be verified and recorded. The test specimen shall be labeled and tagged with Quality Assurance Test Specimen tags to facilitate identification throughout the test program.

3.1.1 Test Specimen Preparation Each test specimen shall be mounted to an 18" x 18" x 1/8" steel plate test i fixture that simulates the actual in-service ecnfiguration. Additionally, the test i specimen shall be inserted into Struthers Dunn Model CX-3966NE socket assembly before mounting to the test fixture. _

3.2 Punctional Tests Functional testing shall be conducted to verify proper specimen operation prior to SWC testing and at the conclusion of the test. These functional tests shall consist of a visual inspection, relay coil resistance measurement to verify continuity, and a test specimen operability verification test.

3.2.1 Visua1 Inspection The test specimen shall be visually inspected for any obvious physical damage using the criteria given below:

I 1. Examine molded parts for chips, cracks, melts, or other physical damage.

1

2. Examine metal parts for bends, warps, pitting, or excesive rust.

PANEL f P. O.14926- O 8 DOC. CAT. 26. A PAdi;E ITEM f /8 OF 23 WYLE LABORATORIES Riv A Huntsvme Fac.hty

n a m.n.~u. m Paga No. 3 g ,j Tcst Procedura No. 48011-00 3.0 TEST PROGRAM (Continued) 3.2 Functional Tests (Continued) -

3.2.1 VisualInspection (Continued)

3. Examine terminals for secure connections, insulation integrity, and, if crimp connectors are employed, adequate crimps.
4. Examine the specimen for any loose or missing nuts, bolts, springs, pins, or connectors.
5. Photograph the specimens as deemed necessary by the Wyle Test Engineer.

3.2.2 Relay Coil Resistance Measurement The relay's coil resistance shall be measured across its input leads and the measured value recorded for data collection purposes.

3.2.3 Relay Operabuity Test The relay coil shall be powered with its rated (125 VDC) voltage. Changing of-the contacts' state shall be verified by noting continuity through the normally open contacts when power is applied to the coll.

3.3 Surge Withstand Capability (SWC) Test 1

3.3.1 Purpose The purpose of this test is to show that a high frequency surge voltage applied to specific relay points will not degrade its operation.

3.3.2 Transverse Mode 3.3.2.1 Between Circuits Con 5guration l A surge wave of 2.5 kV and 1.0 MHz shall be applied from the Schaffner NSG 505 High Frequency Test Set between the relay terminals listed below. The test specimen shall be connected as shown in Figure 1. The tests shall be repeated until alllisted test points have been subjected to the surge wave. While testing in this configuration, the coil resistance shall be measured and recorded prior to l the first surge and after each successive surge application to determine if any change occurs.

l PANEL f P. O.14926- OY 6 DOC. CAT. 24, f iTE/A f PAGG~ /9 o/=~ N WYLE LABORATORIES RE.V A mamm. F.einiy

ATTAC10ENT 4

. . Paga No. 4 g g, j Test Procedure No. 48011-00 3.0- TEST PROGRAM (Continued) 3.3 Surge Withstand Capability (SWC) Test (Continued) -

3.3.2.1 Between Circuits Configuration (Continued) -

STRUTHERS DUNN 219 XBX242-NE Test Terminal to Terminal Wave Duration A 6 to 3 2 see B 6 to 11 2 see C 7 to 2 2 see D 7 to 10 2 sec 3.3.2.2 Aeroes Normally Open Contacts Configuration  ;

The test wave of Paragraph 3.3.2.1 shall be applied across all normally open contacts of the test specimen, one pair at a time for a 2-second duration. The coil resistance of the relay shall be monitored to determine if coil continuity is maintained. Any significant changes in coil continuity shall be noted. The test specimen shall be connected as shown in Figure 2 for this configuration.

3.3.2.3 Energized Coil Configuration The test wave of Paragraph 3.3.2.1 shall be applied between the contact pairs listed below for a 2-second duration. The relay coil shall be connected as shown in Figure 3 for this configuration, and energized with rated voltage during the application. The coil's continuity shall be monitored via sn oscillograph recorder and its operation shall be noted.

Relay Terminal to Terminal 219 XBX24-NE 2 - 11 3.4 Post-SWC Punctional Test The functional tests of Paragraph 3.2 shall be repeated folloiwng the SWC Test.

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Attachment 14 Responses to NRC Staff Questions regarding Review of the Component Cooling Water Pump Logic Diagrams; M. R. Wisenburg, HL&P, Letter to-Vincent S. Noonan, NRC; dated December 9,1986; ST-HL-AE-1840 L1/NRC/ae

ATTACHMES,T /f ST.HL-AE- /7/7 The Light mmPuy neos,e. tis ,ing & Power s P.o. sox 1700 Houston. Texas 77001 (713)228-92ii

- . ~ . _

December 9, 1986 ST-HL-AE-1840 File No.: G9.17 Mr. Vincent S. Noonan, Project Director PVR Project Directorate #5 U. S. Nuclear Regulatory Commission Washington, DC 20555 South Texas Project Units 1 and 2 Docket Nos. STN 50 498, STN 50-499 Responses to NRC Staff Questions Regarding Review of the Component Cooling Water Pump Logic Diagrams

Reference:

A. Letter - J. H. Goldberg, HL&P to R. D. Martin, NRC, dated July 11, 1985; Final Report Concerning Potential Failure of Non-Seismic CCW Tank Level and Flow Switches; ST-HL-AE-1284.

Dear Mr. Noonan:

During a conference call on December 1, 1986 a question was raised concerning the Logic Diagrams for the Component Cooling Water (CCW) pumps.

Two non-Class lE components are shown in the pump control circuit. Logic drawing SR20-9242040 has been revised subsequent to revision 3, held by the NRC staff. Revision 4 to this drawing deleted the non-class lE tank level switches from the pump control circuit, as discussed in reference A. A copy of the revised drawing is attached for your information.

Reference A also indicated that the non-Class lE flow switches would be upgraded to Class lE devices powered from non-Class lE sources. Cable separation for the switches has subsequently been identified as a concern with respect to fire protection. Operator action based on existing alarms has been determined to be adequate for both equipment protection and plant safety, without the automatic protection provided by these switches. Therefore, the CCW flow switches have also been deleted from the pump control circuit design.

In accordance with the project's configuration management program, interim changes which reflect this have been issued. The drawings will be revised when the physical change is completed in the plant.

Ll/NRC/hhh i

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. p is , ,t i ea )r "' " '~

8 Houston Lighting & Power Company F 17 Page 2 If you should have any questions'on this matter, please contact Mr.

M. E. Powell at-(713) 993-1328.

Very rt yours, bY.0 Deputy Pr ect Manage N?

THC/yd

Attachment:

1. Drawing 9Z42040, Rev. 4, Component Coo ing er Pump Logic Diagram l

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.. Houston Lighting & Pbwer Company Pile No.: C9.17 -

p.g 3 cc: 1 Hugh L. - Thompson, Jr.' , Director - T.V. Shockley/R.L. Range.

. Division of PWR~ Licensing -:A Central Power'& Light Company

. -Office of Nuclear Reactor Regulation ,.P.O. Box 2121

-U.S. Nuclear Regulatory Commission- . Corpus Christi, TX 78403

-Washington, DC 20555 Robert'D. Martin; O. Backus/J. E. Malaski-City of Austin

-Regional Administrator, Region IV. P.O. Box'.1088 Nuclear Regulatory Commission Austin, TX 78767 611 Ryan Plaza Drive, Suite 1000

Arlington, TX 76011. J. B. Poston/A. vonRosenberg City Public Service Board.

(*) N. Prasad Kadambi, Project Manager P.O. Box 1771 U.S. Nuclear Regulatory Commission San Antonio, TX .78296 7920 Norfolk Avenue Bethesda, MD 20814 ' Brian E. Berwick, Esquire

. Assistant Attorney General ~for Dan-R. Carpenter the State of Texas Senior Resident Inspector / Operations _P.O. Box 12548, Capitol Station c/o U.S. Nuclear Regulatory , Austin, TX 78711-Commission

.P.O. Box 910 'Lanny.A. Sinkin Bay City, lDC 77414 Ch~ristic Institute 1324 North Capitol Street Claude E. Johnson Washington, D.C. 20002 Senior Resident Inspector /STP.

~c/o U.S. Nuclear Regulatory Oreste.R. Pirfo. Esquire Commission Hearing Attorney P.O. Box 910 Office of the Executive Legal Director Bay City, TX 77414 U.S. Nuclear Regulatory Commission Washington, DC 20555 M.D. Schwarz, Jr., Esquire

-Baker & Botts Citizens for' Equitable Utilities, Inc.

One Shell Plaza c/o Ms. Peggy Buchorn

, Houston, TX 77002 Route 1, Box 1684' J.R. Newman,! Esquire i Newman & Holtzinger, P.C. (*) Docketing & Service Section 1615 L Street, N.W. Office of the Secretary Washington, DC 20036 U.S. Nuclear Regulatory Commission i

Washington, DC 20555 p Director, Office of Inspection (3 Copies) i.

and Enforcement U.S. Nuclear Regulatory Commission Advisory Committee on Reactor Safeguards Washington, DC 20555 U.S. Nuclear Regulatory Commission 1

1717 H Street Washington, DC 20555

(*) Includes attachment 1. All others without the atrachment.

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9 Attachment 15 Final Report concerning Toxic Cas Detectors; J. H. Goldberg, HIAP, Letter to U. S'. NRC; dated January 20, 1987; ST-HL-AE-1885 L1/NRC/ae

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ATTACHMENT

The Light I""'~

NM f Houston Lighting & Power P.O. Box 1700 Houston. Texas 77001 (713)228-9211 January 20, 1987 ST-HL-AE-1885 File No.: G12.350 10CFR50.55(e)

U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50 499

  • Final Report Concerning Toxic Gas Detectors On December 19, 1986 Houston Lighting & Power Company notified your office, pursuant to 10CFR50.55(e), of an item concerning the failure mode of the toxic gas detectors at the South Texas Project. HL&P has determined that this item meets the criteria for reportability pursuant to 10CFR50.55(e).

Enclosed is the Final Report on this item.

If you should have any questions on this matter, please contact Hr.

C. A. Ayala at (512) 972-8628.

.4 J. H. Goldberg Group Vice President, Nuclear THC/yd

Attachment:

Final Report Concerning Toxic Gas Detectors L1/NRC/wt/hg-1 sd /1g y *

' Houston Lighting & Power Company 8 FfifN .350 Page 2

.cc: ,

Regional Administrator, Region-IV M.B. Lee /J. E. Malaski' Nuclear Regulatory Commission City of Austin .

611 Ryan Plaza Drive, Suite 1000 P.O.' Box 1088 Arlington, TX 76011 Austin,' TX 78767

.N. Prasad Kadambi, Project Manager A. vonRosenberg U.S. Nuclear. Regulatory CommiJsion City Public Service Board 7920 Norfolk Avenue P.O. Box 1771 Bethesda, MD 20814 San Antonio, TX 78296 Robert L. Perch , Project Manager Brian E. Berwick, Esquire U.S. Nuclear Regulatory Commission Assistant Attorney General for 7920 Norfolk Avenue the State of Texas Bethesda, MD 20814 P.O. Box 12548, Capitol Station Austin, TX 78711 Dan R. Carpenter Senior Resident Inspector / Operations Lanny A. Sinkin c/o U.S. Nuclear Regulatory Christic Institute Commission 1324 North Capitol Street P.O. Box 910 Washington, D.C. 20002 Bay City, TX 77414 Oreste R. Pirfo Esquire Claude E. Johnson Hearing Attorney Senior Resident Inspector /STP Office of the Executive Legal Director c/o U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, DC 20555 P.O. Box 910 Bay City, TX 77414 Citizens for Equitable Utilities, Inc.

c/o Ms. Peggy Buchorn M.D. Schwarz, Jr., Esquire Route 1, Box 1684 Baker & Botts Brazoria, TX 77422 One Shell Plaza Houston, TX 77002 Advisory Committee on Reactor -Safeguards U.S. Nuclear Regulatory Commission J.R. Newman, Esquire 1717 H Street Newman & Holtzinger, P.C. Washington, DC 20555 1615 L Street, N.W.

Washington,' DC 20036 T.V. Shockley/R. L. Range j Central Power & Light Company

- P. O. Box 2121 Corpus Christi, TX 78403 1

Ll/NRC/wt/hg 1 Revised 1/2/87 t

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. Attachment ST-HL-AE-1885 c., .

. File No.: G12.350

, ~ Page 1 of.2~

South Texas' Project

_ Units 1 and 2,

Docket Nos. STN 50-498,'STN 50-499 Final Report Concerning Toxic Gas Detectors I. Summary On December 19, 1986,~ Houston Lighting & Power (HL&P) notified the NRC

-Region IV of a potentially reportable item concerning toxic gas detectors in the Electrical. Auxiliary Building' air intake. -The control circuitry design associated with these detectors is such that a common mode failure of the detectors or the circuitry could prevent isolation of the control room and Technical Support Center ~(TSC) ventilation systems during the

. presence of-a high concentration of a toxic gas. The detector actuation and alarm circuits are being modified to correct'the design. This deficiency has been determined to be reportable pursuant to 10CFR50.55(e).-

II. Description of Deficiency Two redundant,-non-Class lE toxic gas detectors are provided to protect the control room and TSC operators by isolating the control room and TSC envelopes in the event of high concentrations of toxic gas. The STP toxic gas detectors monitor for ammonium hydroxide, hydrazine, anhydrous ammonia and vinyl acetate concentrations above specified limits. Non Class lE Toxic gas detectors were used because fully qualified toxic gas detectors are not commercially available.

The circuit configuration is such that the instruments actuate only when energized. Therefore, a loss of power to the toxic gas detectors, or

-other common circuit or detector failure could leave the control room and TSC~ operators unprotected for the period between operability verifications specified in-the Technical Specifications.

III. Corrective Action r

The toxic gas detector actuation and alarm circuits will be modified such i

that the detectors fail in a safe manner, (i.e, to cause isolation of the

' control room and TSC envelopes and to initiate an alarm in the control room to alert the operators in case of malfunction or loss of power to the detectors).

Ll/NRC/wt/hg-1 J

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Attrchment ST-HL-AE-1885 l . File No.: G12.350 Page 2 of 2 IV. Recurrence Control Other non-Class lE control interfaces with Class lE control circuits were reviewed to identify any similar deficiencies. This was established to be an isolated occurrence and no further action has been determined to be necessary.

V. Safety Analysis

)

The function of both monitors could be lost as a result of a common mode failure, such as failure of the common power source. The function of isolating the control. room and TSC envelopes in the presence of high concentrations of toxic gas is provided to protect the operators. Had this item remained uncorrected, it could have adversely affected the safety of plant operation and therefore, meets the reportability criteria of 10CFR50.55(e). ,

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' References to-Previous STP Correspondence concerning Electrical Isolation Devices L1/NRC/ae

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Attachment-16 ST HL-AE-1917:

File No.: C9.15, J41.3, J9, J28

'Page 1 of 2 References To Previous- STP Correspondence Concerning Electrical Isolation Devices A. Wisenburg, M. R., HL&P;-Notes from Review Meeting with Instrumentation &

Control Systems Branch; Letter to George W. Knighton, NRC; May 13, 1985;.

ST-HL-AE-1239,- (These meeting notes document the NRC staff's initial question concerning electrical isolators (Item 5) and HL&P's initial response to this concern.)

B. Wisenburg, M. R. , HL&P; Closeout of ICSB Meeting Items; Letter to George W. Knighton, liRC; June 17, 1985; ST-HL-AE-1273. (This letter provides HL&P's response to Item #5, concerning electrical isolators, from the ICSB meeting notes of Reference A above.)

C. NUREC-0781; " Safety Evaluation Report Related to the Operation of South Texas Project, Units 1 and 2; -Docket Nos. 50-498 and 50-499, Houston Lighting and Power Company;" U.S. NRC; April 1986. (The-SER documented the NRC staff's remaining concerns relative to electrical isolation devices as Open Item #7.)

D. Wisenburg, M. R., HL&P; Response to SER Open Item #7 Regarding the Electrical Isolator Test Report; Letter to Vincent S. Noonan, NRC; October 31, 1986; ST-HL AE-1790. (This letter provided HL&P's response to the concerns itemized in b2R Open Item #7 on electrical isolation devices.)

E.- Kadambi, N.P., NRC; " Request for Additional Information on SER Chapter 7 Items - South Texas Project;" Letter to J. H. Goldberg, HL&P; January 13,-

1987; ST-AE-HL-91101. (This letter. requested submittal of several electrical isolator test reports, identified new questions concerning electrical isolation devices, and requested additional information concerning non Class lE control circuit interfaces with Class 1E control circuits.)

L1/NRC/ae

OVERSIZE

DOCUMENT PAGE PULLED i

l SEE APERTURE CARDS l NUMBER OF OVERSIZE PAGES FILMED ON APERTURE CARDS l

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APERTURE CARD /HARD COPY AVAILABLE FROM RECORD SERVICES BRANCH,TIDC i

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1 Attaclunent 22 Revised Final Report Concerning Potential Failure of Non Seismic CCW Tank Level and Flow Switches; J. H.~Goldberg, H14P, Letter to Robert D. Martin, NRC; Dated July 22, 1986; ST.HL-AE-1691 l

L1/NRC/ae

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7. ATTACHMENI dA ST HL AE- N/7 NE f Houston Lighting & Power PO. Box 1700 Houston. Texas 77001 (713)228-9211 July 22, 1986 ST-HL-AE-1691 File No.: G12.227, C2.2 Mr. Robert D. Martin Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 Revised Final Report Concerning Potential Failure of Non Seismic CCW Tank Level and Flow Switches

Dear Mr. Martin:

On February 7, 1985, Houston Lighting & Power Company notified the Nuclear Regulatory Commission of an item regarding the potential failure of non-seismic tank level and flow switches during an earthquake. This item was later determined to be reportable pursuant to 10CFR50.55(e). By letter ST-ilL-AE-1284, dated July 11, 1985 HL&P submitted a Final Report on this item. That report indicated that those Component Cooling Water (CCW) flow switches of concern would be replaced with seismically qualified switches.

Since that report, a design change in the CCW system has eliminated these flow switches. Attached is a Revised Final Report on this item which reflects the change in CCW system design and our revised corrective action.

, If you should have any questions on this matter, please contact l Mr. C. A. Ayala (512)972-8628.

1 l Very truly yours, J. H. Goldberg Croup Vice President, Nuclear THC/yd

Attachment:

Revised Final Report Concerning Potential Failure of Non-seismic CCW Tank Level and Flow Switches L1/NRC/ar.yd-2

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ST-HL-AE i1691.-

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Hugh L. . Thompson, Jr. , Director Brian E. Berwick, Esquire

-Division of PWR Licensing -'A- .

-Assistant Attorney General-for-Office of Nuclear Reactor Regulation the State of. Texas

,- U.S. Nuclear Regulatory Commission -P.O. Box 12548,-Capitol' Station Washington,JDC. 20555 Austin, 1DC 78711

'N. Prasad Kadambi, Project Manager .Lanny A. Sinkin' U.S. Nuclear Regulatory' Commission Christic Institute

'7920 Norfolk Avenue- 1324 North Capitol Street Bethesda, MD 20814 . Washington,'D.C. 20002' Claude E. Johnson- Oreste R. Pirfo, Esquire Senior Resident Inspector /STP Hearing Attorney

,c/o U.S. Nuclear Regulatory Office of the Executive Legal Director Commission U.S. Nuclear Regulatory Commission

' P.CN . Box 910 Washington, DC 20555-

Bay City, TX 77414- ..

Charles Bechhoefer, Esquire

' M.D. Schwarz , Jr. , Esquire Chairman, Atomic Safety &

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Baker & Botts Licensing Board one Shell Plaza U.S. Nuclear Regulatory Commission Houston, TX 77002 Washington, DC 20555 J.R. Newman, Esquire Dr. James C. Lamb, III Newman &:Holtzinger, P.C. 313 Woodhaven Road 1615 L Street, N.W. Chapel Hill, NC 27514 Washington, DC 20036 Judge Frederick J. Shon~

Director, Office of Inspection Atomic Safety and Licensing Board and Enforcement U.S.' Nuclear Regulatory Commission U.S.~ Nuclear Regulatory Commission Washington, DC 20555 Washington, DC 20555 Citizens for Equitable Utilities, Inc.

T.V. Shockley/R.L. Range c/o Ms. Peggy Buchorn Central Power & Light Company Route 1, Box 1684 P.O. Box 2121 Brazoria, TX 77422 Corpus Christi, TX 78403 Docketing & Service Section H.L. Peterson/G. Pokorny Office of the Secretary City of Austin U.S. Nuclear Regulatory Commission P.O. Box 1088 Washington, DC 20555 Austin, TX 78767 (3 Copies)

J.B. Poston/A. vonRosenberg Advisory Committee on Reactor Safeguards City Public Service Board U.S. Nuclear Regulatory Commission P.O. Box 1771' 1717 H Street San Antonio, TX 78296 Washington, DC 20555 Revised 5/22/86 L1/NRC/ar.yd 2

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The-Component Cooling Water (CCW) systen dazign'used surge tank level switches and flow switches which ware not spismically qualified. In the s

event;of.an earthquake, these switches could have experienced contact 'l chatter or apuriou.? closure,j Dueir.o the pump protection logic of the ( g" CCWS, the system p'.usps could'have T hcen jall tripped and inhibited from

. restart by the control room operator. '{ Restart could ba accomplished from the switchgear room t'ut additional' operator response time would have to be considered. Although further investigation revealed other Class 1E-equipment which could be affected by' an interface with non-seismic a equipment, the E m1 evaluation of this ites' concluded that only the CCW tank level and. flowhwitches could have hadutn adverse effect on the n' "

safety of plant operation. ,

t II. -Description of Deficiency .

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The CC'( surge tank level switches and CCW flow switches werv 'criginally designed to protect the CCW pumps from loss of suction pressure. These switches were not seismically.quali(icd ard could have experienced contact chatter or spurious closure curing'an earthquake. Due'to the pump protection function of the switches, some or all of the CCW pumps could have been automatically trippt,d and inhibite$ 1 from restart by the

-control room operator. This could have resulted in 'a" complete loss of CCW. Restart could have been accomplished from the transfer switch panels in the switchgear rooms, but this would require additional operator action time, i- , -

1 ii Our First Interim Report (ST-HL-AE-1203, dated March 7, 1985), stated

. that there are also;non seismically qualified pressure switches in the i - CCW header,and in each ECW pump discharge. sThese switches are connected .-

,2 7; to the CCW and ECW pumps such that on low pressure t% standby ECW and CCW pumps are automatically ste,rted, s" The functions of the autostart feature have bearL ovaf uated further.

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This feature is not required for any safett unction, f because even if the i_ switch failed to signal the pumps to start ou irw pressure, other safety grade signals provide necessary pump starts durir.g abuormal or accident l'

conditions. Therefore , this non-seismic interface with the Class lE purp circuits is not a safety concern and no upgrade is necessary.

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- El mentary r'awings of the: isolation relay panels and logic drawings V: 3= were reviewed to identify other non-seismically qualified devices that L.f - interface with Class 1E' devices. (See' Table 1 of the Second Interim

, , ~ Report, ST-HL-AE-1242 dated April 26, 1985, for a list of the interfaces .i

- reviewed.) This review determined that no safety problem exists with the' other interfaces.

_ . 3 III. Corrective Action.

The CCWi., urge tank level switches were provided to protect the CCW system pumps from/possible cavitation by automatically tripping the pumps when

. low-low-wa n : level was present within the tank. This function has been

- changed to eliminate the automatic trip but provide for annunciation of '

- low water level conditions in the control room. . The operator can then ~

verify the low level and trip the CCW pump (s) manually if necessary. Two (2) separate 1E level' switches at higher setpoints alert the operator to .

decreasing . A safety-grade level transmitter also provides ,sb.CCW purgeindication rge tank level tank level. for each CCW train in the control t room. T q ,

Our previous report (ST-HL-AE-1284, dated July 11, 1985) indicated that the CCW-system . design had been upgraded to provide Class 1E flow switches that were seismical.1y and environmentally qualified, but powered from i non-Class 1Euources. The qualification would ensure that contact chatter or spurious closure _did not occur and that the pumps were~not s- tripped'dur,tagla seismic event. These flow switches have subsequently

- been dela nd from the CCW system design,' since the low surge tank level

- alarms provide' adequate warning for the operator to prevent damage to the y ,

CCW pumps, i IV . - Recurrence Control

In order to determine whether a safety concern might exist elsewhere in the plant dne'to interfaces between Class lE and non-Class 1E devices, a comprehensive list of such interfaces was prepared. Each of these interfaces has been evaluate.d and no other potential safety concerns

, exist. Bechtel's Design Change Management procedure will ensure that

j. future system design changes are reviewed and approved by all affected engineering discipl,ines.

V. Safety Analysis' ET This item, were,it to have remained uncorrected, could have resulted in '

the temporar'y joss of CCW flow following a seismic event and could have adversely affe ded the safety of plant oper6tions. The item, therefore,

[I meets the reportability criteria of 10CFR50.55(e).

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