ML20236K122
| ML20236K122 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 06/30/1971 |
| From: | Boardman G, Carfagno S, Witcher L FRANKLIN INSTITUTE |
| To: | |
| Shared Package | |
| ML20236K121 | List: |
| References | |
| F-C3016, NUDOCS 8711090106 | |
| Download: ML20236K122 (70) | |
Text
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Attachment D
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...?'..'. . , Appendix A Page 1 of 27 (3 G1- 1
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F-C3016 3 .
Report .
l h, QUALIFICATION TESTS OF ELECTRICAL CABLES UNDER SIMULATED REACTOM C0fiTAINT.NT SERVICE CONDITIOfG by . -
G. R. Boardman S. P. Carfagno I L. E. Witcher i
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June 1971
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Prepared for f
Rome Cable. Divisign of Cyprus Mines Corr : ation Rome New York 8711090106 PDR 871103
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hppendix A l' _
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l QDR 6.14 REV"4 i
' Gi- 2 TABLE OF CONTENTS Section Nt24 Pgge,
- 1. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . 1-1
- i R 2. SAMPLE IDENTIFICATION. . . . . . . . . . . . . . . . . . . 2-1 i
TEST PROGRAM ... . . . . . . . . . . . . . . . . . . . . . 3-1
' 3. ;
. 1 3.1 Pre-Test Electrical Measurements. . . . . . . . . . . 3 ;
3.2 Initial Irradiation Exposure. . . . . . . . . . . . . 3-3 3.3 Electrical Measurements Following Initial Irradiation . . . . . . . . . . . . . . . . . . ..... 3-3 3.4 Pre-Condi ti ening . . . . . . . . . . . . . . . . . . . 3-3 3.5 Electrical Measurements Followir.g Pre-Conditioning. . 3-4 3.6 Steam / chemical-Spray Exposure . . . . . . . . . . . . 3-4 3.7 Electrical Measurements During Steam / Chemical- w
$ pray Exposure. . . . . . . . . . . . . . . . . . . . 3-7 3.8 Irradiation to 300 Megarad. . . . . . . . . . . . . . 3-7 Q'
3.9 Electrical Measurements Following Irradiation to -
300 Megarad . . . . . . . . . . . . . . . . . . . . . 3-10 j 3.10 Irradiation to 500 Megarad. . . . . . . . . . . . . . 3-10 3.11 Electrical Measurements Following Irradiation to 500 Megarad. . . . . . . . . . . . . . . . . . . . 3-10 i
- 4. CONCLUSIONS. . . . . . . . . . . . . . . . . . . .. .... 4-1 S. CERTIFICATION. . . . . . . . . . . . . . . . . . . . . . . 5-1 APPENDIX A - IRRADIATION REPORT APPENDIX 8 - LIST OF INSTRUMENTS USED IN OBTAINING ,
TEST DATA l 4
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Attachment'D Appin2iix A Page 3 of 27 i
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nDR6e"I4 M F-C3016 REV.4 Gir 3 LIST OF FIGURES HaureNo. ysz, 1.
7-Conductor Cable Electrical Measurement Connections. 3-3 .
2.
Arrangement of Cables in the Test Chamber . . . . . . . 3-5
- 3. ,
Typical Electrical Loading Circuit. . . . . . . . .' . . 3-6 i
'4.
Steam / Chemical-Spray Exposure Cycle . . . . . . . . . . 38 LIST OF TABLES -
Table _Mo._ Ntle Pace 1.
Electrical Measurements . . . . . . . . . . . . . .
3 5.
Electrical Measurements . . . . . . . . . . . . . . . . . 9
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- 1. INTRODUCTION hb 4 The,teste described in this report were conducted by The Franklin Institute Research Laboratories (FIRL), as part of a cable Qualification Test Program. The purpose of the overall program was to determine whether certain electrical cables manufactured by Rome Cable Division of Cyprus Mines Corporation would faction properly mder the environmental conditions expected to be present within the containment of a nuclear-fueled electrical power plant during normal
- service and following a loss-of-coolant accident. The test program included subjecting the cable samples 'to gamma radiation, thermal pre-conditioning, a prolonged exp'oeure to steam and a chemical spray, and a series of electrical measurements. m; p-Ti>
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l Attachment D Appendix A- .
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- 2. SAlfLE IDENTIFICATION The seven cable samples tested consisted of 2 seven-conductor cables and 5 single-conductor cables as follows:
Sample No. A 7/C 12 AUC 7 Str. , .030" EPR Insul. (C312), .060" Neoprene ,
Jkt. Overall (C414). I Sample No. B
- 7/C 12 AWC 7 Str., .030" DR Insul. (C312),
.060" Neoprene Jkt. Overall (C414) - Aged 7 days at 100*C.
Sample No. C
- l 1/C 12 AWC 7 Str., .030" EFA Insul. (C312), .020" Neoprene !
Jkt. (C417). -
Sample No. D 1/C 12 AWC 7 Str., .030" EPR Insul. (C312), .020" Bypalon h . .Jkt. (C181).
Sample No. E 1/C 12 AWC 7 Str., .030" EPR Insul. (C313), .020" Neoprene /
Jkt. (C424).
. Sample No. F 1/C 12 AWC 7 Str. , .030" EPR Insul. (C312), .020" Hypalon Jkt. (C181) Aged 7 days at 100*C.
Sample No. C .
1/C 12 AWC 7 Str. . 030" EPR Insul. (C312), .020" Neoprene l Jkt. (C417) Aged 7 days at 100'C. j
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Each cable sample was approximately 30 feet in length. l l
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XLP insulation J r9e 2-1 Tur rRANYUN INSTmlTE RIEEARCH LMORATORII:5
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- 3. TEST PROGRAM ;
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7 The test progran performed on each of the cable samples con-I.. sisted of the following sequences i
- 1. Camma radiation to a dose of 60 megarad.
- 2. Pre-conditioning exposure.
- 3. Steam / chemical-spray exposure.
. 4 Additions 1 gamma radiation dose of 240 magarad.
- 5. Additions 1 ganana radiation dose of 200 megarad on remaining !
l 1engths of cable af ter 3-f t of each specimen was cut off.
In addition, measurements of insulation resistance and chars-ing current were made on the samples as received, and after each of the above exposures. pp L
3.1 Pre-Test Electrical Measurements on March 29, 1971, measurements of insulation resistance (after the application of 500 V de for 1 minute) and charging current ;
(af ter the application of 6 kV ac for 5 minutes) were taken prior to >
the start of the test program. These measurements as v,til as those taken following the initial irradiation (Section 3.3) and following the pre-conditioning (Section 3.5) are given in Table 1. The single-conductor cables (except for the ends) were soaked in water at roca .
temperature for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> prior to taking the electrical measurements in these three cases. The measurements on the 7-conductor cables in these three cases were performed by connecting one electrode to conductors 1, 3, 5, and 7 and the second electrode to conductors 2, 4, and 6, as ,
illustrated in Figure ,1 3-1 na: rRANEUN DtSTmm: RIsr. ARCH 1ADORATORE:5 .
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- Figure 1. 7-Conductor Cable Electrical Measurement Connections l
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[ 3.2, Initial Irradiation Exposure -
Subsequent to the pre-test electrical measurements, the cable
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samples.were mounted in a hot cell and irradiated to an integrated dose "?m ;
of '60 megarad (equivalent air dose).* The cable samples were then re-turned to FIRL for further testing.
3.3 Electrical Measurements Following Initial Irradiation Af ter receipt of the irradiated cable samples by ,FIRL, measure- ,
ments of insulation resistance and dielectri.c withstand were taken in a manner identical to that described in Section 3.1. The results of these i measurements are given in Table 1.
3.4 Pre-Conditioning The cable samples were next pre-conditioned for a period of L.
6 bours at 150*F and approximately 100 percent relatf.ae humidity. This i was done by placing the cable samples in an air-cired ting ovet at ,
- This as well as subs'equent irradiations were performed by Radiation International, Inc., Farsippany, N.J., by exposing the cable samples to gamma radiation from a cobalt-60 radiation source. Appendix A ;
contains a copy of the irradiation report. i
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h 3-3 THE T1UuntLD4 DesTmtrE RESEARCH LADORATOREE
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150*F,'with a water pan inside the oven to a&intain the relative humid- i ity at 100 percent..
3.5' Electrical Measurements Following Pre-Conditioning
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Following the pre-conditioning, messiafetante 4cf insulation ,
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resistance and dielectric withstand were agals taken in 'a'$daner identica1I" '
to that described in Section 3.1. Results of thesu :ma;surements are also shown in Table 1.
' 3.6 Steaq/he$ical-Spray Exposure i
Following the slactrical asasurements described above, ,the cable samples were installed l' in a test chambeh for exposure to a steam /
chemical-spray environment. The cables were looped around a shelf of perforated sheet metal.. simulating a. ciable tray, with one loop of each cable extending to the bottom of the tank,'where it remained Lasersed in the chemical solution and steam'condensats Ehich collected below the drain level. Figure 2 shows the arrangement oi' the cables inside the y o
test chamber. Figure 3 shows a typical electrieel loading circuit of a 7-conductor cable sample.as indicated in the test chamber. The' sing:le A
conductor cables were energized in a simple series electrical circuit.
The test cycle was conducted as fE11cws: with the seven con-4
'Ll ductor cable samples carrying 6 asperas per seductor at 480 volts and '
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the single conductor cable samples carrying 25 ageres ac 480 volts, i stess was admitted to the test chamber tc/ increase the pressure to 66 ysig within 10 sec. A pressure of approximately 66 psig and a temperature of I. 's I
approximately 303*F were maintained for a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The ten-( perature and pressure were then reduced to 284*F/36 psig over a period 7
' of one hour, and further reduced to'247'F/15 psig over a subsequent two '
hour period. ' -
These conditions wers asiotsined for a period of 45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />, ' ' '
af ter which the temperature and praksura were further dropped over a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period to approximately 211*F/ 1.0 f.cig.
These conditiens were then main-tained for a period of 12 days. )
Throughout the test the t.eaperature vss maintained
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. as nearly as possible at values corresponding to saturat'e d conditions or 100 percent relative humidity. ,
Throughout the entire test, the cable samples were subjected t '
to a chemical spray consisting of a 2000 ppa solution of boron as boric acid buffered with sodium hydroxide to a pH of 9.0.
Figure 4 illustrates the above test cycle in detail.
' 3. 7 Electrical Measurements During Steam / Chemical-Spray Exposure Just prior to shutting-off the steam in the test chamber at the and of the steam / chemical-spray exposure cycle, a further series of insulation resistance and charging current measurements were,taken. At this point the ambient conditions were 1 psig/211*F. For the 7-con-ductor cable samples, the procedure differed from that used previously m;
(Sections 3.1, 3.3, and 3.5) in that the voltage was applied to each of yy j the conductors in turn while grounding the remaining six conductors.
As was 'done previously, measurements of insulation resistance were taken af ter the applicatica of 500 V de for a period of 1 minute and measurements of charging current were taken af ter the application of 6 kV ac for a period of 5 minutes. 1 nis series of measurements as well as thoss taken subsequent to additional irradiations of 240 megarad (Section 3.9) and 200 magarad (Section 3.11) are shown in Table 2. De resistances were of the order of 103 to 105 megohns and the charging currents were 2 to 4 mA.
3.8 Irradiation to '300 Megarad Subsequent to the above series of electrical measurements, the
, cable samples were exposed to an additional gansma radiation dosage of 240 I
megarad, as noted in Section 3.2 bringing the total dose to 300 megarad.
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Attachment D-
. = . . _ .w.._......--.
Appendix A Page 15 of 27 g QDR6.14 ci- is
*4 - -
T-C3016
~
3.9 Electrical Measurements Following Irradiation to 300 Megarad' Following irradiation of the cable samples to a' total dose of 330 megarad, insulation resistance and charging current measurem ents.
.were performed on the cable samples as described in Section These 3.7.
measurements were conducted at Radiation International, Inc
., by a re-preventative from FIRL.
The single conductor cables (except for the ends) were soaked in water for 6 hours et room temperature o prior t taking the electrical measurements; the 7-conductor dry. es weresampl kept The results of these measurements areAsshown in Table 2 . expected, the values of insulation resistance wereaconsider y higher bl than those,obtait ed at the elevated temperature ne the steam / chemical-spray exposure. ar the conclusion of .
} approximately the samme. The values of charging current were Three feet of cable was then cut off from each of the 30 - "
cable at the Rome samplesCable plant. for further physical measurementsr ormed that were to be pe
~ 3.10. Irradiation to 500 Megarad- E
'^
The shortened cables (approximately 27-ft long) wer L e then K submitted to an additional 200 megarad of gamma radiation
, bringing the t
1:: total cumulative dose to 500 megarad. y. 3.11 , Electrical to 500 Megarad Measurements Following Irradiation e Following the last irradiation dese, the samples w ere re-turned to FIRL and subjected to a final set of p' , Insulation resistance and charging current measurelectrical measurements.,\ ements were taken on the cables in a manner identical to that d escribed in Section 3.7, with 3-10
],
THE rRANnDr Destmnt RESEAACH LUCRA70RE3 ^
~ ~ ~
;, ..-::.... . = . = . - - - ==2---- -- - - - - ~ Attachment D Appendix A
- Page 16 of 27 l,
L QDRL6.14 . 6 REV.4 Gi- 16 '-c " 2' ' the single conductor cables (except for the ends) being soaked for 6 'l hours in water at room temperature prior to sedergoing the electrical measurements. The 7-conductor samples were kept dry. The, results of these measurements are shown in hable 2. Coe-pared to the preceding set of electrical measurements (section 3.9) the trend was toward lower values of charging current and higher values of insulation resistance. I l
. i
, j i
1 i Eh , i l 3-11 JI. s THE TRANEDI Di&mVTE RESEARCH LOCRAfoluES
. j
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Attachment D Eppandi:: A Page 17 of 27 m" QDR6;14 ] REV.4 t 1
. 1
- 4. CONCt.USHNS G1 -17 i
( Two samples of seven-conductor cables and five samples of i single-conductor cables identified in Section 2 of this report, and manufactured by Rome Cable Division of Cyprus Mines Corporation, were subjected to a series of environmental tests to determine their ability to withstand the conditions expected in nuclear-fueled power plant applications. 'The tests included an initial ganaan radiation exposure , to 60 megarsd pre-conditioning, and a steam / chemical-spray exposure. This was followed by further radiation exposures bringing the cumulativs dose to 300 megarad and than' to 500 megarad. The performance of the cables was monitored at each interval by measurements of de insulation resistance and ac charging current. -
- From the results of these tests, it was concluded that the cables can be expected to perform without loss of fianction under the conditions simulated by the tests performed.
All cable samples performed satisfactorily without loss of function, through all tests. Z1ectrical measurements performed at the conclusion of the steam / chemical-sprsy exposure, and again after exposure to a cumulative radiation dose of 300 megarad showed the insulation re-sistance to be of the order of 10 to 10 megohns, and the charging current
~'
to be 2 to 4 vA. Af ter all the cable samples received 300 megarad cumulative exposure and the electrical measurements were made, a three-foot length , was cut-off' from each cable and returned to Rome Cable for further test-ing. An additional dose of 200 megarad was then administered to each cable sample. The electrical measurements performed on all the cables was entirely satisfactory, with insulation resistance in the order of
. 10 megohns and charging current in the 2 to 3 mA range. 1
() 4-1
' rKE TRANrHM E4STTTUTE RESEAACH 1ADORATOREE
-) ,
~ Attachment-D- ]
Appendix A
-l Page 18 of 27- <!
. . i j
'1 1
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REV.4 . 1 i
- 5. CERTIFICATION G1 18 i i
The undersigned certify that this' report constitutes a true account of the tests that were conducted and the usults obtained. G.R. Boardman ,l Research Engineer
^
S.P. Carfago f f Senior Staff Physicisc N)
.ir. (JLL L.E. Witcher Test Engineer f Approved by:
Y M-M 7 ~~-- k k V W.H. Steigelmann, Manager 2r Zudar.s. Director Nuclear Syste s Laboratory &chanical and Nuclear . j i Engineering j i L . { tI 1 1 l l
)
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Page.19 of 27
& QDR614 . .
REV.4' G1- la ' F J
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i t
. - APPENDIX A m
f: IRRADIATION REPORT - k I
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-Appendix A m, . .. Page 20 of 72: =
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QDR6.14
- 0 l 1
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. NUCLEAM DIVISION May 18, 1971 Mr. W..H.-_Steigelman, Manager Nuclear Systems Laboratory. a Tranklin Institute Research Laboratory-
-20th and Race Streets ,
Philadelphia. Pennsylvania 19103 . l Dear Mr. Steigelmans. . The following summarizes parameters applicable to the irradiation of cable samples in FIRL Froject 18I-C3016-01. h..j Tourteen cables were received (see attached) and subjected to irradiation as follows: , Step 1 r Exposed to dose of 60 Mred. Step.2 Returned to FIRL for tests, and again-received i at RII. j Step 3 - Exposed to an additional dose of 240 Mrad. i Step 4 - Tested at RII by FIRL. Step 5 - Exposed to an additional dose of 200 Mrad. (Total dosage - 500 Mrad.) Irradiations were conducted using a 160,000 curie cobalt-60 source, with of -0.5" exposure in air at ambient temperature (6C-70*T) at a gressure Hg. Temperature of the cable during exposure reached approximately 900r, from r,adiant source heat. All exposures were conducted at a dose rate of 2.2 Mrad per hour. Samples were mounted individually during exposure, and were rotated and minimum turneddoseduring irradiation to assure a better uniformity. The - to'the cable core was 500 Mrad, with a maximum dose to outer edges of the cable to 550 Mrad. ' G) t
. m -. , ,, . . . .
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- Attachmant D Appendix h-
' ' Page 21 of 2.7- ']O, .
Mr..W. H. Steigelman May 18, 1971 _.g. & G1- 21 Dose rates at key points . wore nearuped with a'Victoreen Model 555 Radicon, with Probe-(HA-100). This instrument-is' capable of measuring both instantaneous d?se rates-as well as integrat'ed doses for specified periods of time. Dose uniformity over the
- cables ~ (maximum to minimum ratio) was 1.1. i
@R6.14 vari tr=27 7 =r . -
'l REV.4- xtDz- -x-in m.
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' George . D e tz' ' , !
Manager, Nuclear rvices i GRDiar 1
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Page 22.of 27; .
'9 -
QDR 8*14- - Gi- 22 .. l-REj/,.4. - 4 a L i r 3 APPENDIX B
'P"r LIST OF INSTRUENTS USED IN OBTAINI.1G TEST DATA i
4 4 i
.+
- d/
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,s..,..... Attachment D
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Appendix .A '. Paga 23 of 27 i
'G1- 23 cG LQDR6.:J4 F-C3016 R .4 i .
APPENDIX B
- 1 11.157 DF INSTRUMENTS USED IN OBTAINING TEST DATA
{~. I
- 1. 6 General Radio to. Magohmaster Type 1862-3, 0.5 to 2 x 10 gg ,,
500 Vdc. - 2. Beckman Tasuistion and Breakdown Test Set, Model 1000-AC/DC-ITS. - 3. Eoneywell-Brown. Electronik 2-pen recorder, Model No. Y153X(220-VV-1-IV-K-(C) (V), Ranges: . O to 500*F with type J thermocouple; O to 100 pcis with Giannini Potentiometric Pressure Transducer.
- 4. Honeywell-Brown Electronik Multipoint Recorder, Model No'
. 15305846-24-02-2-000-030-10 097, O to 500*F with Type T thermocouple.
9 , k (pr 9 t 4 t i
;i Tiiitxt -- mm ~
1 umumm 1
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, . . Appendix A-
. Page 24 of 27 3
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G1- 24 O* I I THE FRANKLIN INSTITUTE
.. . . RESEARCH. LABORATORIES )
,1 tut stm4 amin raansLin ransway . ~!
rustaattemaa. Fransvtvania totes . vattene : uns: 44s.tooo .2
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Asses ANacAt, AND Nue:JCAM ENUINRERIND DKl'ARTMENT ' August 4, 1971 !, Mr. Frank E. Lacese, Manager l Cosas. & Instr. Eng. Rome Cable Division of Cyprus Mines Corporation 421 Ridge Street i Rome, New York 13440
Subject:
Addendum to Final Report F-C3016. " Qualification Tests of Electrical Cables Under Sisrulated Reactor Containment Service Conditions" References Letter of June 21, 1971 from F. E. LaCase (Rome Cable) to ' S. F. Carfagno (FIRL). he
Dear Mr. LaCase:
In accordance with the referenced letter, we are pleased to submit here-with, the results of the qualification tests conducted by FIRL on various cable samples manufactured by Rome Cable, and not previously reported in the subject final report. ~ ~ ~ ~ ~- " -- The test program to which the cable samples were subjected was identical
- to that in the subject final report.
Sample Identification l I The five cable samples tested, and discussed herein included 3 seven- l conductor cables and 2 single-conductor cables as follows- 1 1 i Sample No. 2: 7/C 12 AWC 7 Str. , Inorganic Tape, .030" EPR Insul. l (C312).,.060" Rypalon Jkt. Overall (C181) j sample No. 3: 7/C 12 AWC 7 Str., .030" XLF Insul. (C506), .020" Neoprene
/ Sheath (C414), .060" "Neopiene Jkt. 'Overall (C416) j Sample No. 6: 7/C_12 AWC 7 Str. Inorganic Tape, .030" EPR Insul. (C312), )
'1060" Hypalon Jkt. Overall (C181) - Aged 7 days at 100*C ]
l
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. Appendix A
. Page 25 of 27 4
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Sample No. 112 1/C 14 AWG Sol. , .047" Special PR XLP Insul. Sample No. 122 1/C 12' AWC Str. , .030'" XLP Insul. (C500), .020" Iteoprene
- m. ' ' ' ' " I QDR8.14
- "~ 5 i Test Pr...es
, REV 4- -
Tables 1 and 2 are a chronological sumary of the measurements of insulation . { resistance and charging current taken on the cable samples during the j test program. The tables also indicate the Section in the subject final l report to which one should refer for further information on the test progras. 1 l Cenelusions_ Yrom the results of the tests previously outlined and further described in the subject final report, it was concluded that the five aforementioned cable semples can be expected to perform without loss of function under the conditions simulated by the tests performed. Certifiestion_ I j N undersigned certify that this addendum letter constitutes a true ] q mer.ount of the tests that were conducted and the results obtained.
- k. $. $MY::: N C. R. BOARDMAN Research Engineer Approved byn i
(.11TV 1 bM' , gl. ZUDANS, Director I l i ( l l l 1 j l l
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_ _ _ _ - . . . . . ~ . . . . . . . - _ . _ _ . - . - - Attachment D Appendix A Page.27 of 27 . 1,., . QDR6.14 H REY.4 c1_ 3 Table 2 ELECTRICAL MEASUREMENT 5 III
- i
. y l . l At Conclusion of After a Total Radia.
- After a Total Radia.
Steam /Chquical-Spray tion Oose of 300 tion ) Exposure 12l Mrad (3) Mrsd(Dese
- 4) of 500 l 1
Charging Insalation Charging Insulation Charging ( Insulation Resistance Current l Resistance Current Cable Terminal Connections Resistance Current (eA) (MQ) (aA) (MO) (sA) J Sas91e 1 !! (Ground) (Ma) 3 3 2.2 8.3 x 10 2.0 2 1 All others 8.5 x 10 3 2.0 8.9 x 10 3 1.9 i 2 7.0 x 10 3 2.5 9.2 x 10 3 2.1 9.4 x 10 3 3 2.1 '8.4 x 10 1.9 3 6.8 x 10 3 2.5 7.8 x 10 3 4 6.8 x 10 . I 2.5 7.9 x 10 3 2.1 8.6 x 10 1.9 3 l 3 6.3 x 10 3 2.5 8.2 x 10 3 2.2 9.3 x 10 1.95 3 6 6c4 x 10 2.5 8.5 x 10 3 2.1 8.2 x 10 1.9~ 3 7 6.4 x 10 3 2.4 8.0 x 10 3 2.1 8.9 x 10 1.85 i 3 0 7.0 x 10 3.01 3 1 All Others 9.6 x 102 3.2 2.0 x 10 3.3 5 2 5 3.6 x 10 3.0 2 7.0 x 10 3.3 1.8 x 10 3.3 [,[l 3 6.7 x 10 2 3,3 g,7 ,gg 5 5 3.3 1.1 x 10' 5 3.0 l 2 3.2 2.0 x 10 3.3 2.9 x 10 2.9 4 7.1 x 10 7.3 x 10 2 3.2 1.8 x 10 3 3.3 5.0 x 10 5 2.9 5 5 2 5 1.1 x 10 2.k5 6 7.1 x 10 3.3 2.5 x 10 3.3 5 2 3.3 1.7 x 10' 3. 3 4.5's 10 2.95 7 7.1 x 10 3 3 5.9 x 10 3 2.2 5.1 x 10 2.1 6 1 All Others 8.9 x 10 2.1 3 3 6.8 x 10 3 2.1 5.0 m.10 2.0 f 2 7.4 x 10 2.5 3 3 2.0 7.4 x 10 3 2.6 f.2 x 10 13 5.2 x 10 f 3 3 3 2.3 5.4 x 10 2.0 4 7.1 x 10 3 2.6 7.8 x 10 3 { 3 3 5.3 x 10 2.0 j 7.2 x 10 2.6 7.5 x 10 2.2 5 3 3 7.6 x 10 3 2.3 5.4 x 10 2.0 6 7.2 x 10 2.6 3 3 7.2 x 10 3 2.2 5.3 x 10 2.0 7 7.1 x 10 2.6 2
)
3 7.8 s 10 3,g 1 cromd 2.5 x 10 I 4.2 2.25 x 10 3.3 11 2.4 5.0 x 10" 3.8
- 4.8 x 10' 2.6
; 12 1 0round 1.5 x 10' '
}
J 1 5 4 l4 (1) Insulation resist 6nce measures af ter the application of 500 V de for 1 minute. i
.f Charging current measured af ter the application of 6 tV ac for 5 minutes.
- j.
(2) Electrieel measurements performed at a temperature of 211't. , j l
,.( See Sectione 3.6 and 3.7 of Su' a ject final report for further dwtails.
.3) Electrical measurements performed at a room temperature of approximately 75'r. f lj ")
!i - See sections 3.4 and 3.9 of subject final report for further details. j l! Ii (4) 11ectrical measurements performed at a room temperature of approximately 75'F. tee Sections 3.10 end 3.11 of Subject final report for further details, l i l (
i Attachment D j Appendix B j page~1 of 1 l L p QDR 6.14 1 421 Ridge Street Post Office Box 71 - /"'A j )f , Rome, New York 13440 TWX 510/243 9732 D COAPQRA7 ION Telephdne 315/337 3000 'I - l December 19, 1983 i Mr. Larry Gradin Ecotech 5418 Tonnelle Avenue North Bergen, NJ- 07047
- RE: Vermont Yankee Nuclear Generating Station
< Dear Mr. Grading Confirming our telephone conversation of December 19, the cables Roma manufactured for subject station back in 1968-1969 consisted of chem-ically crosslinked polyethylene ins 21ation compound and PVC jackets.
The cables were manufactured and tested in accordance with an EBASCO specification. The crosslinked polyethylene compound used was a carbon black filled low voltage compound which complied with the requirements of ICEA Standard S-66-524. It was essentially the same type of crosslinked _ polyethylene identified as C506 compound (Sample No. 3) in the ';g 'j Addendum to Franklin Institute Report F-C3016. I believe that you do have a copy of this document. I sincerely, F. E. LaGase, ! Product Engineering Manager FELads
- q. . .q . u m z,. ..+
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. '/,, ' . Attachment D 1
, +' .
.. ' Appendix-C:
Page l of 1 ..
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.owsmon or. . DS 3,
CYPRUS-MINCG CORPORATION-d N QOg g,{4 - Quality As vrance D:partment w Certi.icallm
- c- REVL4 U '
- VY ' 722h= l(Y7051$$ ,'
U- ESASCO
. VCPJiONT SERVICCSYAtlKEE lilC.- AGElli IJUCLEAR P0WCR CORP.
CasmaeA Onf.ae Na.
< 7 P.O. 80X 155 ' .
,,,,, c w o,.4 u Eltt:-01077 c - VEnl!Oll, VCl;;;0lli ' 0535's 8- o..e : 4 71- i MILL ORDER 1105. '81309, 81310 t, C1311L 4
[ , 4
,f - l, ; iVERt:01.T YAllKEE 110 CLEAR P0MER CORP. '
. m s' 'C/0 POWER STATiot! EUASCO AGilET ATTil: D..i. STEVEll5 -' PROJ. SUPT. ,
[, COVEnh0R HU.n* R0A0'
.t - - VERH0!!, ~ Veit tollT ..
Description App!icable SpecilIcation
-6' llom fio. ' Quantity
- A. ' '14',810i FT. * '3/C '12' STR. 030 XLP ".015"'SYl!.*~~ ~" U-60 f/ VYliF-IV-C 2C TUIST TAPE .01:5" SYll, JACKET.
. D.. 15,10ft FT. 7/C 14' STR. 030" XI.P .015" SYll. ' CX-60 & VYl:P-IV-C {
s TWIST, TAPE .060" CYl!. JACKET.- ..s s ,, 10,090 FT., 9/C 16 STR. .'03'0" XLP .015" SYll. CX-68 & VYKP-IV-C 2C : C.1
. Tut ST, TAPE .060" SYti. JACKET.
E ' E, 10,204 FT. - 5/C- 9 19/22 '.030" XLP .015" SYll. CX-63 & VYliF.-IV-C 2C TWIST, ~ TAPE .060" PVC JACKET. SEE PME F2a 1
. ).'.
I he'reby certify that tlic matetial deuribed above was inspt'eted under my cencral supervision and complie s with the test requitu asinterpret e t.y of- CX-CS & VYl!P-IV-C 2C , f
- Rome Cabic Quality / sturanco Procedures prior to bcinc ptsacd into str,th or relcased for shipment. .
Test records will belept on file Two years, from date of test, and will be made avaltab(c for examination try authorired personn upo.. l. I. request,-
}; * , ,,
7 Signed l. .
- hf&I .
Title . II'I 7{. f*V ff6VI SOIS, 9.he j
Attachment D1 Appendix D Page 1 of 5 DT1 FACILITY: Vermont Yankee TYPE: BWR QDR NO.: COMPONEN1: DESCRIPTION 6.14. Revision 5 Power and Control Cable AND SERVICES:
, Control.and Power l l
MANUFACTURER: MODEL/ SERIAL NO.: . Service Rome Cable.(Cyprus) XLP/PVC/PVC i XLP/PVC ! l PARAMETER: QUALIFICATION STATUS:- !
-Temperature Qualified REMARKS:
For Worksheets ELEC-4, 6, 8, 11, 12,'13 I REVIEW l l As indicated on the worksheets, the subject cables are located in primary t containment, the steam tunnel and various areas of the Reactor Building. l Normal Temperatures - In Primary Containment l 1 The average temperature for the drywell is 1850F (850C) per Section 7.0 of the EQ Program Manual (NOTE: The subject cables are not located above Elevation 315' of the drywell). l The power cable in primary containment is for motor-operated valves as described in the Operating Time Section (Tab DO). Motor-operated valves have a motor operating time typically of two minutes or less (see QDR Page DT4 I which is written by Limitorque, the Vendor for Vermont Yankee Safety-Related s MOVs) and cycle very infrequently, the number of cycles being enveloped by the ' typical 2,000-cycle qualification used for MOV qualification (QDR Page DT5). l Because of the significant thermal inertia of cable insulation which is represented by data in IEEE Standard 242-1975, " Recommended Practice for Protection and Coordination of Industrial and Commercial Power Systems," Chapter 11, Part A Cable Protection, Figure 157 (QDR Page DT6), the smallest l cable will have an insignificant temperature rise even if we were to consider stroke times of as much as 5 minutes. l Even if each valve were to be "on" for a full 5 minutes for 2,000 cycles for maximum rated cabic temperature (ignoring thermal inertia), the total "at-temper.ature" time would be much less than one percent of plant 40-year , life: { 1 (2,000 rye x 5 min /cyc)/40 yrs x 1.yr/365 days x 1 day /24 hrs x i 1 hr/60 min x 100% '
= 104 min /2.1 x 107 min x 100%
1 7 = 0.048% [ i
Attachment D ; Appendix D j Page 2 of 5 m DT7
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Atrtachment D New Generaflon { [ [4 ,, 1 a e, m m
%% N7 aq & W.% g,. 7 Appendix D VULKENE SUPRE
. [ _.rc ..y .
Page 3 of SOWER AND CONTROL CABLE
* ~ c '4 '* * ' ' > "
RE..C..TRI C, - .~.;;; Ouslihed to IEEE Stds.' 323 74 and 38 Is'SENEBAL .
,hI fy'n,'3 0, p /
i.i
>p o
7.- Product Data "" J-DFV. 5 l
cable and $155508 7 conductor No.12 AWG 600 Volt THE PRODUCT e ntrbl cable which qualified the GE line in the 0 2000 volt General Electric's New Generation VULKENE SU. ca eg y.
PREME flame resistant, single and multi conductor power , 9wn in Table 1, the VULKENE SUPREME cable cables and multicon,ductor control c, ables are available for product line comprises single conductor 600 Volt and 1000 use where cables with a non chionnated Gar,ne resistant Volt control cables in the most commonly used sites and insulation are desired.The new cables rated 90 C, areinsu- conductor str andings. Both the.600 volt and 1000 volt rated 4 lated with VULKENE SUPREME a non chlorinated control cables are available with two or more conductors. version of General Electric s flame resistant, filled, chemi- cable jacket wall thicknesses and cally cress-linked polyethylene. The insulating matenal Overall weights diameters'from for cables two through 37 conductors are has excellent thermal and electncal properties and out. standing resistance to moisture and chemicals. Aam a P n h@ 18 d %. W him Inf rmation on control cables with more than 37 conduc-The New Generation VULKENE SUPREME non chlor- t rs can be supplied on request. Insted insulation on individual conductors meets the requirements ofIPCE A Publication Number S 66-524, Par. TABLE 1 3.6. The overall jacket, either Hypalon* or GEOPRENE!, VUI.KENE SUPREME Power and Control Cables a General Electric flame resistant formulation of Neo. c enerai ti. cine prene is also resistant to ozone, oil, neids and alkalis and meets the requirements of IPCEA Publication N'o, S 19 81. $o]*f,' SP'ctegyn
, , As N'a$' M *$'
Par. 4.13.3. Vertical rack flame tests on GE's New Generation ecov susasic uc pe*er E'wNr'[1occucu VULKENE SUPREME Da , ,,,, ,,,, ,,c g , ci,,, , keted 7 conductor No.12 G and AM,me 7 conductorresistant No.16 AMGEOPRENE G ecov jac- susessi 90.., .s A w einrv 7so ucu incE A c>sss a control cables were conducted et the Underwriters' Labo- roon sosasis uc po*er m Awo tnrv icco ucu ratory, Inc. facility located in Northbrook, Illinois. The .ts. i(12. to Awa e h tests conducted wen similar to the vertical rack flame test described in IEEE Standard 3S31974, incorporating the nbbon gas burner, except the trays of cable were burned ecov iocov sussses susseos ingr is s n e,s som met.oAwc q q with the flame source rated 210,000 BTU /HR output and 400,000 BTU /HR whereas the IEEE Standard 3S31974 requires a name source rated 70,000 BTU /HR. Tests were CONSTRUCTION conducted with cables random laid to 40% fill of the cross. Conductors used in General Electric's New Generation, sectional area of the cable tray. The flame source was VULKENE SUPREME cables consist of 7 or 19 strands of positioned to maximize the destructiveimpingement of the tinned, soft copperin control cable constructions and bare
'0 I a ition Ge eral Electric has conducted in its Wire n m It c nd t rpo er ab es and Cable Department test facilities vertical rack flame Individual conductors are insulated with VULKENE tests similar to the tests desenbed in IEEE Standards 353- SUPREME insulation, a non chlorinated, filled, cherni-1974 incorporating the ribbon gas burner as the Came cally c.ross l. inked po.lyethylene. C.olor coding on control source (cables spaced /: cable s diameter apart) except at cable is available with solid color insulation (with tracer-210.000 BTU /HR on single conductor size No.14 AWG SI. recolor identification for more than 6 conductors) per 57279 Type SIS switchboard wire, and sizes No,2 AWG IPCE A Method 1 or pn,nted coding on blackinsulation per and 500 MCM SI 5SS12 2kV power cable. The test arrange- IPCE A Method 3. Multi conductor power cable ts available ment and test parameters for each specific Game test and with solid col,or-d insulation or colored , hash marks on cable construction is shown in Table 6. black insulation for identification. Multecenductor con-Finished cables were subjected to carefully controlled structi ns are assembled with nonchlorinated flame resis-tests suggested in IEEE Standards. The tests were normal tant fillers as required, and tinned soft copper ground vdres life, design basis event, post design basis event, and flame when appropriate, then covered with a core binding tape test. These products satisfactorily passed the normal life and an overall GEOPRENE or Hypalon Jacket. Standard qualification tests, the quali5 cation tests under simulated jacket color is black with or without hash marks. Two reactor containment service conditions, and the combined conductor through twelve conductor control cables are BWR PWRioss of coolant accident simulation (LOCA)for available with solid color GEOPRENE jackets on special a duration of 110 days per IEEE Standards 3531974 and rder. Smgle. conductor power cables are available with 323 1974 and are fully qualified to these IEEE Standards. s lid colcr insulation.
The representative GE cables subjected to these tests were S1 55810 single conductor No.12 AWG 600 Volt power mc *onime-s' o w = ::: r - Data subject to change without notice.
~
Cafi . WIRE AND CABLE BUSINESS DEPARTMENT BRIDGEPORT, CONNECTICUT 06502 _'L. ay*** fr-
o.,
4)
'y _.
g
reattachment D Appendix D l PD.80 Page 4 of 5 DT15
.Naw Gonerdlon \
VULKENE SUPREME'" ! 3 POWER AND CONTROL CABLE PRODUCT DATA
.h Non Chlorinated Insulation Oustified to IEEE Sids. 323 74 and 383 74 Page 4 of 18 l
June 30,1977 ODR 6.14
, , REV. 6
- o QUALIFICATION TESTING PER IEEE Y l' STANDARDS 323 74 and 383 74
\ ' vu$NiUE:
The VULKENE SUPREME insulated cables that were (""*"a*
- subjected to qualification tests were constructed as shown , , .
In Table 3. The cables are rated 600V. im no ...
~"' a" TABLE 3 CONSTRUCTION C omponent Control 6 u Fower st2 AWG,7 strands tinned copper Conductor e t 2 AWG,7 5trand tinned copper f h '88'C
.c30 NoncNorinated insulaleon .c30 NoneNoranated na e VULKENE SUPREME VULKENE SUPREME y ~
~
Assembly 7 Cond. Fillers w. Polyester Tape onrau.cael .oso oEopRENE or HYPAt.oN
- w. '
" " " " ,1 ,
Aging Characteristics '""* To establish the aging characteristics of the New Gen. eration VULKENE SUPREME, slabs of the insulation Fig. 7 were aged in an air oven at 136'C,150*C, and 160*C and
,, percent retention of original elongation was measured, a
- Aging curves were plotted including mean values and 95 From the aging curves (Figure 6) at 65 percent retention O per cent confidence limits. of original elongation, time in hours at 136'C,150'C and (*' 4 160*C, was obtained and these points were used to estab. '. i IEEE Standard 383 1974 states that a minimum of 3 lish the Arrhenius platin Figure 7. An extrapolation of the j dsta points including 136'C and two or more others at test data shows a time of over 350,000 hours (over 40 years) least 10*C apart should be used in developing the aging data. The criteria to establish thermallife was chosen by at 90'C. Thermal aging of samples for qualification test.
GE as 65 percent retention of original elongation. ing was selected from the Arrhenius plot. GE selected an aging time of 125 hours and aging temperature of 165'C. AGING CHARACTERISTICS This exceeds the requirements of the IEEE Standard Nonchlornated VULKENE SUPREME which states that the aging time must be 100 hours do' minimum. Note that aging at 121'C for 165 hours (7 days) does not come close to the Arrhenius plot. At 121*C,over 3000 hours , of aging time would be required to fall on the Arrhenius
* ' N' } ,.c plot. Aging for 125 hours at 165'C was used for all qualifi.
................ . ....M.'.S.'.'*".... cation testing.
I Normal Life Qualification The normal life qualification test is designed to demon. d strate that the cables are serviceable for the design life when subjected to the combination of thermal aging and
,e ,
radiation to simulate a 40 years time period. Four sets of samples were used. (Two sets with thermal
)* .-c aging and two sets unaged.) They were mounted on 20-inch diameter mandrels and exposed to gamma radiation l
- - - ( from a cobalt 60 source to an accumulated air. equivalent 0 8 ' e e o u w e e ao 22 dose of 220 megarads at an average dose rate of 0.54 Trae (Maurs e 00)
Fig. 6 m,. a.:n,..c m . a ..,....n.
Attachtnent D
. . Appendix D Page 5 of'5 DT16 PD 80 New Generation VULKENE SUPREME
- PRODUCT DATA POWER ANDNon. CONTROL Chlorinated insulati.
Qualified to IEEE Stds. 323 74 and 383 74 CABL Page 5 of 18 June 30,1977 l
, ODR 6.14 l REV. 5 I megarada per hour. This radiation dose meets that sug. 5.......-.,-
gested by IEEE Standard 3831974 including a 10 percent margin suggested by IEEE Standard 3231914.The radia. tion dose is equal to the radiation intecrated over the g=l,; a
' i expected plant life plus the radiation dose of a simulated 6 *"*"* -~'- aa*'-a 'a aaaa" I'oss of coolant accident.
uad
, 6 6 e l ,,,,,,, ,,,
Design Basis Event t 6 A typleal pressure test vessel (Figure 8) was used to test electrically loaded cables. Temperature and pressure were h a { ~~ I
==,.,.,.a-,' \ ' gh, varied in acordance with the temperature pressure profile, Figure 9, as prescribed in IEEE 323 74 for 110 davs to ,
g , ,, ,, ,, ,, ,,.\ t [,,, . , qualify for boiling water and pressurized water reactor -3 ,u ,g;,,, 9 4 e Oe.Cg ,a eats S.,:,; _ .
,sn.
? ]g,. . : n!'s b u a Oe .s*-
p,M, I- $
- 4, < i f - - - - ~ . O 3.x
_ _'C 98G s
),
r. 88 f.n2-
.G
-Q .
*\.,['$
- Post Design Basis Event L '[' h 'AG.N 'g .( ,N , ' After samples had been subjected to the temperature N,
- 1. N..N pressure profile, they were removed from the 20x mandrels, 3 s, I <
!] straightened, and each sample was reverse wra'C'
. i around a mandrel with a diameter 40 times the as - N i'
# a
', diameter, immersed in water for one hour and then given a '
a . high voltage withstand test of S0 volts per mil ofinsulation l/h. ,.J
*)
l}; , hG ,
* :,e '! ' thickness for 5 minutes. All GE samples passed the test.
./ [ #- ' j' , . This test is called the Post DBE test and demonstrates that the samples can be handled and bent and still main.
e
..L [ds/ *
' .' / l tain electrical integrity after having gone through the temperature pressure profile.
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. "n.
Fig.8 conditions. Samples were continuously sprayed ve'tically r upward for the first 24 hours with a solutien of the following composition at a rate of 0.15 (gal' min)!ft' [6.1 (liters! minim') of spray area: 0.28 molar H. BO,f3000 parts per million Boron) 0.064 molar Na, S, O, NaOH to make a PH of 9.5 to 11 at 77F tabout 0.59 percent) Insulation resistance was measured periodically as shown on the profile in Figure 9. ) v ;' Darc saject to thayr utrhour nonce. L_____ ____
4 Attachment D
. Appendix E Page 1 of 9 i- DR1 l h FACILITY: Vermont Iankee . TYPE: BWR QDR NO.: .
COMPONENT: DESCRIPTION
-6.14. Revision 3 Power and Control Cable AND SERVICES:
Control and Power , MANUFACTURER: MODEL/ SERIAL NO.: Servics . Rome Cable (Cyprus) XLP/PVC/PVC . PARAMETER: QUALIFICATION STATUS: Radiation Qualified REMARKS: For Wor'ksheets ELEC-4, 6, 8, 11, 12, 13 REVIEW The cables have been tested to a total radiation dosage of 5 x 108 rads, as stated on QDR Page G1-20 of Cyrpus (Rome) Test Report for Qualification. The worst case radiation dose which these cables are subject to is 7 x 108 rads TID es indicated on Worksheet ELEC-4 (QDR Page B1). This value is for cables installed inside primary containment. NOTE: The tect value envelops the radiation requirement of 5 x 106 rads for the steam tunnel (Worksheet ELEC-6, QDR Page B4) and 2 x 10 7 rads for the Reactor Building (Worksheet ELEC-8, QDR Page B7). The data in Section 7.0 of the EQ Pro ram Manual for worst case drywell is 7 x l 108 rads (samma plus beta) and 8 x 10 rads gamma (beta shielded) as shown in Section 5.0 of the EQ Program Manual. Therefore, beta contributes 6.2 x l 108 rads to the total radiation dose. The DOR Guidelines, Paragraph 4.2, appropriately states that, " Beta radiation doses generally are less significant than gamma radiation doses for equipment qualification. This is due to the low penetrating power of beta particles in comparison to gamma rays of equivalent energy." The DOR Guideline goes on to explain that a 30 mil insulation would reduce beta by approximately a factor of 10. Data from the Specification for the subject power cables (QDR Tab C3, QDR Pages G3-3 to C3-4) indicates that the minimum insulation thickness for any cable is 45 mils of insulation and 30 mils of jacket for a total thickness of 75 mils. For review, the major dose reduction factors are determined with a i 1
, ., .a- '
' Attachment D ,
Appendix E Page 2.of 9 DR2 ., ODR NO. 6.14 REVISION 4 g' l i
. rather conservative use of only a small fraction of credit available used as f
described below: i Raceway Credit As described in Chapter 8 of the~ Vermont Yankee FSAR, the cable routings of
- safety-related cabling is in rigid conduit or cable tray. NUREG-0588 allows 50% beta reduction credit as shown in Paragraph 1.5(9), QDR Page DRS.
Jacket Credit
- As described in the Technical Specification, the minimum jacket is 30 mils' (QDR Page G3-5) with a PVC jacket. Per IEB 79-01B, this thickness allows a reduction to 10% of'the total beta dose. As the primary purpose for the ;
jacket is insulation protection during installation with no electrical function,'its degradation due to beta is not significant to' safety function. 1 Consequently, the total beta dose of 6.2 x 10 8 rads can be reduced to 0.31 x 108 rads at the jacket insulation interface as follows: i Total Beta at the Insulation = Total x 0.5 Factor for Raceway x 0.1 Factor for Jacket
=.(6.2 x 10 8) x 0.05 :h'i
= 3.1 x 107 ,
Consequently, the total insulation radiation dose will be beta plus 8 x 10 7 rads or 1.11 x 108; rads total integrated dose. 4 Specific YAEC Beta Reductien Data Conservative beta reduction data which allows margin in excess of IEEE Standard 323-1974 values is provided on QDR Pages DR5 to DR8. This data which l takes no credit for raceways indicates a value for TID of 1.3 x 10 8 rads (QDR Pages DR7 and DR8) af ter "self-shielding" of 30 mils (the minimum jacket
~ thickness).
IEB 79-01B Data i Using just a factor of 10 reduction in beta previously described as allowed by , IEB 79-01B, a 30 mil jacket reduces the beta shown in Section 5.0 of the . j Program Manual to 6.2 x 107 rads. 1 The actual dose experienced by the cable will then be 6.2 x 107 rads (gamma) I or 1.42 x 108 rads (beta plus gamma). This is the larger of the three TIDs determined. l l
, _.39 -
- r J Attachment D -'
([! Appendix E' 7- '/( .
, Page 3 of 9 l
- )'.?y, ;
p . v. EPM ". ODR NO.iii.14-
;REVI!Q0N 3-g -
l
/- ;
i
,. J , MV .i
;Y
, l'
' ,i..
Consequently, based on the above approaches, it[i$ 59aconable to take creditf I!'s( for beta ' reduction to at -1sast' 6.'2 x 107 radd frer; 6.2 x 108 rads for a D-
- s. ". .i d' total samma plus beta dose c,f 1.42 x 108 radv. 'It is reasonable to accept s 0[f-(.
these. cables as qualified it.e., as indicut.ec.in'the DOR Guidelines. Appendix C, substantial. doubt does not' exist as to the qualification of these. cables). '
.The test value en'Uelops the requirement.with.the following margin.:
i Margin = [(Capability - Requirement)/ Requirement 1 x 100% l
, ,1-
= [(5 x 10 0. !1i42 x 108)'/1.42 x 10 8] x 100%-
i
= 252%
s i Conclusion Qualified.
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+ # p age. dix 4 ofe.-
9 NUMEG 0588 ! jfg ' '
,p Rev.'1>
QDR 6.14 .,., of 1, . gf.h,A,q f p e@. j f ,. '%'; g;. u ;1 < . REV 3 _
'nQ. b __
- ,www.,.
'o' 'f)lV Il _;
. =
n,, , 1:?'. ' (ls}<l$ i' 's s' x - O i
%. nterim1Sta9 Position on
- f Environment' Qualificatioft 6f e -
tr o.iSa%y:Re"s;ted Electrical Ec,uioment"
-j 4,;>
);.; '
s . Includng Staff Resoonses to Pudfis Comments i l Resolution of Generic Techriical ActNky A 24 -- - M-
, f. , t_ _
Manuscript Completed: November 1980 (. g, q / // 10 18 Published: Jufy 1981 - ./- ' l,. A. J. Stukiewicz. Tasi Mabger , j
' ' :c' Division of Safety Technology '
.i Office of Nuclear Reactor Regulation '
l q J S. Nuclear Regulatory Commission o y sy& ,/ashington, D.C. 20555 * ;;'-
. y, (. ,
iti m o2 . );;,)k h ,,! ;. + ..,, ' m, P'
, ,f a f '
( @W/
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9o Jt, I' I l f!d o _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
< .MglW$g ".
i f jf : 7< . - p[, - - - - - c ue y pi. W - th.p'z.Q . JAttachment'D g g;d!jhj.h 3 .9 ' " Appendix E u Page 5 of 9 p,;J(}.} y . e / Ay ,7 . . , 5 QDR; 6.14 W Q? w$ M W up
;.v '
[a 9; y$\a.. REV .3 - - as 3 ', , & oV >'# w ;
! ; CATEGORT T1
,~-!?ATEGORY ( -lI..
h'f Appu aw.e to squienent ee lified in . l
$ ' Appuesbfie Mfient custs Y Y '
t Accordance artth IEEE Std.,32.11971 j Accordance, w@ /pf. Std. 324 f4 s, y.; p, 1 sueldien sof as eq.a,.e. reducee ae-w j _
-d.se a.4 a.se ,at..
f y' 5N
-(7) Ter wasM elded equipneet, the beta desee -
,Nt s / ' at the tryfece of the equiposet shutil '?:
'4LY '
be the sts of the airberse and plate-out
-sources.1The airberse beta' den should' * ' - e e seseu en Lt.e beta done ediculated for
-# I a point at the' containment coster. , (
.. ( ; ,- ' y
- (s) shielded compeeests seed be qualified enly to the geana radiation levels mi
$ . required, pshstded as analysis er test shows that t&s-;seesittwo pertiosa of the.compeeest' er equipeent are set 4
- esposed to bets rediattoa er that the : j
' ' of fects of betsdadiettaa beating and fanizaties have'sa deleterteus eff. cts j es componest prferusace, (9) Cables arrassed is cable trays to the i contatasest abou14 & l.issumed to be ! exposed to half thB usta radiaties deae
..esiculated for e, ist y the center of .
-j t
. . - :the costalaseet p ,es the gaceia ray dose
- g -
- calculated is accendance with Secties 1.'#4.
~
This reduction 13 ' beta dose is allowed because of the'localissrd shielding by its +
/' >
l other cables plus the cable tray itsest . :[ ,) , a
-(10) Points and coatings should be assumed to be esposed to both beta and gsans
k" $.
rays-is assessieg their resistance te l * ;, , , radiaties. Plate-eut act;vity should e $
'Y j i .
be asswned to resqs se ao equtpeest surface unless the effecte of the / ', resevel mechaeises, such as spray wesha - j ' eff or stese condecsate flow, ca4 be ,l justified and quantafied by analysts l f , f or esperiment. ,
'f/ I
/ ,
r}pfo ,, (11) Componesta of the energency cars kae,l- *
./ -
ing system ( J s tetament 3(e:TCC3) located
.'paspa. valvesi sealsevtside coa-
)I ' ;
and electracal equapsent) should be . a
. qualified to withstand the radiattee '
- etuivaleet to that petetrattagi t6e coe*.' ') i tatement. plus the espesure free char / f '
sumpfluidusingassumptionscoaststesk', . with the requirements atsted is / !
. ,), Appeedia I to.70 till Part 30, f 4 -r
;(12) Iquipe3e)t thatimay be esposed to rad 4a*
taea deeve below !$* rada soeuld not be eseandered to'Le esempt free d
. radisttes quaitsstles. 441,34 / I /
aselysis support'ed by test data 16 : provided te verify that these levels j will met degrade thy, eserability of the . q equapeest belev usepatp yslues. } f 19 l
;' '_ } 'l t,
\ g f 9
l ',l s, o, t , i
)
k g ) [- ,
**-====*-- -I . . . . . .
m.
. Attachment D ,
Appendix E . 9'
- Tscohonetet1)sr u t00 TWX 7tDJet>78tf YANKEE ATOMIC ELECTRIC COMPANY @R . 614 REV 3 gy, g,'
1671 Worcester Road, Framingham, Massachusetts 01701' g 'YANKE l - VYE #65/84
, W.O. f4440 May 23. 1984 DCC M -ECOTECH-84-12 'i Mr. L. P. Gradin .
.Ecotech. Inc.
5418 Tonnele Avenue . North Bergen, NJ 07047 ~ Purchase order Number 103135 Environmental Qualification Consulting Services Vermont Yankee Nuclear Power Station
Dear Mr. Gradin:
. ?
We are transmitting a radiation dos'e specification model for equipment I within the VY drywell. The model provides the equipment qualification dose to cable insulation as a function of insulation or jacket material depth. The model can be used to justify dose reduction due to self-shielding. Very truly yours. (f); a W P. R. Joh on Lead Electrical Engineer Vermont Yankee Project PRJ/kg Attachment ec: A. C. Kadak 5
, S. R. Miller _
i R. J. January R. L. Smith ECoTe ch, Inc. D. M. Thomson F. Trotto (DCC) MAY 251984
, RECEly50
- -Nin
- J
Attachment D l Appendix E Page 7 of 9 l DR7
%Ian: n.nw )
y y y g RAUIAfl0N 005f SI'rClriCATION WOltK5)(Cf.T C'I'# **lI"" -- (From Procedure YA-R$C-11. Rev. O. P.8) ' 69 Rev Date P. System Calculation Applies to Each of the Following Pieces of Equipment TD Description Location Bete Shield Qual. Dose E (,6.t. C M 40 (L L(J-S E 6.'<.tci r Ak I45'06/ p,wea f e .5 .s u r v il o rside MO / g, {gy cu,s t 0 RbM */ rau m,e2 y H
, f Ri M A't 'l _. c 0 Ari4eovos &ti c o n %rti et /St h d i \
$ {,g-g e s 'gT j G.L 6v'r4 Qo,v ODR 6.14
',1 f J. cy r REV 3 RE/.3
-----------------Design Basis Event (Other Than Wormal Operations)----------------
D.B. Accident Period of Operation Limiting D.B.A. t oc A Ano 360 CMS L OC A -
- 0 /15 2 ~C 4 ** 1 f -
m f p g, g P FA S 5 R. r4 0,',o r,- A+0 H v y , De ~c 7 Input Prapared By Date 995^o,1%%9.E1=!2%) Event, source,and
- a . b Type of Radiation Assumptions ,
genua
- References Ord ruits- /O n<< t r .
7X 104 ]XiU Y
} beta y Y ( --j 9'5 A PPG- n o g g g ,,f g, y ,g 4 ,,gg;q 't
$_. /,7 xio# / ,7 t iO I gsama !
$$ Y YC - l9 3 A P PG es 0 ?X 6.7 51 . S~X 10 W.5X IQ b
$ 8 beta Y Y C ~' I $ 3 A PP6 r1 C I)c P>, I l l 9X10 1.k XIO h a recirculating Q g systers v 6 '=
g sump water-a ne ae
,e cent.ainment cwx shine y
I other
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a.*"" IEEE 323-1974 (6.3.1.5) Margin-107. on Accident Dose 7 / gg7
" "E 0,5"fg Q, if Limiting Wormal Dose" (j Rate (Rad / hour) kO D
hO Total Dose (Rad to a 7b 7,04/o7
,. i N /0 Prepared E bh d ste f4M M ( Reviewed Date j
U l
7, p y. n.. a > ,. -* Attachment D' ~
' Appendix E Page 8 of 9 ,.
_ . _ DR8-(plant name) - -- -
\/ y y p p RADIAfl0N 00SE SPEClflCATION WORK 5ftECT cald section_ p,
.; ,e ~;
I (From Procedure YA-HEC-11. Rev. O. P.8) New Date P,
. Calculation Applies to Each of the Following Places of Equipment-
' System
__ . ID Description Location i p Beta Shield Oual. Dose
, etecrc.sut Ete.c.r.r Ett'.td" M ; .1, ewu e s n.1e s t**M ogy y p, *i r D6 /
fd O . 10.7RAC ! rw aT S A6A484 Pg.ime ra y V P a-
- A " Y
- H .
c o,n Mnc ( o rVC A g A/ vH 6 MT*
~ E L W 4 c'E ,
est +r QDR l6.14
. REV 3 :
-----------------Design Basi s Even t (O the r Than Normal Opera tions m _ D.B. Accident Period ' of Operation ,
)---------------- l '1 Limitine D.B. A.
j .l t ' i Input Prepared By- . Date
' Event, Source and.
. 86*C4
-~~---Dose SNest0 g yp*55(f= ---- /Z3 j Type of Radiation s b Assumptions References
~
ganuma / E +v rLZf . 76 mr t < . -, b '7XsOC < 7 gg o 4 ,_b. 1 y yc - 19 3 ,, pee n oix a. 5-
.g neutron 1.sxio 4 ).x xiu Y l'.
g gamma le iXs OT / o 7 X ILI y
\/ Yd - l 9 3 19 PP&h 051 6T 4. 5 x go' 4,Sxt o l -
o a bets 8 a
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y recirculating VYC-l93 A PP&s oix' R / 7 f.fX 10
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[* W 10 7 g .rst.m. 6
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e containment E*U shine C "' _ ---- x s' . other
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IEEE 323-1974 (4.3.1.5) Margin-10% on Accident Dose -
,g 7 f, ,, 7
, Roundup
- 5. l 90 l* O YJ l
15 Limiting Normal Doss a b Total Dose " Rate (Rad / hour) kb . kO (Rad to A k d410 7D l< 3 kl O 7' Prepared M h b ate #4/ f N Reviewed / Date $!i '[ f 0 1 1
.b..ei. %- -- 4'.
Attachment D Appendix E Page 9 of 9 DR9 A' QCR 6.14 l 1 - REV 3 :: i i I L.4
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!, l ATTACHMENT E Page 1 of 3 ! Lewis Cable Purpose The purpose of this review is to document the qualifiability of Lewis PE/PVC electrical cables used at Vermont Yankee. The subject cables are located outside primary containment and serve the loads as described in Appendix (a). } The cables require qualification to the DOR Guidelines. The basis of the ! review is to document the acceptability of a generic material qualification , _for the cable. Generic material qualification and Vermont Yankee's position i of its acceptability has been previously discussed in Attachment D for Rome Cable. Discussion The Lewis Cables installed at Vermont Yankee were purchased to the EBASCO Specification for Special Cables (see QDR Section G4). That specification required all cables be in accordance with IPCEA standard. A comparison of the data contained in Appendix (b) (Vermont Yankee Purchase Order Information) and the requirements of IPCEA Standard S-61-402 demonstrates that the PE insulation used in the Lewis Cable meets or exceeds the IPCEA requirements. Since no type testing of the subject Lewis Cable exists, environmental . qualification is documented through similarity with the PE/PVC cable tested by ' Wyle (Test Report No. 45917-40-1). The cable tested was Simplex PE/PVC Cable with 0.016 inches of PE insulation. The use of the Wyle test report of Simplex PE insulated cable is acceptable to j demonstrate the qualification of the Lewis PE insulated cable because: A. The Lewis Cable has 56% greater insulation thickness than the Simplex Cable. (25 mils for Lewis versus 16 mils for Simplex.) B. The demonstrated capabilities of the Simplex Cable exceeds the capabilities required of the Lewis Cable. Specifically: ! i
- 1. The Simplex Cable was successfully preaged to an equivalent life of I 40 years at a temperature of 6700. The requirement at Vermont l Yankee is 40 years at 6000.
l
- 2. The Simplex Cable was successfully subjected to a peak accident temperature of 3190F. The peak temperature was maintained for l one minute after which temperature was reduced, slowly over a period i of eight minutes, to a value of 210 degrees. As installed at s Vermont Yankee the Lewis Cable is subjected to a peak of only l 3000F and that peak lasts for less than ten seconds. !
i
- 3. The Simplex Cable was successfully exposed to a total radiation dose of 7.7 x 106 rads. The worst case exposure for the Lewis Cable at Vermont Yankee is 5 x 106 rads. )
i i
I ( i l ATTACHMENT E Page 2 of 3 ' (Continued) ) l Conclusion
'In accordance with D0R Guidelines, environment-qualification of the Lewis PE '
insulated cable installed at Vermont Yankee:is demonstrated through similarity with the Simplex PE insulated cable tested in Wyle Report No. 45917-40-1.- 1 ' Because the Simplex Cable was qualifled to environmental conditions which were' more severe than those the Lewis Cable is exposed to at Vermont Yankee and because the Lewis PE insulation thickness is approximately 56% greater than that of the Simplex Cable.. reasonable assurance is provided such that adequate ] confidence of the environmental qualification of the Lewis Cable exists, j The above review and supporting test reports will be added to QDR 6.27 for ! Lewis Cable. I s 1
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, Page 1 of 2
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J ,} Funct'. tonal Reviewi , . l v uTne Lewis Cable at Vermont Yankee:scrves the following Instrumentation only:; ,
~
.. L .
1 vFT 104109 A/B' RHR System Flow
+
y ~ FTi 10-111 A/B. RHR Torus Cooling and Containment Spray Flow
& TDPT- 10-91 A/B 1RHR Heat Exchanger Dif ferential Pressure
- The Flow transmitters (FT-10-109A/B and FT-10-111 A/B) were added to our EQ' Program as
.a result of our RG 1.97 evaluation. They were added as a long term operator aid. Since the i
q RHR System has several accident modes that could be shared by one loop (ie. both torus-Ecooling and LPCI modes'op'erating together in one RHR subsystem), the flow indicators provide flexibility.to enable better control over system line-up changes during the course of 0 'the accident. No automatic action occurs as a result of these instruments. Therefore, these flow g instruments are considered an operator aid only for 1:ng term accident management. 1
'l I
l
.j '
- The differential pressure transmitters (DPT-10-91 A/B) are associated with the automatic
~
~ control'of the RHR Heat Exchangers' differential pressure. In the early phase of an HELB, the
, - decay heat from the reactor will be transferred to the Torus. The operating procedures instruct the operators to initiate Torus Cooling upon Torus temperature increase. When the 3 controller is in the automatic mode, this instrument controls the position of the RHRSW outlet j valve and thereby controls the flow rate of cooling water through the Heat Exchanger. When I
~ the controller is operated in manual mode (which is the usual case) this instrument only provides indication of differential pressure with no control function. The ability to control valve position in manual mode is iridependant of the transmitters and associated Lewis cable.
1 _.mm___i..m_. . _ _ . _ . . . - ~ . - . _ _ _ _ _ _ _ - __ - ..__._U
At.tachment E Appendix A Page 2 of 2 Since the controller is normally operated in the manual mode, and since other instrumentation is relied upon to monitor the effectiveness of Torus Cooling (eg Torus Temperature instruments), the function of the differential pressure instrument can be considered an operator aid Iqr setting up Torus Cooling and long term automatic control as desired. This instrument is not considered essential in early phase of HELB since other instruments can be utilized to insure Torus Cooling is performing properly,and remote manual valve position could be readily performed as necessary regardless of differential pressure indications. t e m 9 **'
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_ - mv _aw M-I l
- - - - - - - - - ~ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ ___ _
~~ _ - - - - - Attachment E / i Appendix B f Page 1 of 7 I l M +
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W. , i t plant to witness testa y, -'* s The writer visited vender's Neugatuck. Connect d r. cu and examine cable being furnished an oubbet or e 4140' = 7 W~ . 3115' 3090'
, ,v 4955' . 4940' . 4992' . ds coatwo copper e ltem 48 43.3 '2 f t k5090' l d 1/C black, 1/C -
g [ , s 3900* - 5100') (9 reels) 2/C (16 Aws.d19 streaconductor, .025" polyethyle owr myter p-p; white twisted with plastic fillers, cafl8 047* Aws, blanksolid pyc ceated copper drate wtre, b 11 a .0025" uncoated copper shle!Jteg tape, r and undet
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" helically wound over nrylar and under ll. a .005* uncostu shielding tape, .000" black hC jacket owra d coated coppwr toiwacter, this has en f4 5"
'i f ites 810 2038 ft 4/C (f. palt) #16 Awg. 19 stran ssame construction as item #9 abo black MC Jechat overett. d eerper ceaducter.
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m._ ,The of fered cable was tested and esaatned te accordance w tspecificattoe WYYMF-IV-4' l ,
?"* sub}ect order requirements. IPCT.A. ASTN. and Deseo C ^L revistem one dated October 6.1969.
F w Cable was accepted and released for preparation for shipseet. "
- a. Our endineer accepted emeesa footage on all items.
drata wits was u.ed in On steme #14 and #19 e 416 Aug solid coated copper This was also eccepted. if lieu of 818 Ants. l chnk tent with The of f ered cable was subjected to electric al end physica L satisf actory results observed as followat , 1.1
- L. 19 h.72 l. ::.5 volt sue Ant ted 2.5 2.5 E 2.5
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' ATTACHMENT F ~ page 1.bf'l' ml , , l t , h l
M . Question:No. 18: x- 1 % yy , .\
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{ i MOV-10-15BShlice ., q
.m. 1For the splices.on.the motor leads of the' dual-voltage motor; MOV-10-15B, "
o e:P M iplease provide-evidence to' support their qualification; l . . . . s LAlthoughithis. valve motor'is in a relatively mild are'a,;our' concern extends.to l l
' ~
' valve. motors installed inside the drywell. l
.(
Response No. 18* 1 Je have verified,"by additional' physica1 ' inspection, that the spliceson the.' l
' motor leads of. this dual-voltage motor consist of ' a nylon dual-voltage'; motor 1 : connector (similar to those discussed in Question No.,19) . covered by additionally 1ayers of. electrician *s; tape which has:.no'effect.on' qualification.
From' discussions.with plant, personnel,'we have determined.'thdt7on occasion,. o, 'the electrician may. have added electrician's tape 'to a nylon splice to provide. t added assurance.that'a good insulated connection'was made;
- 3. 1
' Qualifications of nylon-' dual-voltage motor. connectors are discussed .in the response to Question No.' 19 and No. 14. . These responses also:> discuss'the
~
. qualifications of"other. motors including those located'within the'drywell. .i I
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1 i
ATTACRMENT G Page 1 of 2 The following discussion is being provided to document the justification of the original qualification of 3M Tape Splices as documented in QDR 16.1. The Nuclear Regulatory Commission's (NRC's) concern about the 3M Tape Splice QDR is documented below:
- 1. Page A2 - Discusses worst case 3.2 V/ mil.
Page All - Addresses two half-lapped layers Scotch 23. l Thickness of tape 30 mils (before stretching). l Max insulation is 4 x 30 x 3.2 = 362.4 volts ? l How is stretching accounted for ? l 2. Type test do not match configuration on Page All. l
- 3. Overall conclusion on Page DT5 assumes all EPR based splices to be l qualified. Explain the Non-3M splices for which this report applies.
The V0rmont Yankee initial response is detailed below, i l 1. 3.2 volts per mil is not the insulating property of the material, but the l most conservative application at Vermont Yankee - 600 volts /187.5 mils. The actual dielectric strength of the material is greater than 500 volts l per mil. Stretching is not a concern because the material is applied to a thickness of 3/16" (187.5 mils), not to a number of layers. The vendor recommends stretching to eliminate possible voids (QDR Page G2-12).
- 2. The material used in both the 3M and Okonite tapes is EPR (QDR Pages G2-10, 33-8, and attached product data sheet). The conservative testing of the Okonite configuration bounds the application and requirements at Vermont Yankee.
The subject QDR only addresses the EPR based splices as applied to 3. Vermont Yankee requirements. No other application or qualifications are , assumed. _ It is Vermont Yankee's contention that the basis of the 3M Tape Splice qualification is a combination of the electrical testing performed by the nunufacturer and similarity of the insulated splices to those tested by Okonite Company. As discussed in Attachment D, the demonstration of adequacy in environmental qualification is not completely absolute but rather relates to the " reasonable" concepts established in Title 10 of the Code of Federal Regulations and NRC staff guidance in such appropriate documeats as the DOR Guidelines. The Vermont Yankee files provide " reasonable adequate assurance" such that " adequate confidence of environmental qualification exists." i
3 Jtj
, t-
. ATTACHMENT C Page 2 of.2t 1
(Continued) As discussed in Attachment D generic material qualification has,been accepted
.for:certain o'utside containment applications' based on the following factors:
' 1 '. .The severity of the environments relative to commonly known material capability and to normal (nonaccident) environments.
2 .' The amount'of margin between generic test environments and the required environments for the item to be qualified.
- 3. What similarity data exists (e.g., aging, radiation-resistance, information en materials and processing.from manufacturers involved, etc).
- 4. 'What type test data does exist for the item to be. qualified. .
LThe.folicwing analysis which takes into account these four factors documents ~ our. contention of the original acceptability of the 3M Tape Splice file.
-1
. The splices used at Vermont Yankee .are similar to those used for years in the electrical. industry in conditi'ons ranging from subzero temperatures to flooded
. manholes.. The material is rated for 9000 continuous duty, short-term duty at.1300C, and relative humidities.up to 96%. The peak conditions experienced by these splices at Vermont Yankee are 2130F-(10000) and 100%' ,
relative humidity. The specific material (Scotch 23)'has been satisfactorily J tested i.o radiation levels of 1 x 10 R8 or five times the Vermont Yankee requirement of 2 x 107 RL The similarity of the Scotch 23 tape to the Okonite T-95 tape is based upon both being manufactured from.ethlylenepropylene' rubber to produce a high voltage, high temperature splicing material with excellent electrical
. properties. }
A' review of the electrical properties indicates that the 3M Tape ' has.a higher dielectric strength and greate- insulation' resistance than the tested Okonite tape. The LOCA. testing of the inferior Okonite tape splice far exceeded the Vermont' Yankee' requirements demonstrating significant margin for the Vermont Yankee 3M Tape Splice applications.
)
l Therefore, it is Vermont Yankee's contention that the files as they were on i I October 19, 1987 vere sufficient to demonstrate reasonable assurance of qualification of the 3M Tape Splices and that no violation existed. . I l
% {;
o
r-I l. 1 h ATTACHMENT H Page 1 of 2 I l-l - The Nuclear Regulatory Commission (NRC) questions concerning QDR 6.15, Cerro l EPR Cables were as follows (Reference Vermont Yankee Audit Question No. 3):
- 1. Qualification of this cable is based on Rockbestos Test Report QR No.
1804A, Revision 1, dated February 23, 1982. This report is considered invalid because of IE Information Notice.84-44.
- 2. The test report states that the tested specimen was subjected to 200M rad radiation. Who conducted the radiation test ? Where is the radiation cert 3ficate ?
Vermont Yankee.is aware of the concerns noted in IE Information Notice 84-44. These concerns question the acceptability of Rockbestos Cable qualification programs. The notice states that users of the subject cable should take steps to ensure that Rockbestos Cable installed in the plant is qualified. Rockbestos.is presently revising all of their qualification reports. Vermont Yankee'has closely monitored these efforts. Requalification programs for XLPE I and CO-AX Cables are complete. Testing is complete for SR Cable. As of this date retesting of EPR Cable is not scheduled. Each program has successfully re-affirmed that Rockbestos Cable is fully qualified. As stated in IE Notice 84-44, one of the deficiencies of the Rockbestos test program was control of and documentation of tests performed by "outside" test organizations. The documentation of radiation testing was one of the items not supported by test certification documents. When originally prepared, Vermont Yankee's environmental qualification package for Cerro EPR Cable was based on the results of FIRL test report F-03789 (March 1974). This was the package which was found to be acceptable by Franklin in their Equipment Environmental Qualification Review (see QDR 6.15, Tab G5,.and Page A1). Subsequent to that review a new test report by Rockbestos of their Firewall EP Cable (EPR insulation) became available (dated February 23, 1982). Vermont Yankee believed that this test superseded the FIRL report and so replaced the FIRL report with the Rockbestos. As discussed on Page A2 of the QDR, Yankee was made aware of the NRC audit of Rockbestos in 1984, and as instructed in IE 84-44 Yankee reviewed the audit findings and determined that reasonable confidence in the adequacy of the j actual test results existed. Further confidence existed due to the existence of the old FIRL report included in the original EPR Cable qualification l package still on file at Yankee Atomic Electric Company, and successful tests j of similar EPR insulated cable manufactured by Anaconda (QDR 6.25) and Okonite. i Note: The demonstrated capability of the EPR insulation as shown in the FIRL, the i Rockbestos, the Anaconda, and the Okonite reports exceeds the requirements for Vermont Yankee with significant margin. For example the radiation requirement for Vermont Yankee is 2 x 107 rads (QDR Section DR) just 10% of the demonstrated capability of 2 x 108 rads discussed in the test reports.
}
(; ATTACHMENT H Page 2 of 2 (Continued) l Yankee committed to remaining current with the: ultimate resolutions-to the audit findings; specifically to. replace the Rockbestos report with the new, l . revised Rockbestos reports currently being issued. As stated earlier the Rockbestos re-test efforts have successfully affirmed that their cable is fully qualified. Therefore, per the instructions of IE Information Notice 84-44 Yankee ensured EPR-Cable installed at Vermont Yankee was qualified. i i 1 t
'j l
i l j
l i Page 1 of 1-ATTACHHENT 1
' Additional-Information on Eg MOV Walkdowns
- 1. .As requested during the EQ Audit, we are submitting examples of the. types- ;
of MOV inspections and walkdowns performed at Vermont Yankee. ! During the.1970's, MOV's were inspected many times by plant maintenance < personnel and engineering personnel to respond to various issues raised on components supplied-by Limitorque. Inspections covered. types of torque switch, terminal block, etc. The results of these inspections were pro- 1 vided in responses to the various IE Bulletins and Notices. A typical + maintenance' record is included as Attachment I, Appendix A, to this response. It also documents the various inspections and walkdowns per-
-formed on a typical MOV. :
In 1980 and 1984, Vermont Yankee performed walkdowns of equipment included in the EQ Program. The 1980 walkdcwn was performed in preparation for our NRC subm4ttal. The 1984 walkdown wss performed to obtain final equipment data. An example of the. raw data taken during the 1984 walkdown is pro-vided in Attachment I, Appendix B. In 1986, while performing the changeout of internal wiring in Limitorque actuators, walkdown information was reverified. Attachment I, Appendix C, provides a sample of this walkdown information.
- 2. In addition, in response to your question nos. 15 and 16, we have requested Limitorque to reverify that the subject motors are qualified (see attached).
v. , i l l l \ \ l l L____---- --- )
Attachment .I
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..; ,,, ,X . x, . Appendix A.
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./- M ACHINE REPAlR RECORD t
- M ACMlN E SERIAL NO PROPERTY NO. -
_[OS' Gate'Valhesc*
- V14-5A,B DEPARTMENT. LOC ATION ggyggg HOU45DOWN
',, i
. _ . . - - --. - - . - - - , . - - - . . . - - - . - - . - - - - . -- COST
) DATE on arrsnthet WORK PERFORMEQ O N LABOR M ATERI AL TOTAL ACC U M UL ATI
- 10-16-7 1 Dutchmen installed on both valves : : : _ /g p :
N}/2lm M7?Muth M*/TEk. Hiu rts>LAWM W/i?+ B 2 ~7 T<, . l
' 9/1'2/72 MR72-2 216 Tightened covers oil V111-5A
- - l Sf_10/72 v'* Changed torque switch- 5A-'open- 13,6 close.112_ 1E-11.bpen close-13.6 -
Igip.g - V-5)L__%nsected worm and_ brass motor _ ge.ar- _ Bound _05 A S LLimitis _Ran.$,K_1_DA - 11/12/7:. V-5b Inspected worm and brass motor gear- Found OK- Set limits- Ran;0K DA :
- q. M1962 V-5by Changed _lo_r_que' switch with_reyJded typw of red inahrialk i. HFA -
E .' l/2/ 76 V14-5A . Complete inspection of the limitora le operator! - l Gilmar't(
*' .DAT :
8/29/7T - v14-5 B .. Complete limitorque operator'inspcction . , . 12/13/79MR79-1041 repaired pinched wires on SA . DAT/FAS: J 10/6/80MR80-1068 ^ Repaired broken limitorque mounting b ql.t__}H# l10s0076lhh,$h_yW/_DD
~M 3/J/06MR86-0396 V14-5B Replaced thermal reset pushbutton w/ new resetikit'. 03B0106 WAC/NF/
J/El80tR85-12C 2 "V-5B" Performed -OP 5220 on 10/31/85 - Iospect:ed internals ofiop-. ;. erator. Inspected spring pack assembly & nc ted: ithe plastic stop nt t , f , was tight.. (see MR for details) . Replc ced greasefin raain ihousing lof : ,
...s operator with EPO:6 in limit switch with MOBIL 28. Replaced 0 rings .
I '# ' guard rings 6 gaskets as required. NCTE: The close setting of the : torque sw is now set on 2 & not on tl e 14 e s round. Comp,leteds.l1.b . ,j chn. out of all jumpers in the sw cmr t.. MI l0A0267, 0266, 0207,l02D6, 'I
/
0127. 0206. 11A0152, 11A0137, MR01B02 58, MI; 11A0182 ,
- CCR/WAC/JB/MC/M
, 1/16/8(MR85-126 1 "V-5A" Performed OP 5220. Inspected sprinn pack a ssem., r epladed : i o rings, quad rings & gaskets, torque sw vijth new one, all aperator .
grease with NEBULA 0, all limit sw gear. box grease L 28. ; , Ch3 'd all limit sw compt. wires to S. I.S. Rockbesto with s. MIi10 MOB [G35,:
, 10A236* 10A263, 2B160, 2B170, 1B193, IB322, 10A1l27, MR02l301 70. iJC/JG/AAG/IE 3/.1Q/B6MR86-9163djusted packinn on V14-5B -
! CAP /CWKp 13/.19/lBf MR86-125 1 "R" Installed sp_rIDg_ Rack _gIcase rq _i.e_f__t;abingi pe digitorque' instr.
- Also,(installed adjustable spring ca tridge cap;.
- WJM/NEPSC(
n_f11LQ248. 6B0302, 6B0315, l
"(*
f/19]afMnR6 179Q "A" T n s t all e d sp. ring _pa.C kLiegq_e._Lelief t 3binfip_ef Lim'ityguejinstr.
'& Also, installed adjustable spring cartridge cap.: MI 6B0315, 6B0248, i
i
.[ '[ ' l 6B01Q2 WJM/NEPSC(
- u. M.w *** 2/2 3/86 MR83-1262 "5B"
, SAME AS BELOW
- : !I k ;,'-[**1/ 16 /86 MR85 1261, "5A" _ During 85-86 Recirc Outage changed gretse in operatpr' : 1'
-@, to Exxon Nebula EP-0 Grease PFC per HAT .
h/JO/ 3_7287-174]_5A_ Chanced wiLinn per LL&J #87-0053 and set l'imi ts to' CWJ Jy ; l
'a 9o "VISlrecord" ..'
VISIRECORD PREVENTIVE M AINTENANCE SYSTEM tess e .e gi
"* 4 N; @h FORM S 803A)
N. s $ i A n n n n n ~ - a @@
, . Attachment I L. - Appendix A
[ .Page.2 of 2 L I,
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SUMMARY
OF PREVENTIVE' MAINTENANCE DONE
- N ACHIN E PROPERTY NO.
l ~CS Gate Valves V14-5A,B ' DATE DME . MISC, LUBE ELEC. MECH. , ORDtntO DONG F R EQ. CODE FREQ. CODE F4tQ. CODE FREQ. CODE 9 /30/8C I $- 5A Tnanoetad 1imitorqua-oparator RD2 1 n/3/.ar 714 5E Inspected-41mitorque-operator JA9 4/29/83 V1 4-$A_ Performed op5220 UAg A/94/m v1 4i n porfnrmnel op 599n.01..n? .T FV /h (' / T .
,i 2/28/86 r14-5B One-time PM: Inspected SMB MTR, operator
! for_aolm_ shift Ic.ckhu_t TPh 8 D set scr_ev tinhtness per info. notice
! 86-3, at td_Ho. LL__11E.4 . Also replaced Rr0880 in . operator With
- ! Fmvo htchilt E' )-C'. MC/JJL V1 5-4R Performed OP 5220 - see MR85-1262 CCR/JAT/W
, IO/11/Ai
/l5/86 V14-5A Performed OP 5220 - see MR85-1261 LF /?G 3/25/8_' h14-5 B Ferf orned'overl$ad reset 'rnd;.ihapction" ^.T A 3/25/87 V14-5A Performed overload reset rod insgention JA I 9/10/87 , _ ,
VI i-f A Performed OP 9220 .T A i I ~ n
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.l/ 'i Attachment I Appendix c MEMORMBUM Page 1 of 4 YANKEE ATOMIC - FRAMINGHAM
', Date February 10, 1986 To s. R. Miller 11 _
~ ;' a Gr0Up # VYE #14/86 From P. R. Johnson W.0. # 4440 q Subject IE INFORMATION NQILCE 86-03: QOLENTIAL l.M.S. #
DEFICIENCIES IN ENVIRONMENTAL QUALIFICATION _ OF LIMITORQllE MOTOR YALY1LAPJJM10JLli1 RING BACKCROUND INFORMATION f [ IE Information Notice 86-03, dated, January 14 k986, alerts licensees of potential probicms regarding tha environmental qualification of wiring used in Limitorque MOVs. The notico rwisorts that, during several NRC inspections, ' licenseeswereunabletoidentif;ythemanufactu'rerofint@nalwiringusedin the HOVs. In addition, when the licensee contacted the manufacturer. '# Limitorque was unable to certify that the wire installed in the velve operator was environmentally qualified. Limitorque stated that it could provide some ' environmental qualification information for wiring it provided, however, it could not certify wiring added by the valve manufacturer or the field. DISCUSSION As part of our ongoing _ commitment for Vermont Yankoo's (VY's) Equipment Qualification (EQ) Program, VY Project Electrical Engineering (VYE) was asked to evaluate Infomation Notice 86-03. Because Limitorque actuators are used
) in nearly overy nuclear plant, this notice has significant effect on the EQ Program of every plant and, therefore, it has received industry-wide attention in the past two weeks.
i. We have learned through other projects at Yankee Atomic Eldtric Company (YAEC) and through other utilities that Limitorque has not %etually tested wiro as part of their test program and that in nearly every instance when a licensee has attempted to obtain certification from Limitorque on the wiro provided, the information obtained only resulted in finding additional discrepancies. Attempts by utilities to identify the jumper wire installed in the actuator by field walkdown resulted in finding a variety of wires installed, sotre of which could not be identified. This notico seriously questions the onvironnental qualification of HOVs and questions the operability of HOVs for plants which are en-line. The Nuclear Utility Group on Equipment Qualification (NUCEQ) quickly assembled a qualification package entitled " Qualification Data and Reports Associated with Limitorque Hotor Operated Valve Control Wiring." Yankee Nuclear Services Division (YNSD) reco1ved this package on January 30, 1986, and we have completed a preliminary review of it. The package attempts to qualify wire
" generically" and, by a failure modes and effects analyals, attempts to demonstrate that the problems cited in the notice will net create n problem.
It is our opinion that this document can only serve to support a justification for continued operation for a limited number of inaccessible valvos for plants currently on-line. We believe that this report should not be used as auditable documentation to support qualification and cannot be used as justification for inaction on this notico for any plant currently of f-line.
- m. _ _ - _ , .
e.* gj c...- g-f .g hiM;(' Attachment I ye U 1 ' " Appendix.C
.Page 2 of 4-f lt' 7 ,
3 9 lSC R'. M111er. February 10,;1986
~
l
' Page.2-d[ # We believe the most expeditious method of resolving the concerns of
- Information ' Notice 86-03;is to replace all internal wiring "on the MOVs.. listed
'in Attachment 1 with qualified Rockbestos SIS wire (QDR 6.4-2). .The EQ i; I maintenance = records, the MOV, field'walkdown sheets, and.SCEW sheets #should be updated to' document that thic wire is used.in-the MOV circuits'. QDR 6.4-2 N . , should.bereviewedto.determineifanymodification'ofthatQDRisrequired[. N' jjp,leesulting'iromthischange.j '
4
' g ;l:Inladditicn, as theri,Olrink ,,as %< 1 L is performed, we request that .VY personnel t' comp 1'oLh Attachment 2. LThis form will enhance the field walkdown information j
l in QDR 3.1, Limitorque NOV' actuators, by adding additional qualification data '
-l 1 onMOVinternalssuchsgforqueswitch< type. p< -
- 7, y,. '
6"c RECOMMENDATION ,,.' Q{. ; VYE recommends thatta'1% internal wiring on MOVs listed in Attachment 1 be' l replaced with qua.lifie@ houkbestos wire. In addition, as the work is. s performed, we request that the information in Attachment 2 be completed.. l
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'\ $. W. Johnson itie.Sd Electrical Engineer "Ye,rmont' Yankee Project
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)*J,/K[Thayer [ .;'
(. . ' ' (,4nsincering . Manager Vermont Yankee Project i
,' ,PRJ/gms
. Attachments cc: W.'D. Hinkle 3 i
.R. L. Smith
.g. M. J. Cofske 3 M. Saniuk Please return to P. R. Johnson with. action taken: .l
-i . J. Thayer RecommirNdation accepted: [
j j[ 9 ' 3; d. ;a R'ecomnidqdnMen derded: 4; Comments; _ _ , . _ w 1
*Y .
. $ _._ 11__
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- r. '
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@3 ATTACHHdNTJ '
ff j/ MOV Walk;). L informati6n
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, MOV No: __
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/ i x i Order No: _t ~ f' -
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Serihl Nc:. .* ' 1 Hotor Hfg: , 1/_
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Mots}Serial \ No: __
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, 3 Motor "iertaination Method: Termina1 Block dd splice (circle) s
, q 4 - < ,a j Splice Type: 3 Raychem or Tape (Circle) l
- f. )
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Terminal block Type: ,,i
, C f :{
Torque Switch Color: j _.
; { <' > }' i j
j 1 Limit Switch Color: i
^
Lubricant Uced: ,'
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') T-drains used: yes or tra (circle);' if yes, location: __
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Attachment II
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;l
'ATTACHMDf7 2
-si MO'/ Wa 1,kdown info:~natica MOV No: On Usi ( /N - 3,C3 Q Or'dce No 3IN73&b
' Serial.No: 2clY/Md
.Hotcr Hig: kfll }9 hg [
'Hotor' Serial No; b-9 9 b O 9 [ O Tfl - V k c1 i
' Motor: Termination Method: Terminal' Block oc h (circle)
. Splice Type: horTape(circle)
Te:nina)l' Block Type: /t///9 Torque Switch color: $/b /J rt) i Limit switch Color: [A O/ dtdt\] Nbh($ OrdOd Lu'tricant Used: [ b I-
- T-drains Used: Yesoch(Circle); if yes, location:
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,< Attachment I Appendix D resep%ne (6171873 81c0 Page 1 of 2 rwx 7to-a8o.Fers YANKEE ATOMIC ELECTRIC COMPANY.
y ;-- , 1671 Worcester Road, Framingham, Massachusetts 01701 November 2, 1987-WO 4440 1 VYE 110/87 J DCC VY-87-114 , Limitorque Corporation { j 5114 Woodall Road l P.O. Box 11318 ; Lynchburg VA .24506 Attn: Pat McQuillan, QA Manager
Subject:
Actuator Motor Lead Insulation
Dear Mr. McQuillan:
During a recent NRC audit at Verment Yankee Nuclear Power Station, j j several concerns were identified regarding Limitorque actuator motor lead insulation. The list of affected components and description of NRC concerns
.are contained in Attachment 1.
Limitorque has previously provided Vermont Yankee with certification of compliance for these two motors to the applicable Limitorque test reports. In light of the NRC concerns, we request that you review your records for the identified motors and verify the applicability of the existing test reports. If'you have any questions or require additional information, please contact me a telephone number (617) 872-8100 Extension 2296. Your cooperation in this matter is appreciated. Very truly yours. C. J. Nichols Vermont Yankee Project CJN/25.226 - bec: P.-R." Johnson M. P. Sanluk R. N. Mosche11e J. K. Thayer S. R. Miller R. L. Smith M:: J. Cofske
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.m-' '
Attachment I Appendix D1 N ATTACHMENT 1 .Page.2 of 2-6
@i I.- 1MOV's-Installed at Vermont Yankee b 11. VermontYankee,ValveTagNo..MOV-70-19ALimitorque'Operato'r !
J l' 1
-Order No.- 391355A
- Serial No. 215715'
. Reliance Motor Serial'No. Y276060A2 a
2.- Vermont Yankee Valve Tag No..MOV-70-19B Limitorque Operator Order No.- i 391355A Serial No. 215714 - Reliance Motor Serial'No. Y263461A3 4 The NRC. inspector identified the lead wire. insulation on these motors as J
-unique (i.e.. not.previously:seen by.the.' inspector). MOV-70-19A has' red.
nonbraided insulation ~and MOV-70-19B has' grey..nonbraided insulation.,'The inspector questioned whether or not these wire types.are covered by
- Limitorque testing.
-II. Motors in the Vermont Yankee Storeroom 1.- Motor Manufacturer Porter - Peerless Motor Serial No.. 'YM73197TN.
3 Limitorque Order No. 3K8763S Vermont YankeelPO No.' 22859. Item 30
- 2. Motor Manufacturer' Peerless Motor Serial No. TM68900 Limitorque Order.No. 3K3150A Vermont Yankee PO No. 21948 3.- -Motor' Manufacturer Porter - Peerless Motor Serial No. YM73198TN-Limitorque Order No. 3K8763R Vermont Yankee PO No. 22859, Item 29
- 4. Motor Manufacturer Peerless - Winsmith j Motor Serial No. NP87761 Limitorque Order No. 3P3964A Vermont Yankee PO No. 25578
- 5. Motor Manufacturer Peerless - Winsmith Motor Serial No. NP87764 Limitorque Order No. 3P3964B Vermont Yankee PO No. 22578, Item 2 During the NRC inspectors review of Vermont Yankee's response to )
IE Information Notice 87-08, he identified several motors which are not directly covered by the notice, but appear (visually) to have the same !
.Nomex/Kapton insulation. The inspector questioned if the lead wire insulation is of the-same or a different material and if it is covered by Limitorque j testing.
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