ML20041C777
| ML20041C777 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/26/1982 |
| From: | Vincent R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| TASK-03-10.A, TASK-3-10.A, TASK-RR NUDOCS 8203020554 | |
| Download: ML20041C777 (19) | |
Text
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e Consumers Power Company oeneral Offices: 1946 West Pernell Road, Jackson, MI 49201 + (517) 788-0550 February 26, 1982 SD A
Dennis M Crutchfield, Chief Operating Reactors Branch No 5 Nuclear Reactor Regulation RECDYND fl!AR 011982> ;9 US Nuclear Regulatory Commission Washington, DC 20555 7
R 5E'8 #
DOCKET 50-155 - LICENSE DPR W h" BIG ROCK POINT PLANT - SEP TOPIC III-10.A, is THERMAL OVERLOAD PROTECTION FOR MOTORS Y
M OF MOTOR-OPERATED VALVES By letters dated July 3, 1980 and August 3, 1981, the NRC issued for review a draft evaluation of Topic III-10.A and an SER respectively, for the Big Rock Point Plant. Attached are the Consumers Power Company comments on those documents.
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Robert A Vincent Staff Licensing Engineer Attachments - 17 pages CC Director, Region III, USNRC NRC Resident Inspector-Big Rock Point 0
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t oc0282-0032bl42 8203020554 820226 PDR ADOCK 05000155 P
i REVIEW 0F SEP TOPIC III-10.A Big Rock Point Plant I
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s ENCLOSURE REVIEW OF SEP TOPIC III-10.A A.
Summary of the NRC Evaluation The objective of the NRC ; valuation is to provide assurance that the appli-cation of thermal-overload protection devices to moters associated with safety-related motor-operated valves do not result in needless hindrance of the valves to perform their safety functions.
The NRC cited as current licensing criteria:
- 1) IEEE Standard 279-1971, and
In addition, the NRC stated that as a result of numerous operating plant events resulting from torque switch problems, the following supplemental criterion also applies:
"(3) In MOV designs that use a torque switch to limit the opening or closing of the valve, the automatic opening or closing signal should be used in conjunction with a corresponding limit switch."
According to the NRC evaluation, thermal-overload protection for motors of motor-operated valves at Big Rock Point does not meet current licensing criteria. Thermal-overload devices for AC MOVs are not bypassed, available information indicates that TOL trip setpoints are inadequate, and torque switches rather than limit switches are used to terminate some automatic valve functions.
B.
Detailed Review of the NRC Evaluation A review of the drawings referenced in the NRC evaluation (and also refer-enced in Attachment 1) shows 30 motor-operated valves (MOVs) which are supplied from either AC motor control centers (MCCs) or DC buses.
(These 30 MOVs along with two additional MOVs, MO 7054 and MO 7055, are itemized in Table 1 of this report. These two additional valves are included in the table since the table summarizes valve failures as described in Licensee Event Reports and in the Probabilistic Bisk Assessment.) Contrary to the NRC evaluation, however, is the fact that these MCCs are not specifically designated as ESF MCCs. Neither the Final Hazards Safety Report (FHSR), the Technical Specifi-cations (TS) nor the referenced drawings specifies them as such.
As can be seen in Table 1, all of the AC MOVs have thermal overload (TOL) protective devices which are not bypassed.
None of the DC valves, however, have TOL devices.
The NRC evaluation states that the ECCS MQVs have TOL trip setpoints which do not meet current criteria. The NBC statement is based on a letter sub-mitted by the Consumers Power Company in 1976 and referenced in the evaluation.
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Contrary to the statement in the referenced letter, are the results of an evaluation (based on test, refer to Item B in Attachment 1) completed by the Consumers Power Company in January of 1979 (see Attachment 2).
According to the evaluation, a realistic combination of elevated ambient temperature, setpoint drift, excessive motor current and inaccuracies in both motor data and overload heater characteristics was employed to de=enstrate the security of the safety-related valves against spurious tripping resulting from TOL devices. As a result, it is the opinion of the Consumers Power Company that the safety-related TOL setpoints are conservatively set accurding to current licensing criteria.
The NRC evaluation incorrectly states that two automatic valve functions terminate on limit switches and nine functions terminate on torque switches.
To the contrary, all of the MOVs listed in Table 1 have their stec travel terminated by torque switch in the closing direction and by limit switch in the opening direction. As an example, Drawing E-llh, Sh 1, Rev U shows that Valve MO 7051 (which automatically opens upon low reactor pressure and water level) starts its opening stroke on a closed LS/5 limit switch. This limit switch bypasses the torque switch during initial valve unseating to allow for a higher breakaway torque. Once an intermediate position is attained in the valve's opening stroke, the LS/5 limit switch opens and further valve travel is carried by the parallel torque switch. As can be seen in the drawing, a similar feature exists in the valve's closing circuits. The dissimilarity between the opening and closing circuits appears in the method of terminating valve travel.
In the open direction, valve travel is termin-ated by limit switch LS/4. The torque switch vill open to override the limit switch, however, in the case of valve obstruction or seizure. The closing circuit is terminated strictly by torque switch.
The limit / torque switch configuration and operation as described above applies to all of the valves identified in Table 1 except MO 706h, MO 7069, MO 7070, MO 7071 and MO 7072. As shown in Drawing E-103, Rev P, these valves employ an opening torque limit switch in the opening circuit and a closing torque limit switch in the closing circuit. Each one of these switches represents a valve actuator contact wired into the control circuits which can open to terminate valve travel either as a function of valve position (limit switch) or valve torque (torque switch); depending on certain actuator adjustments.
Using MO 706h as an example, it can be seen in the drawing that the valve (which automatically opens upon reactor building high pressure) starts its opening stroke on a closed OT/LS switch.
(Note, the in-series limit switch LS/0AS2 is set to perform concurrent with the OT/LS switch.) The OT/LS switch remains closed until the valve reaches a full open position at which time the switch opens as a function of valve position (OT/LS acts as a limit switch). The torque function can override the limit function and open OT/LS at any time throughout the valve stroke should valve obstruction or seizure occur. A mechanical interlock, however, prevents unwanted tripping of OT/LS as a function of torque during initial uns, eating movement. The valve's closing travel (note, this would not be '.he valve's safety response) is limited by the torque function. The torque function is mechanically prevented, however, during the initial closing stroke similar to that de-scribed above for the opening stroke.
In effect, the operation of Valves MO 706k, MO 7069, MO 7070, MO 7071 and MO 7072 is identical to the remainder of the valves listed in Table 1 as described in the previous paragraph.
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It should be noted that all but two of the safety-related automatic valve functions are in the open direction. Although carried by the torque switch throughout most of the opening stroke, the torque switches are bypassed during Initial unseating.
In addition, the safety function is terminated on a limit switch. The operation of these valves, therefore, conforms to current licensing criteria. Valves MO 7050 " Main Steam Isolation" and MO 7067 " Turbine Bypass Isolation" are the two exceptions since their safety function is to close. These automatic valve functions terminate on torque switches to ensure that they are indeed closed after responding to the reactor building high pressure situation.
Similar to the other valves, however, the torque switches are initially bypassed by the limit switch during the initial valve travel.
Although the automatic safety functions provided by Valves MO 7050 and MO 7067 terminate on torque switches, a failure of either valve's torque switch would not result in the inability to isolate main steam. Each of these valves serves a redundant purpose. A failure of MO 7050 to close on a signal from the reactor protection system, for example, could be tolerated since both the turbine stop valve (CV h200) and the turbine bypass isolation valve (MO 7067) close on a signal from the reactor protection system and, therefore, isolate main steam (see Attach:ent 3).
This exa:ple of system redundancy illustrates that in the Big Rock Point design, there are no instances where a single MOV is required to operate to fulfill a required safety function.
Another redundant component or system is always available to perform the required safety function.
A single failure of a torque switch could thus be tolerated.
In addition, the dependability of the torque switches to provide reliable operation and not to interfere with the safety function of the valve has been shown throughout the plant's history. As can be seen in Table 1, a survey of Licensee Event Reports and a review of MOV failures as documented in the recent Probabilistic Risk Assessment (FRA) shows only one out of thirty two MOV failures (or 3.1%) to be caused by improper torque switch use or operation.
In fact, the only failure attributable to a torque switch was caused by an improperly set switch and not one that had failed.
In three of the observed thirty two failures (or 9.h%) the torque switch acted as required to prevent valve damage during instances where obstruction impeded valve travel.
As a result of the aforementioned bypass of the torque switch during initial valve movement, design redundancy and record of dependability, it is the opinion of the Consumers Power Company that valves MO 7050, and MO 7067 (as well as the other safety-related automatic acting MOVs whose safety functions are carried by torque switches) meet the intent of the current licensing criteria.
C.
, Corrections to the NRC Evaluation C.1 Page 2, Paragraph " Discussion" is incorrect in that the motor control centers shown in the referenced drawings are not specifically designated as ESF centers. As described in Section B of this report, neither the FHSR, TS nor the referenced drawings specifies them as such.
k C.3 Page 2, Paragraph " Discussion" is incorrect in stating that "two automatic valve functions terminate on limit switches, but nine automatic valve functions terminate on torque functions." The operation of these valves is as described in Section B of this report.
D.
Conclusion The thermal overload protection for safety-related MOVs it the Big Rock Point Plant conforms to current licensing criteria. In addition, the use of torque and limit switches for safety-related MOVs at the plant also conforms to current licensing criteria.
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Enclosure Pagg 1 of 3 SEP TOPIC III-10.A TA!U1 1 VALVE FAI!UNE SURVEY TOL Failure Failure 5 h
@ or @
Scheme f TOL3 Contacts Identified In PRA%
Identified In LER/ER Torque Switch MOV #
Systeal DWG #
Vol VI.Tb1 XIII-17 PRA Failure LER/ER Survey? Failure Related Failures O 7070 CS E-103 Rev P B 163(AC)
Yes No Yes: 10/29/78 Defective Motor W!ndings No N/A No h/17/79 Spurious opening Cu9 h/19/T9 Spurious opening Cu9 MO TOT 1 CS E-103 Per P B 152(AC)
Yes No Yes: 9/30/71 Tagged for Repair
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No N/A Cu9 10/21/T1 Internal Valve Leakage No MO T0691% CS E-103 Rev P B 156(AC)
Yes No No N/A No N/A No G 7068 ES E-103 Rev P 5hlh(AC)
Yes No No N/A No N/A No MO 706h ES E-103 Rev P D01 (DC)
No N/A No N/A No N/A No O 7072 CS E-103 Rev P D02 (DC)
No N/A Yes: 10/ 1/T1 Tagged for Repair No N/A Cu9 M0/N001A RA E-111 Rev G 2h0h(AC)
Yes No No N/A No N/A No O /N001B RA E-111 Rev G 2h0T(AC)
Yes No No N/A No N/A No Q /N003A RA E-111 Rev G 2403(AC)
Yes No No N/A No N/A No M0/N003B RA E-111 Eev G 2bo6(AC)
Yes No No N/A No N/A No M0/N002A RA E-111 Rev G 2h05(AC)
Yes No No N/A No N/A No M0/NOO2B RA E-111 Rev G 2h08(AC)
Yes No No N/A No N/A No M0/N006A RA E-111 Rev G 2bl6(AC)
Yes No No N/A No N/A No O /NnO6B RA E-111 Rev 0 2h1T(AC)
Yes No No N/A No N/A No Mo 7056 SDC E-112, Sh 1 6koh(AC)
Yes No No N/A No N/A No Rev M Mo TOST SDC E-112. Sh 1 6h06(AC)
Yes No No N/A No N/A No Rev M MO 70!3 SDC E-112, Sh 1 6h05(AC)
Yes No No N/A No N/A No Rev M MO T059 SDC E-112. Sh 1 6kOT(AC)
Yes No No N/A No N/A No Rev M Yes: LER 78-37 Hardened Stem No MO 7050 MS E-112 Sh 1 6603(DC)
No N/A Yes: 3/ 6/T3 ValveStem/Fg11over Rev M Binding Packingll 9/ 6/78 Hardened Stem Packingll LER 80-3h Buildup of No Graphic Packing 6 MO 7053 RA E-112. Sh 2 6602(DC)
No N/A Yes: b/ 5/T3 Packing Gland Cocked 6 y,g. ER-T!-13T toose Locknut No Rev 0 11/11/73 Would Not Close -
Cause Unknown Cu9 11/lb/73 Would Not Close -
Cause Unknown 12 Cu9 6/ 5/T8 Valve Through-Leakagel2 D-78-31 Through Leskase no LER 80-01 Through Seat Lk No No10 N/A Yes Mo T063 RA E-112. Sh 2 6603(DC)
No N/A Yes: 1/25/T2 MrstorDamsge-Igproper Rev 0 TS Getpoint
SEP Tople III-10. A Tabla 1 Encloiure Eugt 2 of 2
'IDL Failure Failure 5
@ or @
Scheme i TOL3 Contacts Identified In FRAk Identified In LER/ER Torque Switch MOV f Systeel Dvg I (AC or DC)2 Relay?
Pyrassed?
Vol VI nl XIII-17 MIA Failure LER/ER Surveyt Failure Related Failures NO 7065 RA E-112 Sh 2 6606(DC)
No N/A No N/A No N/A No Rev 0 M0 7052 RA E-112. Sh 2 6h08(AC)
Yes No No N/A No N/A No Pev 0 MO 7062 RA E-112. Sh 2 6h09(AC)
Yes No Yes: 10/30/78 Rand Tightened Against Yes: E-BRP-Tightened Against No Rev 0 Backsest T9 k1 Backseat 13 12/10/79 He.nd Tightened Against No Backseat 13 Mo T066 CS E-lik, Sh 1 Sh18(AC)
Yes No No M/A No N/A No Rev U MO 7073 CS E-11b, Sh 1 Sh20(AC)
Yes No No N/A No N/A No Rev U MO 707%
Yes No No N/A No N/A No Mo 7051 EC E-11b, Sh 1 5601(DC)
No N/A Yes: 8/27/77 Bt.rrs Removed From Yes: ER loose locknut No g
Rev U contactor Arms 75-12 9/23/77 Icose Chips on Coggaetor No Coll MO 7061 EC E-11%, Sh 1 $602(DC)
No N/A Yes: h/ 9/73 Hand Tightened Against Yes: ER Icose Iocknut No Rev U Buckseat 75-1 Mo 7067 TRB E-119. Sh 1 9b12(DC)
No N/A Yes: 8/13/71 Packing Leak No N/A No Rev D 9/29/T2 Failed To Close Cu9 5/10/73 Failed To Close Cu9 11/ b/73 Failed To Close Cu9 5/10/77 Packing Leak No 5/31/77 Iseking Leak No 11/15/77 Packing Leak No 11/22/TT Packing Leak No 1/23/79 Controller Pwr Supply No 11/ 8/79 Falls to Open Cu9 Mo T05h CwS E-110. Rev J 2h13(AC)
Yes No Yes: 3/15/73 Closing Contact Vires No N/A No Interfering with Control Box Cover MO 7055 CWS E-110 Rev J 2 hlb (AC)
Yes No No N/A No N/A No TABLE N(7TES 1.
CS-Core Spray, ES-Enclosure Spray, RA-Reactor Auxiliaries, SDC-Shutdown 8.
Subject Failure also documented as A0-12-75 Cooling, MS-Main Steam, EC-Decrgency Cooling, TRibTurbine.
9 Cu - Cause of Failure Unknown.
2.
10.
Failure reported to NRC in letter RBSete11 (CFCo) to P A Wrris 3 TOL - Thermal Overload.
(NRC). 3/3/72.
b.
FRA - Probabilistic Risk Assessment.
11.
9/6/78 PRA failure and LER 78-37 doeunent the same failure.
5 LER - Licensee Event Report. ER - Event Report.
12.
6/5/78 PRA failure and ER T8-31 document the same failure.
Reports surveyed were from January 1, 197b to present.
- 13. 12/10/79 PRA failure and E-BRP-79-b1 document the same failure.
6.
Torque Switch Prevented Further Damage.
Ik. Valve is maintained electrically disabled in open position. Refer 7
Subject Failure Also Documented as A0-13-75, to Revision 2 of " Environmental Qualification of Electric Equigment".
ENCLOSURE ATTACHMETr 1 REFERENCES AND NOTES A.
Consumers Power Company Drawing
References:
l 1.
OTk0 G 30103, Rev P 2.
OTh0 G 30110, Sh 1, Re-J 3
0740 G 30111, Sh 1, Rev G k.
0740 G 30112, Sh 1, Rev M 5
07h0 G 30112, Sh 2, Rev 0 6.
07h0 G 3011h, Rev U T.
OTh0 G 30119, Sh 1, Rev D B.
Attachment #2 is a topical report which describes a thermal overload heater evaluation which is based on test. The evaluation and testing was performed by the Consumers Power Company Systems Protection Section and completed in January of 1979 Variation of the operating characteristic of the overload heaters was determined by actual test at the Consumers Power Company laboratories in Jackson, Michigan.
Raw data, generated during the test, is on file to support the conclusions as described in Attachment #2.
The test project engineer has indicated that laboratory test equipment, which is routinely calibrated and certified, was used to obtain the data although the specific test instrument identification was not recorded as part of the test documentation package.
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Pace 1 of 10 BIG ROCK POINT PLA*1T EVALUATION OF 480 VOLT MMOR OPERATED VALVE OVERLOAD HEATERS TOPICAL REPORT Introduction The Nuclear Regulatory Commission has inquired as to whether or not our Motor Operated Valve overload protection at Big Rock adheres to Regulatory Guide 1.106 and Branch Technical Position EICSB 27 The safety related valves l
considered are listed in table 2, they are all AC motor operated valves.
The l
DC motor operated valves are not equipped with overload heaters.
In su= mary l
the Regulatory Guide and BTp suggest one of two courses of action to be taken.
- 1) The overload heaters should be bypassed or 2) If used the heater trip set point should be at a value high encugh to prevent spuricus trips so that the valve may complete its safety related function,and periodic testing should be performed to verify the accuracy and reliability of the overload trip set point.
The criteria for evaluating the selection of the cycrload heaters was drawn from heater manufacturer's recc=mendation, IEEE Guide fer Motor Protection, M.O.V.
manufacturer's reco=mendations and operating experience.
Heater Temperature Test Testing of the heater was conducted to evaluate the effect of temperature variation on the perfor:ance of the overload heater. The heater chosen for the test was rated at 3 56 a=ps the sa=e si=e as those used for MoV's 7068 and 7069 All the heaters are of the same design ie. they are interchangeable, and all except the two indicated in table 2 are from the sace manufacturer.
Because of this similiarity of design only one heater size was tested.
The temperature was varied from 20 C to 70 C at 10 C intervals. The equipment wasallowedtostabilizeateachtemperatureforaminimumofidhours. To simulate the effects of recent operation of the valves during plant operation, a current equal to the maxi =um full lead current of a motor for which that heater would be selected was continuously passed through the heater. Trip currents of three and five times heater ratings were then applied and the operation of the heater was timed.
The higher the ambient te=perature of the overload, the faster the tripping time recorded.
This was especially noted for te=peratures above 50 C (the upper operating ambient te=perature is 43 3 C,110 F estimated plant).
The higher the multiple of current times heater rating, the more consistant the timing results were with manufacturer's data. See graph #1 and table #1.
Setting Criteria Since the original design criteria for the sizing of the overload heaters is not known, a set of criteria was formulated to help determine whether or not the heater trip set point allows the valve to perform its intended function.
The criteria used to determine the proper sizing is as follows:
- 1. Obtain the meter na=eplate data.
Full load current (IFL) and either the service factor (S.F. ) or duty must be included.
- 2. Utilize the heater manufacturer's literature to apply correction factors based upon the duty or S.F.
If this is not available, use the IEEE Guide for Motor Protection to base any correction factor.
Attachment. 2 2
Vuce 2 of 10
- 3. select hester size fre: table: provided by the manufacturer. A 1155 to 125$ mar.;in 1: inherent in manufacturer's table:.
To verify the security of the heaters against tripping, cargins were impo:cd and a check of performance was conducted en the heaters.
Cperating condition ccncidered were temperature variance, effect: of recent operation of the M.O.V.'s, cet point drift and inaccuracies in the nameplate data.
- 4. Verify that there is a 505 margin in operating time at rated current and maximum ambient temperature.
- 5. Verify that there is a 256 margin in operating time at 150% of rated current and maximum actient temperature.
- 6. Verify that the heater will trip in 10-15 ceconde at locked rotor current.
This is recontended by at least one M.O.V. tanufacturer and is realistic since the normal operating time of a M.O.V. is 20-30 seconds.
The 1ccked rotor current wa not specified in the nameplate of the:e p?rticular M.0 Y *s, no a value of 6 time: full lead current is u:ed.
- 7. Apply the cea ured cperating tines of the valves to the adju:ted operating characteristics of the overload heaters.
The adjusted curve reflect: the performance of the overload heaters as described in the Heater Tc:perature To:t section.
- 8. Apply a 10$ rargin to the full load carrant to allow for inaccuracies cf the data and set point drift.
This 10 in addition to the 115% to 1255 margin inherent in the table.
- 9. Verify the cumulative effects of 4 through 8 do not cause incorrect operation of the heater.
Discussion of Grarhs Graph No.1: Plots the data of table Uc.1 and al:o ec pare: the manufacturers average trip times at 3005 and 50CG heater ratins, the larcer, 35 48 sec, time range corre: ponds to 3CC3 the smaller, 14-19 sec, correspond: to SCUS.
Graph No. 2: In the manufacturers time current curve for the GE CR12hC112 relays.
It thould be noted that the extrapolation of thic curve, and the remainin,; curves, is shown as a straight line. this is an extremely con =ervative enticate cince the curve actually approaches the rating of the henter asymptotically, or in this case approaches 1 (time: the rated current) acymptotically.
Graph No. 3: In an adju:ted time current curve.The lower bound in plotted frc the trip times at h0 C free the test results.
The upper bound is the manufacturer:
upper bound of the trip ran.;c frc Graph No. 2.
Graph Mo. h : In like Graph No. 3 but at h3 3 C which in the estimated highes roce ambient temperature where the heater: nre installed.
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Pace 3 or 10 Grapn No. 5:
Compares the operating times of the F.OV's to the overicad heater cperating times at 43 3 C (shown in Graph :io. 4). The !?OV tultiples of heater d
rating are the fraction the ad,iusted full lead amps (frcm table I*o. 2) are of the heater ratings. For exa:ple 1.0 times the heater rating for M.OV 7070 equals L.66 amp, the adjusted full lead current for this valve is 2 38 amp.
The resultant =ultiple of heater rating is 2 38 i 4.66 2 0 5 2
Conclusion I
The overload heaters presently in use are satisfactory. A realistic ceabination of elevated ambient temperature, set point drifting, excessive cotor current and inaccuracies in both cotor data and ov.erload heater characteristics demonstrates the security of the heaters against spurious tripping.
Graph No. 5 displays the resultant of each of the previcusly described criterien and the cu.ulative effect of all the criteria. The mar;;in of tire during cur ucrst case evaluation is a minimu:: of 23 5 se ends. Tne results de enstrate the esnservative nature of the engineering design of the selection of overicad heaters. The l
existing overload heaters are correctly sized and no further action is considered necessarf.
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w Page 4 of 10 OVERLOAD HEATER OPERATING TIME FUNCTION OF TEMPERATURE Temperature Trip Time (in *c) 3 Times Rated 5 Times Rated Current Current 20*
44.8 sec 27 sec 30*
22.0 see 14.4 sec 26.0 see 13.0 sec 40*
23.0 see 11.0 sec 21.0 see 11.0 sec 50*
14.0 sec 10.0 sec 22.0 sec 8.0 sec 22.0 sec 8.5 sec 60*
12.0 sec 6.0 sec 9.0 sec 4.0 sec 7.0 sec 70*
Continuous trip at 3.0A The heaters were allowed to stabilize at cach temperature for a minimum of 1-1/2 hours.
3.32 Amperes was continuously passed through the heaters prior to time tests.
Multiple times at each temperature demonstrate variance of trip times.
nu0282-0032d142
Attachmen?, 2 Page 5 of 10.
A'.C.
MOTOR OPERATED VALVES-l t
Adjustek'OperatingTime Duty (c) Adjusted Heate[a)%1 (b)
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%I Open Close M.O.V. #
Bus I
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FL p
73 i
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7052 Emerg Condenser Inlet Valve 2P 1.9 2.20A 116 15 Min.
1.33 166 7062 Emerg Condenser Inlet Valve 2P 1.9 2.20A 116 15 Min 1.33 166 i
7066 Fire Wtr to Core Spray Sys V1v 2A 9
0.97A 108 15 Min
.63 15h 7068 Rx Bldg Emerg Spray Backup V1v 2B 1.h 3.56A 25h 15 Min 98 363 20.2 18.2 7069 Ex Core Spray Lines Cross-2B 3.h 3.56A 105 15 Min 2.38 150 i
Conn Valve I
7070 Rx Emerg Cool Spray Backup V1v 2B 3.h h.66A 137 15 Min 2.38 196 15.7 7071 RX Emerg Coo) Spray Backup V1v 2B 3.4 h.66A 137 15 Min 2.38 196 11.2
_11.0 7073 Fire Main to Condenser Primary 1A 1.h 1.h8A 106 15 Min 98
.151 25.8 24.3 i
1.h8A(f) 99 15 Min 1.05 1h1 23.6 23.3 70Th Fire Main to Condenser 1A 1.5 4
Secondary 4
t (a) General Electric C123e...
3 (b) Heater t I
- %I FL FL (c) Requirement of service (time) rating of motor 4
f (d) I K Correction Factor (per Duty) = Adjusted Ipg gg
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