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Responds to 780921 Request for Addl Matl on Seismic Testing of Neutron Detectors & Balance of Plant (BOP) Class 1E Equipment Qualification
	ML19259A787
Person / Time
Site:	Sequoyah
Issue date:	01/03/1979
From:	Gilleland J; TENNESSEE VALLEY AUTHORITY
To:	Varga S; Office of Nuclear Reactor Regulation
References
	NUDOCS 7901100299
	Download: ML19259A787 (43)
	v • d • e

{{#Wiki_filter:~ TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374ol SDOC Chestnut Street Tower II January 3, 1979 Director of Nuclear Reactor Regulation Attention: Mr. S. A. Varga, Chief Light Water Reactors Branch No. 4 Division of Project Fbnagement U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Varga:

In the Matter of the Application of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 In response to a verbal request by Don Lasher of the NRC staff during the telephone conversation of September 21, 1978, enclosed is additional material on seismic testing of neutron detectors and Balance of Plant (BOP) Class lE equipment qualification. The B0P Class lE qualification data includes the 125-volt vital battery charger, motor control centers, and seismic qualification test of the static inverter. Also enclosed is a draft of TVA's revised response to Q6.56. Very truly yours, c h' Q J. E. Gilleland Assistant Manager of Power Enclosures (2) w

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ud u An Equal Opportunity Employer

      . s Seismic Testing of the Nuclear Instrumentation System Power Range Detector for the Sequoyah Plant S. J. Jarecki V. V. Miselis J. Parello 4
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                         ' Approved:   G. J. Bohm A. E. Blanchard '

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l.0 INTRODUCTION

A seismic test was performed on a Nuclear Instrumentation System (NIS) Power Range Detector (PRD) mounted in a simulated support assembly to demonstrate the electrical functions / operability of the PRD during and after seismic event. The seismic event simulated during testing exceeds the carthquake requirements at the PRD location specified for the Sequoyah Nuclear Power Plant. Five tests at four successively higher input levels were performed on the Power Range Detector Assemb.ly. The highest Icycl of input being 2.5 times to 20 times, depending on the frequency, than the Sequoyah required level for the NIS Power Range Detector Assembly. Testing was performed at Westinghouse Advanced Energy Systems Division (WAESD) in Large, Pennsylvania, using multi-frequency, tri-axial test inputs developed in accordance with WCAP-8624.(1) 4 e 6

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2.0 EQUIPMENT DESCRIPTION _ 2.1 EQUIPMENT TESTED The equipment tested consisted of a Nuclear instrumentation System (NIS) Power Range Detpctor mounted in a support assembly which conservatively simulated the detector holder. The Power Range Detector consists of an uncompensated ionization chamber with two individual neutron-sensitive sections with a common high voltage cicetrode, integral mineral insula-ted cables with tri-axial connectors and eleven ceramic standoff insula-tors. The WL-23686 detector S/N 771703 was built in accordance with the Westinghouse Industrial and Covernment Tube Division (WIGTD) Drawing E-2231, Revision 12. The detector is installed in a mechanical positioning device which allowa the detector to be placed in the proper position relative to the reactor vessel. The installation arrangement is shown on Figure 2-la &

b. The normal side entry holder / positioning assembly consists of a 7-1/2" OD x 1/4" thick tube which is supported vertically by a steel whec1 resembly. The removabic neutron detector (uncompensated ioniza-tion chamber) rests on the fixed axle of the whec1 assembly. The holder with the detector is positioned at the desired location relative to the reactor by push rods, 2" in diameter, that extend through the chield wall. The push rod assembly is fixed to the shield wall to prevent motion along the axis of the push rods. The attachrent of the push rods to the holder is made by a clevis. Between the male and female portion of the clevis, a + 1/16 cicarance exists in both horizontal directions; while a vertical slot in the male clevis provides a + 1" vertical cicar-ance. The vertical clearance is provided to accommodate construction tolerances. The entire holder assembly fits into a vertical recess in the concrete shield wall. The recess is 9" wide along the length of the holder and is increased to 15" at the holder wheel assembly. The clear-acce between the holder tube and concrete is + 3/4" and between the axle of the wheel assembly and wall, the cicarance is + 5/8". Wnen the holder is in the operation position, as shown on Figure 2-lb, the dis-tence of the concrete above the top of the holder tube is limited to a minimum of 9.0" to provide adequate bend radius for the wiring for the detectors.

Details are on the following Drawings. 541F677 Neutron Detector Positioning Device Assembly 583F092 Neutron Detector Positioning Device Details , 883D366 Neutron Detector Positioning Device Details 2.2 TF4T EQUIPM GT AND INSTRUMENTATIqN A scher.atic of the tri-axial test setup is shown in Figure 2-2 and pictures of the test setup are in Figures 2-4 through 2-10. The

tri-axial configuration is developed by having the table input motion at an angic of 35 degrecs from the horizontal and the equipment positioned so that the horizontal principal axis of the equipment is at a 45 degrec angle from the horizontal component of the input. This tri-axial con-figuration results in equal and simultaneous inputs to all three prin-cipal equipment axis. Two control accelerometers are oriented and mounted to the test table to measure the horizontal (V2 times front to back and side to side input) and vertical accelerations. During scismic test, the detector was energized from a high voltage power supply (500 V DC) and a 10 K IIz AC signal was imposed on the high voltage electrode. This signal, coupled via the interelectrode capaci-tance, was monitored on each of the signal electrode outputs as well as the leakage current (DC) as shown in Figure 2-3. The AC input signal was recorded along with the two AC output signals and the two DC output signals. The DC output signals were used to identify shorted conditions ((10-8) Amp. full scale) while the AC output signal would identify interelectrode capacitance changes indicative of cicetrode motion. Tabic 2.1 provides a list of the instruments used for these tests. Reference measurements, which consisted of DC resistance measurements for cach cable-electrode (high voltage Signal A and Signal B) and Icak-age current (high voltage to Signal A and Signal B) measurements, were performed before and af ter each test, All other electrical output sig-nals frcm the test assembly were cabled to a separate acoustically shicided data acquisition room adjacent to the scismic test area. These signals from the detec tor assembly consisted, of 9 accelerometers and 4 strain gages used to monitor the response of the equipment. A list of the instruments used for the tests is given in Table 2.1.- ,

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TABLE 2.1 TEST INSTRUMENTS - NAME MANUFACTURER /MODEL liigh Voltage Power Supply Keith1cy 240A Signal Generator llewlett-Packard 200CD Electrometers Keithicy 600B 0.1 uf 5 KV Capacitor Box Westinghouse 0.25 uf 2 v_V Capacitor Eox We stinghouse Megohm Meter General Radio 1864. Conditioners B&F Model 10-800 Amplifiers B&F Model 10-800

Recorders (2) lioneywell 1612 Recorder E&I 500 Oscillographs Bush Mark 200 Shock Spectrum Analyzer Spectral Dynamics Corporation

. 13192 and 13231 Magnetic Tape Recorder CEC CR 2800 '

     *Between tests 3 and 4, the recorder was changed ,due to a failure of the first recorder.

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3.0 DEVELOPMENT OF REQUIRED' TEST SIMULATION 3.1 DEVELOPMENT OF REQUIRED TEST SIMULATION - The test input for the NIS Power Range Detector consist of four input 1cvels. The fourth level is representative of a fragility test level (in excess of all present plant seismic input levels for the NIS Power
Range De tec tor Assembly) .
The response spectrum input was developed in accordance with WCAP-8624(1) methods for selecting frequency content, magnitude, and phasing. 3.2 TEST FIXTURE A test fixture was developed that conservatively simulates the potential nonlinearities and impact condition that could affect the Neutron Detec-tor functional operability. The test fixture is shown on Figure 3-1 as nell as, the nonlinearities which were simulated. As indicated on Figure 3-1, the lateral bending stiffness of the detec-tor holder push rods were simulated by one way acting springs. The springs had a spring constant of 1090 lb/in. The actual lateral spring constant for bending of the push rods is equal to 4845 lb/in. , The lower spring constant is conservative and simulates a poten-tially nore damaging condition of impacting between the holder and the coterete recess in the shield wall. . A second conservatism results because of the positioning of r.he push rod springs above the bottom of the wheels. The lower spring (push rod) for both the test simulation and the actual installation are 31 inches above the bottom of the wheels. However, in the te s t , a 5'-0" distance was . used between push rods, where as in the Sequoyah installation the dis-tance between push rods is 6'-9". The placement of the top spring l'-0" lower relative to the base sirulates a sof ter system for an overturning condition for the holder; and thus simulates a more severe condition of impacting of the top of the holder with the concrete shield wall. The - sof ter push rod springs, as well as the lower push rod position results in a more severe icpacting condition than exists for the actual instal-lation. , i Also, as indicated on Figure 3-1, a top plate was added to the fixture to simulate the c.cncrete/ steel above the holde; when the holder is in the operating position. The height of the plate above the top of the holder was 9". The 9" dimension is the minimum permissible distance to ' accommodate the minimum bend radius of the cables for the detectors. . k [
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4.0 OPERABILITY REQUIREMENTS Operability requirements for the power range neutron detector are that the detec tor be able to perform its function during and following a seismic event. For determination of functional operability following the simulated seismic event insulation resistance measurements, leakage current measurements and subsequent neutron sensitivity tests were uti-lized. Functional operability during the simulated seismic event cannot be directly tested' due to the principal of operation of the detector. Iloweve r , functional operability during the simulated seismic event can be inferred from continuity measurements and the absence of short or open circuits.
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5.0 TEST RESULTS 5.1 CENERAL Testing.was performed at Westinghouse Advanced Energy Systems Division (WAESD) in Large, Pennsylvania using multi-frequency tri-axial test inputs as described in Section 3.0. Seismic testing of the detector ; assembly consisted of the following five (5) tests:
1. One-Quarter Level

2. One-Half Level

3. Full Level Run 1

4. Full Level Run 2

5. One and one Half Level (Fracility Level) ,
Figure 5-1 compares the Sequoyah spectrum at r. ass point No. 1 of the reactor building elevation 692.00 for the ho izontal direction to the 4 test levels. Both the vertical and the horizantal spectra are for a higher elevation on the interior concrete of the containment building than the elevation of the detector. .The elevation of the top push rod of the detector holder is 676.63. Note that additional conservatism is introduced in the comparison because a lower Jamping value (2%) was used for the required response spectra. The te.H response spectra is plotted at 5% damping. There fore, it can be concladed that Test Level 1 envel-opes the Sequoyah requirement. Tn addition, when the response spectra for accelerometer A3 vhich is located at the top of the pipe used to simulate the concrete is compared to the response spectra of the control acceleroaetet, the response spactra at the top is appproximately twice that of the control accelerameter. This occurs beesuse of a rocking of the test table as a consequence of the high center of mass of the test fixture. Thus, the actual test was more severe relative to the Sequoyah requirement, than that indicatef. by the response spectrum comparison made on Figure 5-1 for the control accelerometer.
. . s 5.2 MECHANIC /sL AND ELECTP.ICAL 'IEST RESULTS The following sections discuss the results obtained for the five IcVels '
of testing noted in the previous section. 5.2.1 TEST 1 ONE-QUARTER LEVEL Level 1 3 The seismic event was performed and accepted. Elec trical: Circuit continuity maintained during the test. No short-ing out or electrode movements were observed during the seismic event. Pre-and post-test insulation resistance and Icakage current measurements were normal and accept-abic.
-1 Mechanical: dxternal visual examination following the test showed no damage. No vertical lift or horizontal movement of the holder wheel axle was observed.
_ _ a-'_.__ _ 2.. u- n ' um m -w " - = = - - - - - - - - - - 5.2.2 TEST 2 ONE-HALF LEVEL . Level 2 The seismic event was performed and accepted. Electrical: Circuit continuity maintained during the test. (Two instances of AC signal perturbation (base line shift; were noted on signal electrode A only). No shorting out n or perturbation was indicated by the recorded DC sign 1s and post-te st insulation resistance and leakage current measurements we e normal and acceptable. J Mechanical: External visual examinntion following the test showed no damage. The wheel axle lifted approximately 1/16 in. vertically and no horizontal movement noted. 5.2.3 TEST 3 FULL LEVEL RUN 1 Leve1 3 The seismic event was performed but not accented until af t.er test 4, due to a malfunction found in the control channel amplifier lead to the shock spectrum analyzer. Electrical: Circuit continuity maintained during the test. (Twelve (12) instances of AC signal perturbation (baseline shif t) occurred on signal cicetrode A only.) No shorting out and no AC signal perturbations for signal electrode B or - DC signal changes were observed on either signal elec-trode. Post test insulation resistance and Icakage cur-rent measurements were normal and acceptable. ., Mechanical: The power range detector was removed from the test fix-ture for a visual inspection. The ceramic bushings showed evidence of impacting, but no structural damage to the detector was observed. Approximately 1/16 in, verti- ' cal lift and 3/8 in. horizontal movement of the axle was ~ noted. 5.2.4 TEST 4 FULL LEVEL RUN 2 Level 3 g The seimsic event was per formed and accepted. E1cetrient: Similar to test 3, circuit centinuity maintained during the test with several instances of AC signal baseline i shif t on signcl electrode A occurred. No shorting out and no changes.in other signals 6eing recorded. Post - test insulation resistance and Icakage current measure-ments were normal and acceptabic. t s ~
Mechanical: External visually examination following the test showed no damage. Approximately 1/16 in. vertical and 1/2 in. horizontal movement of the axle was observed. Mal func-tion in strain gage S-4 occurred. The strain gage fa il-ure in no way affects the functioning of the detector. 5.2.5 TEST 5, ONE AND ONE HALF FULL LEVEL
~
Level 4 Seismic event was performed and accepted. Electrical: Same as test 4 except minor DC signal fluctuation (less , than 10-8) on A signal was observed. Circuit continu-ity maintained during the test, and there was no short- , ing. Post test insulation resistance und leakage current measurements were normal and acceptable. Mechanical: The detector was removed from the test fixture for a visual inspection. The ceramic bushings showc3 evidence of impacting, however, no structural damage was observed. At completion of the seismic testing, the detector was returned to the vendor, WlGTD, and the normal acceptance test for neutron sensitivity . was performed. The test showed a 4.6% change in the neutron sensitivity from the original test performed prior to seismic testing. This small > difference is within the expected error for the neutron sensitivity measurement. The manufacturer verified that the tested detector passed the normal acceptance test.
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6.0
SUMMARY
AND CONCLUSION The power range neutron detectors are of the integral mineral insulated cable design, model number WL23686. Shock and vibration tests have been performed, in the past, on this type of design by the Westinghouse Electronic Tube Division. The integral cable design was subjected to a vibration test with con-stant sinosoidal acceleration of Ig in the horizontal and vertical planes. A constant sweep of 2.5 minutes duration was performed from 6 to 20 Hz in the horizontal plane. Following this, another constant swe(p of 2.5 minutes duration was performed from 10 to 40 Hz in the vertical direction. In addition, the design was subjected to a sino-soidal acceleration of Ig amplitude for 20 seconds, in the horizontal plane, at frequencies of 6.5 and 7.4 Hz. The performance of the datec-tor was evaluated by checking the resistance, capacitance, and neutron sensitivity before and af ter the test. Also, a shock test was performed for this design. The shock input pro-vided a 0.15 second duration pulse which prod' iced an acceleration with a 0.8g radial component and a 0.14g longitudinal component. The perfor-mance of the detector was evaluated as before and no detectabic damage was observed. As discussed in Sections 1 through 5, for the Sequoyah plant, additional multi-frequency and multi-axis tests have been performed on a single NIS power range detector (model WL23686) mounted in a support assembly which ' simulated a lower bound or worst case detector holder. The multi-frequency inputs were developed in accordance with the guidelines set forth in Reference 1 and the National Standard IEEE-344-1975. Figure 5-1 presents a comparison between the multi-frequency and multi-axia test spectrum and the required spectra of the containment interior structure. As can be seen ir the figure, the test spec trum cavelopes the required spectrum. During test, the detector was energized from a high voltage power sup-ply, cud an a-c signal was imposed on the high voltage electrode. This . a-c signal as well as d-c . leakage currents were monitored on each of the tuo signal elec trodes to identify shorted conditions or intereitetrode capacitance changes indicative of electrode motion and circuit continu-
, ity during the test. The test results during the test showed that cir-cuit continuity wcs maintained, and there were no conditions which would a ffec t the functisnal performance of the detector during the seismic event. Post test insulation resistcnce and leakage current meccurements were acceptable and verified operability of the detectors after the simulated seismic event. The small signal perturbation nc ed (less than 10-8 amperes) would not cause any loss of protection c .pability of the NIS System during plant operation in the presence of a normal detector signal (greater thau 10-4 amperes). These small pet turbations vere most lihely generated by c1cetrede displacement produced by <he detector assembly impacting with the holder assembly.
At the completion of the seismic tests, there was no observabic mechan-ical damage and subsequent detector acceptance tests performed by the detec tor ma tufacturer did not disclose any abnormal permanent change in the electrical or neutron sensitivity characteristics. Thus, it is concluded that the NIS Power Range Detector will operate as required during and af ter a seismic event and thus, this equipment is qualified for use in the Sequoyah Plant. REFERENCES
1. Jarecki, S. J., " General Method of Developing Multi-Frequency Bi-Axial Test Inputs for Bi-Stables," WCAP-8624, September 1975.
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.. O Sequo8i af IV R Q. c.c3739 a s a u M W z a y ( s ,g e ,s TENilESSEE VALT2Y AUT1:0RITY APPD?!)IX C GUA11A"TERD FFYFCD_'JICE D/iTA Item Ia(a1 torr. ate)
(To be Made a Part of the Contract)
'the bidder hereby guarantees that the performance and characteristics of the equipment bid upon vill be as stated in the following tabulation. In the case of conflicts bet' een data furnished below and any .other data furnished uith the bid, that furnished below chall govern. Include a separate tabulation for alternate propocal where applicable.
TVA considers this information so material to its decision on whether or not a bid meets the specifications that the omission of any one or more of them could make impossible such decision and cause the bid to be nonresponsive. If the omission of items of information renders a bid nonresponsive, such bid will be rejected. Input requirement: 36 kva input at 19.6 kw output (rated)
, 23.4 hu input at 19.6_ kw output (rated) - 80 percent efficiency
_Itegulation: _i i percent from no lead to full load with a simultaneous 7.5 percent line
- voltage variation and 2 percent frequency variation -
100 mv vo,.ts ras, or .5 percent Output voltage ripple: without battery connected , Current limit: 125 max. percent rated at nominal input
~(3 80 volts, 60 Hz) 1 J 0 rax. percent rated value at nominal +10 percent input 125 max. percent rated value at nominal - -10 percent input Ambicnt temperature: 45 C maximum - {
Power Cr,nversion Droducts Inc.
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Ylf f fh)t/ h?lM.S l ., ,i B. APPLICABLE SPECIFICATI0HS A O DRAWINGS, continued
2. 'vTncre discrepancies between this specification and the bidder's
! li proposal exist, requirements under TVA specifications shall govern except where the bidder lists exceptions to TVA sp.ccifications , under appendix 3. .
3 TVA Drawings
a. The work in shoun on t'he accompanying drawings which apply under this specification to the equipment listed in the Schedule of Prices; any other equipment shown on these drawings is hereby excluded. The electrical equipment drevings shall govern in case of any discrepancy.
The specification drauings bear the general title, Sequoyah nuclear
. Plant, and individual designations as follows: . ~
.. DradlnENo. Title ..
45B361-1R0 - Electrical Equipment, Unit 1, h80-Volt Turbine Building . Vent Board JA, Circuit Schedule
. 45B361-2RO - Electrical Equipment, Unit 1, 480-Volt Turbine Building '
Vent Board 1B, Circuit Schedule
~ -
1FJ361-3R0 - Electrical Equipment, Unit 2,' h80-Volt Turbine Building Vent Board 2A, Circuit Schedule e h5B361-hRO - Electrical Equipment, Unit 2, Ir80-Volt Turbine Building
' Vent Board 2B, Circuit Schedule h5B361-5ARO E-.:c orical Equipment, Unit 1, 480-Volt Control and and -5 BRO , Auxiliary Vent Boards IAl, lA2, Circuit Schedule 45B361-6 ARC , Electrical Equipment, Unit 1, 480-Volt Control and and -6 BRO Auxiliary Vent Boards 131, 132, Circuit Schedule h5B361-7ARO ~
Electrical Equipment, Unit 2, 480-Volt Control and arid ,7 BRO Auxiliary Vent Boards 2Al, 2A2, Circuit Schedule . 45B361-8ARO Electrical Equipment, Unit 2, 480-Volt Control and _and -8 BRO - Auxiliary 7ent Bcc.rds 2B1, 232, Circuit Schcdule
, 45B361-9R0 - Electrical Equipment, Unit 1, 460-Volt Reactor Vent Board 1A, Circuit Schedule 45B361-lORO - Electrical Equipment , Unit 1, 480-Volt Reactor Vent Board 1B, Circuit Schedule 45B361-11R0 - Electrical Equipment, Unit 2, 480-Volt Reactor Vent ~
Board 2A, Circuit Schedule 8
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TENNESSEE VALLEY KJTKORITY APENDIX B
,' DESIG'i DATA .
The following design data shall be [ubmitted with each copy of. the bid:
1. Exceptions to TVA specifications. (See section B.2.)

2. Illustrations showing type of .otor control centers proposed.
3 Dimensional drawings or cuts for each moter control center, includit.g (a) lengtli, (b) height, (c) depth,- (d) reccmmended and minimum frcnt aisle space, (e) recommended and minimum rear aisle space, (f) available . space for power cable and conduit termination, (c) net inside dicensiens of control center horizontal and vertical wiring, gutters, and (h) apprcxi-snte total net weight. 11 Manufacturer and type designation of each of the following:
a. Control centers .
Continental "Concentrol"
b. Load interrupter suitches (1) 30-ampere size G.E. Co, type "QMU"
- (2) 60-ampere size G.E. Co, type "QMU" _ .E. Co, type "QW" (3) 100-enpere size
c. -Load interrupter switch current-limiting fuses Chase-Shaunut Fo m 101

d. Motor starters and contactors A-H, I'nc. type'"RL"

c. Control transformers ,
G.E. Co, Machine Tool Ty a
f. Relays -
(1) Auxiliary G.E. Co, type HGA & HFA (2) Time delay Agastat - Series 2I.DC
; . . / .
b .
. g 1 . -e I
, 4.,.
s .
, APPENDIX B DESIGN DATA, Continued' -
I +. ^l. f Continued ,
g. Molded-case breakers ,
.G.E. Co, type "TEF" or Uss . ! (1) 100-ampere frame - .(2) 225-ampere frama GE "TFJ", frame or Westin;r:
GE "TJJ" frame or Uestin;r:. (3)' I00-ampere frame 4 GE."TJK" frame or Westin;h:. (h) ,%00-ampere frame .
' GE type SEM or Westingh::.;sz
h. Backup control switches

i. SCR controller
Loyola Industries type EF :-
(1) Number and type of silicon controlled 3_ 3
- rectifiers in power unit N
8.3, 41.5, & 83.0 (2) Rated kva ,...~' 10A, 50A, & 100A (3) Rated current
99%
(14) Efficiency
~ 30U, 150U, 6006 (5) Losses in watts .
8+3 MVA - ll%"U X lIN'M x i (6) Dimensions of each controller or 41.5 MVA - 13"U x 23"H x .: controller unit if not an integral I . 83.0 MVA - 13"U x 23"H x 1 U . . part.of the controller r ,
.(7) Type surge suppressor used See enclosed Loyola . (L-R-C network, sener diode -
Bulletins & Instruction's j - thyrector,etc.) One. instruction boek covering the proposed SCR to be furnished shall bc , submitted with each bid. t il \l . ,
.a -
(Ab ,
f, Arrow Hart - Continental Divicica , l - Bidder
4 SEQUOYAH NUCLEAR PLANT SEISMIC C' LIFICATION TEST OF STAh C INVDITER STATIC PG1Dl, INC.
Reference:
Ogden Technology Laboratories, Incorporated Report F-73165 September 1973 The static inverter was subjected to a number of slow sine sweep tests followed by a series of sine dwell tests for qualification to safe shutdown carthquake leve 3. The sine dwells were performed at frequencies corresponding to the observed natural frequencies of the equipment. The test input acceleration levels were such that the corresponding response spectral acceleration was far in excess of the applicable floor response spectra peaks. The test procedure in effect applied the most severe seismic conditicas (floor response spectra peaks) at the most critical frequencies (equipment resonance). This testing represents a considerable amount of conservacism over simply enveloping the required response spectra. The attached plot illustrates the degree of conservatism provided by the SSE tests. The updated applicable floor response spectra are also attached. eb O e O
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9 TENNESSEE VALLEY RUTHORITY 12/12/73 RESPONSE RCCELERATION SPECTRUM E* SNP AUXILIARY BLOG . MRSS POINT NO. 9 DAMPING RATIO 0 020 OPERATIONAL BASIS EARTHOURKE FLOOR ELEVATION =748.S0 8 E-H HORIZONTAL ACCELERATION _',- 1 o m . s O N WW C L2J _J WO 09 - 00 C LJJ (D ZO C3 c a-(f) . tu
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. _ - . .. . _ __ - - . ~ -- . - _ m. .. . - , , , , TENNESSEE VALLEY RUTHORITY' 12/17/73 RESPONSE ACCELERATION SPECTRUM SNP OUXILIRRY BLOG 11 ASS POINT NO. 9 OAMPING RATIO 0.020 OPERATIONRL BASIS EARTHOURKE FLOOR ELEVATION =748.50 '
N-S HORIZONTAL ACCELERATION - 9 esa eu
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_m TENNESSEE VALLEY AUTHORITY 12/17/73
- * * ' CESPONSE RCCELERATION SPECTRUM SNP AUXILIRRY BLOG E M99S POINT NO..
d- DRM?ING RGTIO 0 020
'0PtRATIONRL DRSIS EARTHOURKE FLOOR ELEVATION:
VERTICAL RCCELERATION 8 - d-O a-8 .f-1 i ? s- . 3 a- . x - 8 . 0'.90 10( 0'.40 O'.S0 0'.60 0'.70 0'.00 b'. 00 0'.10 0'.20 0'.30 3 PERIOD IN SECONDS E..S v'\ Fmote
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SO.),UO'IAH EU':LSidt PL1IiT VITAL AC Td.Till"ES CC /:.2.'.CT 75C3-75362 STATIC FC;l.R, II;CCCCP.1TCD - SST3."IC A'iD EN'/I20"'C?i".'E T3STS One of the 12-hVA vital im crters bein; furnished vr. der subject contract uns ccisnically tected in accordance with T/A Specificatica 1565, Static Pcuer Test Precedures 569-1271, Revicica D, and 569-1285, Revicion A, and in accordance with IE.E 3%-1971, Guida fcr Salcnic C.ualification of Clusa I Eleeirical Equipment, at Ogden Tec' e nolcr/ Laboratoriec in Fullerton, Califernin, en July 17,18, cnd 19,1973 The same inverter ves envirormentally tested in accordance with T/A Specification 1565 and - Static Powr Test Procedurec 569-1271, Revisica B, at Ogden laboratories on July 20 and the veck of July 23,17(3 f The invertar tected was an SPI M:xici 15, cerial ro.1396. . Seismic Test The unit was checked visually and electrically before moving the unit frca the factcry cnd upon errival at Ogden. A minor problem vac noted in that the output frequency van apprc: irately 62 Hz, but it van decided to valt and trouble shcot the oscillator circuit bercre the final electrical acceptance test. - Ogden's ceismic test cetup, althou;h adequato, left cemething to be desired.
' Initial difficultica were encoun:cred in counting the equipment on the shake table. In accordance with the approved test procedtre, the lower channel c111c vere to ba bolted to the chake table tning a mininun of 31x 1/2-inch,
_high-strength bolts for cach sill. This type of rounting could not be used due to the configuration of the shake table top. The problem */as resolved satisfactorily when it van decided to use a cla= ping nechanica at cach end of each channel clll (fcur cle :pa total) and to use a n:rcbeccope to =cnitor any clippage in the clumping techanisms. . The equipment used to reniter the test included visual iniicaters for the controlled input, a five-chunel recorder, cln 3-level r.cters, cnd five acceleroneters placed within the inverter cabinet. The ceccleromoters vere located on tro rajor cubpanel acuc blics, incide the frent decr, on a side Innel and on the top panal respectivc3f. In order to record the controlled input, it vac decided to run a preliminary resonance scarch with 0.2g inpuc to detcraine which of the five output accelerc=2ters could be used to conitor the input. The test coquence van no follous on the first exic' teated:
1. Perfor:n a preliminaq resonance cearch vith a 0.23 input cud cove on'c output t.ccelcrc=2ter to conitcr input.

2. Encrcine the inverter clectrically and load it vith c IOO-cupere reciutive lond.
} -
b
y . Electrical D!aign Fi.'en Au".uat 19, 1973 ' S1M.UDY/.11 !?.'CT"/J1 PIA!iT VT".G /.C II.'. .".TT3C CC:.Tt.'.C2 T.03-75352 STAT 10 FCEt, IU0Ca?C2A1CD 3 Perfom recocance cecxch and frequency cucep vith taxiraum inputs of O.2g und 0.42c recycetire4
- 4. Apply a taxieum crecified force of 0.623 for a u;inint:2 of 20 coconic at'cach resonant frcquency determined irca ctcp 3
5. Visual.1;y monitor the clcctrical operat, ion of the inverter during atops 3 and 4. .
.The test cequence of subsequent test vac as follous: ,- ~ ~
1. Repeat step 1 above. .
~
2. Perform recenance centch vith an input of 0.2 3. ,

3. Perform frequency svecp with an input of 0.42g in the horizontal axis and 0.285 in the vertical axis.

4. Enersize the irrterter electrically and lead it with a 100-ampere resictive lead.
3 Appy a tax 1=em specified input of 0.623 horizontal a:d 0.h23 vertical for n tr.ininum of 20 cceanla (20-cacend dwell) at the loveat resonant frequency determined D ca steps 2 und 3
6. Energize the chunt trip coils ot' each of the three chunt trip brea'se-a during the 20-seccnd dwell an.1 observe proper breaker operation.
T. Close chunt trip brechcro--dcenergite the inverter cicetrically by opening 480'l cc breaker en distributica pancl--repeat otep 5 for other reconant frequencica--observa breaker bounce.
8. Clone h607 ac brecher on distribution panel and cncrgize inverter--rake vicual inspectics--tect conplete.
The first axic to be tested van the horizontal front-to-back. The oscillogrcph traciras produced frca the rcronance r.carch-and-frcquency eveep indicated rcconant frec;.encica ut approxinately 12,17, and 23 H . During the 20-accocd dwell test ut 12 Hz, the rear door alcoct cate off the cabinct; but the unit functic cd naticiactorily clectrically. Inspectica reven]cd taat the dcor placed oa thc cabinet vas an carly productica ::cdel which h:d n In'.ch probica. The test vac called off until the ncnt day to allcu Static Power prconnel time to re-fiuce the rcar dccr with cnother ent-which htd rcdecie,ned in:chen. A:r;1c irna reinforcind uns nico cdded to the
' front door at thin tire in hopc0 of raiairi; the reconant frequency cnd /
leverists tha emplificatica facter of the front decr. Mter r.nhin3 the 63 structural changen, the ceinnic tectn were perforned ac described tbove.
,Elcetrien12y the inverter operation vac caticfactory, and it appeared to . pacu the acicuic teac.
* . SCPhl Q G .6(.r I'.:
j. The instruntentation inside containment which provides automatic protective

h
,' signals for a main steam line break is (1) pressurizer pressure; (2) pressurizer level; (3) and steam line flow. The instrumentation inside containment which allows the operator to monitor the steam line break accident is (1) narrow range steam generator lesel; (2) pressurizer level; (3) reactor coolant system wide-range pressure; and (4) react.or coolant system wide-range temperature. Qualification type testing for the protype pressure and differential pressure transc2itters to be used for the above instrumentation is described in Westinghouse letter US-CE-1384 (Eicheldinger to Stolz, March 23, 1977). Qualification type testing of the resistance temperature detector's for the reactor coolant system is described in section 3-4 of UCAP 9157, " Environmental Qualification of Safety Related Class lE Process d' Instrumentation." The qualification testing program for the valve motor operator and position switches is described in Westinghouse letter NS-CE-692. TVA-purchased valve operators are identical to the Westinghouse supplied Namco siTVA-purchased (limit operators described in NS-CE-692. 4-!!f L Ivu MS4 I A. switches M_';r " : 2 . ' l E L~. o f- c.l l h u...m.. a t ic c ' n x .ci m . The tests for TVA-purchased air return fans are described in a reprint by Joy Manufacturing Co=pany of a paper presen ed at the 10th Electrical Insulation Conference held September.20-23, 1971. The tests included accelerated heat aging and pressure-temperature transients in a saturated 1 steam, chemical mixture environment. -The t d i.:g ;n ugm . .. for cicc c ,1,3 .x n a m e , .- e i_. gapr 1 2. j m , , ,,,, g r ,, r 7 7-.. , 2 n.pertc. The rcpa ._,
-- r o - : der re"i - M - 11 L iJeg :rr,a w! th_ n .;t-:Hese-i-hed-try- *)
6
M g:
'n*. Ic 2 ire _ +: n ;c.,
y
.44&ca.La 1, 1979. Thc tc L.c pcagre*4ee-p..ctrctirn: $ -.i gesca s mi ny m 1-3;; ;, ;gg, .aa4-w ' 11 h id e* i r i mi f line The temperature inside containment for breaks in the main steam The temperature is calculated for the worst i
will not exceed 327 F. erature i case small break which is the controlling case for containment temp
;
response. Thia calculation was done for the generic plant whose parameters different from
! are conservative with respect to or are insignificant 1y /.11 safety-related electrical equipment that must those at Sequoyah.
3 cnd Af cueeed perform in this environment is identified in FSAR tabic 3.11-
]i Manufacturer model, and type numbers are ' dr. rCa" scetien ".2.1.2.3. Cjiv % below clcctcical . identified in all test reports. With the exception $cf ti ; ; f c' 'e ed, all the test i ng u, tr ..q,.h be ,3 I ,. e n i ,, , ,, e p o ., . , t - e t ,, .,
from a subjected the equipment and instruments to temperature ranging o o In most of these tests, these temperatures were brought 330 F to 370 F.
)') l d in the nbout by rapid temperature increase requirements Which resu te actual temperature profile overshooting the required maximum temperatur In other cases, unplanned cicvated temperatures resulted in conservat overtesting.
The actual testing of this equipment at or above 330 F JWhc rc netu21 L: nt t: . ,~c;turer see j qualifics it for service at 327 F. ;{7
.j_, ; 1 ,. 7 c egt ,
a 14 r, .
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+ ,Eu fuc 1 ' - 2 'i.;.
e -rnsev+ 8
-l grf Recent testing developments for productica run pressure final statement pressure transmitters rcquire further evaluation before a 'A conclusion can be made regarding qualification of ther.e instruments.
An evaluation will be submitted when these generic issues are resolved. ,
<)
4

. _ ,_X,GW - ScPM Q G. G 6 f3, j 'of the separation and independence of equipment necessary to mitigate -inW onw the effects of a main steam line break inside containment was done gyp . g ggg Q 76 h yi according to requirements of the pipe break evaluation inside containment. Sensors, cables, and other equipment, were included in the evaluation. See section 3.6 of the FSAR for details of the evaluation criteria. Where unacceptable interactions were identified, sensing lines, conduit, and other equipment were moved or protected to provide the required separation and reduadancy of mitigation equipment. See Figure 1.2-11 for the physical layout of the steam generators and main steam lines. Independence between steam generators, as required by the plant safety analyses, is provided by the system design, the physical layout, and by modifications made as a result of the pipe break evaluation inside containment. See Section 3.6 of the FSAR for details of the pipe break evaluation.
\
e a
' ~
. tn g g. h . -16 S Q M Q 6 % ~ - .w .. . - . -22'. XJ .1 - fo. v iul . m~u+
w n m .s.,; 4.for ati;n i; ;aL,,:L; ' ;,,-repe:re te per+c (i),(j),
*c =r M fr \ ~ - Ense:A A . ' i it 5..itchn -Thc; 3. itches were qualified to IEEE Standard 382-56 -
1972 and were subjected to thermal and mechanical aging, radiation exposure,'- LOCA, and MSLB environmental tests. The results of the test are in Acme Clevelarid Development Company qualification reports on Namco limit - switches, models EA-180 and EA-740.
. ~_[ns & B ,
ePc. ; ctretiqq . Testing of the penetrations was performed to ensure seal integrity and insulation quality after being subjected to " accident" . conditions for tempe ature and pressure. All penetrations were subjected to a temperature in excess of 3250F except the triax which was subjected to 323oF. This small difference was considered insignificant. The tests
' demonstrated penetration integrity for the MSLB occurrence. The results ~ .of the test are in thefollowing reports: .. ,
Low voltage power - PEN-RLK-3-16-01 *
~- ~ ~
Nedium voltage power - PEN-ACD-4-72-03 .
~ - Low voltage control and' instrumentation - PEN-RLK}-26-73 ~
Triax (neutron monitoring) - Westir.ghouse tr'iax incident report
^q Ec ekcMcx cobles a clestnbed in e large. '77v-.
n u m bev- h%sEjr.rce.wje p5 repd , b 4c,-j. p Jh j x2,x Lee.n ,5wmm wged . e J.aM4 w "cfcc to Tchic 22.71 in - T A/e. Q
-22. XJ . 2 "^ : p= s e gg g , . - The safety-related instrumentation is channelized and the separation and independence requirements.are found in FSAR section 7.1.2.2.
v. . 4
* ~ .sqN - , , , -1 -
Q TABLE-22cXG G .6 0. D -
~
SQNP , QUALIFICATION DATA ON CABLES INSIDE CONTAINMENT TVA Applicable Contract Env Qual Mark No.I IEEE Std No. iifg Aging Rad LOCA MSLB2 ' Remarks' WVA 383-74 WB 85259 Belden Yes 2,x 10 8 3000F * . Franklin Institute report F-C4039
~
323-74 - BLN 820991 Boston - Yes 2 x 108 300 0F
BIW report

Insulated Wire ,
383-74' 84211 ITT No 2 x 10 8 3460F Yes Franklin Institute, report F-C3961 Surprenant ' . 383-74 822000 Brand Rex Yes 2 x 108 3400F ' Yes Franklin Institute report F-C4113 383-74 - 824171 Rockbestos Yes. 2 x 108 3400F Yes Rockbestos report on qual of firewa
. 823265 111 Class lE Elec Cables 383-74 " 87232 Ann'conda ' Ye's' N x 108 .3400F Yes Franklin Institute report F-C4836-3 824447, ,
WVA-1 583-74 824171 Rockbestos. Yes 2 x 108 340 0F Yes . Rockbestos report on qual of firewa 823265 .
, , 111 Class 1E Elec Cables WVC 383-74 87232 Anaconda Yes 2 x 108 .3400F Yes - Franklin Institute report F-C4836-3 82447 e . - ~
SQu , 2
I INic; G 0 5 6 - 1 b o d d) -
TVA Applicable Contract . Env Qual - Mark No.I 'IEEE Std No. , ,, g Aging Rad LOCA MSLB2 . Remarks WPA, 383-74 . 824308 . Rockbestos Yes 2.x 10 8 3400F Yes . Rockbestos report on Qual of Firewa(1 WPS, 823428 - SR Class 1E elec cables WPC, & . WPG . 85861 C;nunental No 1 x 10 8 3400F Yes: Franklin Institute report F-C2935 83999 - Wire . S5112 ,
..;WPJ 85851 Continental No 1 x 108 3400F Yes -
Franklin Institute report F-C2935 WPH,1 . 83999 Wire . .
. 85112 ..
Note 1 - Description of cable is as follows: ' - Mark Nos. WVA, WVA-1, & WVC - Cable, multiple conductor, twisted, stranded, cross-linked polyethylene insulation, color coded, shielded, and 900C minimum black light stabilized chlorosulfonated polyethylene jacket. Mark Nos. WPA, WPB, WPC, WPG, . Cable, multiple conductor, stranded, 600V,1250C, silicon rubber insulation with glass braid over silicon. Overall cable has mylar binder tape and WPH-1, and WPJ asbestos braid finished with flame and heat resistant finish. 0 Note 2(*)-Anarrheniuscurvewasobtainedforthesecableswhichindicateusageinexcessof3weeksat325F. It is felt that due to the short duration o.f this temperature extreme for a MSLB occurrence that the cables would experience neglible degradation. ,. . . q .
. O g .}}

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