ML20205R957
| ML20205R957 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/02/1986 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8606060052 | |
| Download: ML20205R957 (28) | |
Text
..
e TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374o1 SN 157B Lookout Place 4
June 2, 1986 Director of Nuclear Reactor Regulation Attention:
Mr. B. Youngblood, Project Director PWR Project Directorate No. A Division of Pressurized Water Reactors (PWR)
Licensing A U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Youngblood:
In the Matter of
)
Docket Nos. 50-321 Tennessee Valley Authority
)
50-328 As a result of questions regarding the auxiliary power system at our Sequoyah Nuclear Plant (SQN) from NRC in a January 8, 1986 telephone conversation and a subsequent visit by NRC at the SQN site on January 14-16, 1986, TVA provided information to NRC by my February 12, 1986 letter to you.
Subsequent to receiving your March 26, 1986 letter to S. A. White responding to the February 12, 1986 letter, a meeting was held with NRC representatives in Bethesda, on April 16, 1986 to discuss NRC concerns identified in the March 26, 1986 letter. Enclosed is additional information, as well as clarification to information previously provided to you, to demonstrate that additional verification testing of the auxiliary power system at SQN is not necessary.
Very truly yours, TENNESSEE V LEY AUTHORITY 6
. G idley, r_ector Nuclear Safe y %nd Licensing Enclosure cc:
U.S. Nuclear Regulatory Commission Region II Attn:
Dr. J. Nelson Grace Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 i
Mr. Carl Stahle Sequoyah Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 8606060052 B60602 PDR ADOCK 00000327 dgl P
PDR i
g An Equal Opportunity Employer
ENCLOSURE 1 RESPONSE TO B. J. YOUNCBLOOD'S LETTER DATED MARCH 26, 1986 RECARDING ADDITIONAL VERIFICATION TESTING OF THE AUXILIARY POWER SYSTEM AT SEQUOYAH NUCLEAR PLANT Subsequent to receipt of the March 26, 1986 letter, a meeting wac held with NRC representatives on April 16, 1986 to discuss NRC concerns identified in the March 26, 1986 letter. As a result of the meeting with NRC, we agreed to the following information requests from NRC:
1.
Provide additional data supporting the old and new analytical evidence of computer program adequacy (word description) 2.
Provide additional clarification of the original tests performed at SQN and any additional confirmatory analysis (explain exactly what we did) 3.
Perform a confirmatory analysis using 1980 measured load data and the presently utilized computer programs provides a copy of Revision 1 to the degraded voltage calculation, SQN-APS-001, entitled, "NRC Branch Technical Position PSB-1 Validation Test" that was generated to add the calculations performed utilizing the Radial and Volt computer programs. This calculation also provides the information identified above that was requested by NRC in the April 16, 1986 meeting. Attachment 2 provides a copy of the slides presented to NRC in the April 16, 1986 meeting. Additionally, the following is a response to each of the other concerns identified in the March 26, 1986 letter.
NRC CONCERN 1:
Addition of Two Start Buses and One Common Station Service Transformer The addition of two new start buses affects the incoming voltage from the offsite 161-kV switchyard to the onsite distribution system voltages which changes the voltage profile for the entire auxiliary power system. This addition also reduces the maximum loading of the common station service transformer.
Further, this modification provides an easy access to the third common station service transformer, which was installed as a backup, when such a need arises.
TVA REJPONSE Common Station Service Transformer (CSST) C was a spare that had been procured to the same specification as the original two transformers. Two additional start buses were not added, but instead the original two start buses were split into four buses thus reducing their impedence.
In addition, isolated phase buses are neglected in TVA's voltage calculations because of their insignificant impedances. Therefore, this modification added no new impedance to be considered in voltage calculations, but simply reduced the maximum loading for any single winding (i.e., the electrical model is unchanged).
See Figure 1 of attachment 2 for a comparison of the changes in the offsite connections due to this modification.
i 1
- /
' NRC CONCERN 2:
Change Out of 100 valve Motors The replacement of valve motors with motors of different electrical characteri:stics affects the plant transient load which resulted in changes in sequencirs of these loads.
Thisrequiresthenewsysteyloadingstobereanalyzed.
TVA RESPONSE Thetransientloadingandvoltageeh[e'ctofthereplacementofthevalve operators have been addressed in the SQN electrical restart calculations.
The SQN verification test was perforr.ed-ur. der' steady state conditions with the exception of starting a single motor on both the 6900 V and 480 V buses.
NRC CONCERN 3:
The Computer Processing System Changes The previous voltage study used an analytical model VNEW.
It was developed for the mainframe computer (Control Data Corporation's time sharing) while the computer programs (RADIAL / VOLT / VOLT 2), which were used for the new SQN auxiliary'pewer system voltage calculations, were run on the perso;.al c9mputer. Therefore, there appears to be a question regardng the comparability of the analytical techniques and assumptions used between the software (VNEW vs. RADIAL / VOLT / VOLT 2) and the hardware (mainframe computer vs. personal computer). The validity of the mathematical model used in performance of/the analysis can ouly be reestablished by perfomring a new verification test. Although it has been implied that those sof tware -
packages have been used to demonstrate' Position 4 of PDD-1 for some other TVA plants to date.the staff has not found where this has been reviewed and approved.
TVA RESPONSE 4
?.
Page 2 of attachment: 1 provides a description of thd computer calculation
~
methods.
=
M s
- W#<
hu.
95 W
s '
eY,
'4 s
a,
. NRC CONCERN 4:
Position 4 of PSB-1 versus Position 4 of Question 8.33 TVA contends that there are differences in Position 4 of PSB-1 and Question 8.33 (and imply that Position 4 of PSB-1 does not apply to SQN). We find that there are no differences. Other than the fact that PSB-1 is more specific about test procedures and the acceptance criteria, the intent of the two is the same.
TVA RESPONSE As, discussed in the April 16, 1986 meeting TVA agrees that the intent of Position 4 of Question 8.33 requirements is the same as Position 4 of PSB-1 requirements, even though the PSB-1 requirements are more specific. As discussed with NRC, we believe that we satisfied the licensing requirements by discussion of the scope of the testing with NRC on June 24, 1980 and subsequent agreement by NRC in that telephone discussion, by the validation testing performed in July 1980 and by submittal of the test results to NRC on October 3, 1980.
4 4
I N
li i
J s
I
-.. - -,.-~,.. -,-,.,,..--..-,,
ATTACI'HENT 1 NRC BRANCH TECHNICAL POSITION (BTP) PSB-1 HEANALYSIS SEQUOYAH NUCLEAR PLANT i
.0A Record TVA 10697 (CE445)
OE CALCULATIONS TITLE PLAN T/ UNIT NRC Branch Technical Position PSB-1 Validation Test Sequoyah Ul&2 PREPARING ORGANIZATION KEY NOUNS (Consult RIMS DESCRIPTORS LIST)
DNE-EEB Degraded Voltage BR ANCH/ PROJECT IDENTIFIERS Each time these calculations are 6ssued, preparers must ensure that the original (RO) RIMS sccession nurnber is filled in.
Rev (for RIMS
- use)
RIMS accession number SQN-ADS-001 R0 EEB 800806 913 APPLICABLE DESIGN DCCUMENT(S) 05i9 920 Rt FSAR R __
SAR SECTIONIS)
UNID SYSTEM (S) 8.0 N/A R_
Revision 0 R1 R2 R3 Statement of Problem ECN No. (*ndicats if Not Applicable)
To calculate voltages on certain Prepared unit I boards in accordance with E. Dimitriadis "T
the equipment loading and system Checked xicely
- k. J. 07 conditions that existed during 4
the two test periods at Sequoyah u.ed f
Nuclear Plant.
G. R. Reed Approved
~
T. S. Woodson
<M r),In 7
List alI pages added
,A f {d 3 L f
by this revision.
s
,,g DPP - D fl.
3II List all pages deleted lE of this revision.
's }s l 2. - 2 6 List all pages changed by this revision.
/-II Abstract Calculations were performed to simulate the loading and system conditions for test configurations 1 and 2 during testing at the plant (see Appendix A).
Manufacturer's information was used for all motors and transformers.
For cables, actual pulled lengths and sizes were used.
Transformer voltage taps were simulated using actual tap settings.
.e r_--
cc: RIMS, SL26 C-K
REVISION LOG Title :
NRC Branch Technical Position PSB-1 Validation Test Revision DESCRIPTION OF REVISION Dat u,,
Approved 1
This revision adds calculations performed with the Radial and Volt computer programs using measured data per NRC request.
The added calculations are contained in Appendix E.
The computer program listings are in Appendix F.
~
et I * '.
T TVA 10534 (EN DES 4 78) s 1
l TABLE OF CONTENTS 1.
Purpose, Results, and Conclusions of Test Report II. Appendix A Test Scope and Procedures III. Appendix B Test 1 Recordings and Calculations
~
IV.
Appendix C Test 2 Recordings and Calculations V.
Appendix D A.
Computed Load Data B.
VNEW Results C.
Radial Results D.
Stone & Webster P.esults VI.
Appendix E A.
1980 Configuration 1 and 2 Steady-State and Motor Start Computer Runs 1986 Configuration 1 and 2 Steady-State.and Motor Start Computer B.
Runs VII. Appendix F A.
VNEW Program Listing B.
Radial Program Listing C.
Vdit Program Listing S'
... ~25t~5 -
Y
SQN-A PS-00 l c::.;: :g,; 7 m n.;,q y,,9,g7, C h'. ~.
.. ;gg g '
SEQUOYAH NUCLEAR PLANT PSB-1 TEST REPORT
(
Purpose:
To verify the adequacy of 1) the equipment parameters and assumptions that have been used in Sequoyah Nuclear Plant design verification calculations, and 2) that the calculation methods being used (both hand calculations and computer calculations) will give acceptable answers.
Background
July 28, 1978, NRC submitted Ouestion 8.33 to the Sequovah FSAR.
Question 8.33 addressed new NRC requirements for an additional level of under-or-over voltage protection (degraded voltage protection).
Staff Position 4 of Question 8.33 entitled, " Optimization of Transformer Tap Settings," stated the following:
"The voltage levels at the safety related buses should be optimized for the full load and minimum load conditions that are expected throughout the anticipated range of voltage variations of the power source by appropriate adjustment of the voltage tap settings of the intervening transformers. We require that the adequacy of the design in this regard be verified by actual measurement, and by correlation of measured values with analytical results.
Provide a description of the method for making this verification and before initial reactor power operation provide the documentation required to establish that this verification has been accomplished."
I NRC letter from A. Schwencer to H. G. Parris dated May 5, 1980, required confirmatory tests of distribution systems and transformers supplying power to vital buses as required by Position 3 of Regulatory Guide 1.68 and Position 4 of the staff position on degraded grid voltage.
The NRC position in this letter was that confirmatory tests of all vital buses cust be conducted including all sources of power supplies to the buses.
On June 24, 1980, in a telecon between TVA and Faust Rosa, NRC/PSB, an agreement was reached which allowed the unit 1 test to only include one train.
Additionally, on April 2, 1981, agreement was reached in a telephone conversation between TVA and NRC (J. Knox) that additional testing of the ac auxiliary power system for unit 2 would not provide any additional benefit.
TVA's position not to conduct additional testing on unit 2 was formally submitted to NRC on April 2, 1981, by letter from L. M. Mills to A. Schwencer.
APPROACH - General On July 12 and July 16, 1980, TVA conducted tests (Special Maintenance
_j, Instructions, SMI-0-317-13) of the SQN ac auxi liary power system. The
,. - -S ' '
purpose of the tests was to collect data (current, voltage, kilowatts, and running motors) for the existing specific load configuration on a specified -
s part of the power system.
Calculations were made for the same loading configuration on the same portion of the power system. Voltages were 086132.02 -
a S Q N-A PS-00 )
g,:. g7 37g g;,77 f. ; ) pg, C:.K...i Q Q L:.1t S/t9/8 C measured from the offsite power system down through one in plant power distribution train (161-kV switchyard, 6.9-kV start bus, 6.9-kV unit board, 6.9-kV shutdown board, 480V shutdown board, and 480V motor control center) for an identified steady-state loading at each power distribution bus.
No voltages were measured on the 120V ac buses. Voltages were measured over the same path and at the motor terminals of an emergency raw cooling water (ERCW) pump motor (700 HP) while it was started and at the terminals of an auxiliary building general exhaust for motor (150 RP) while it was started. The voltages for these test cases were then calculated using computer calculation methodology and compared with the measured voltages.
METHODS - Description of Computer Calculation Methods The following in-house written computer programs were used to perform the analytical calculations performed in this study:
- 1) VNEW: Mainframe Fortran Program
- 2) RADIAL: Micro Basic Load Flow Program
- 3) VOLT: Micro Basic Program The computer programs used for these calculations are shown to give correct answers by the following procedures (see Tables 1 and 2).
VNEW has been checked by the following:
1)
Comparison to the public domain General Electric program - LFLOWS.
~2)
Comparison to PSB-1 related tests at SQNP, BFNP, and WBNP.
3)
Comparison to hand calculations.
4)
Comparison to independently written programs VOLT and RADIAL.
RADIAL has been checked by the following:
1)
Comparison to independently written program VNEW 2)
Comparison to hand calculations 3)
Comparison to PSB-1 related tests at SONP and WBNP VOLT has been checked by the following:
1)
Comparison to independently written program VNEV 2)
Comparison to hand calculations.
3)
Comparison to PSB-1 related tests at SQNP.
...a T
086132.02 I i
SQ N~ A PS-oo l crc ~D T3H F.'.H S-li- %
APPROACH - Onsite Testing Scope 5-M.b A.
Requirements The requirements for the tests were defined in the memorandum from M. N. Sprouse to J. R. Calhoun dated July 9,1980 (EEB 800709 905). A detailed Special Maintenance Instruction, SMI-0-317-13 (See Appendix A), was written to incorporate the requirements of Engineering. This document was reviewed and approved by the Plant Operating Review Committee (PORC) before implementation testing was accomplished at the plant on July 12, and 16,1980.
Those tests were conducted as follows:
B.
Test 1 conducted on July 12, 1980 - Test Configuration 1 This test, as described in the special maintenance instruction more fully, was with 6.9-kV unit boards 1B and ID connected to the start bus B through CSST B x-winding with y-winding unloaded.
Measurements for voltages, current, kilowatts, power factor, and recording of closed breakers were taken in accordance with the points of measurement table.
Board meters, where available, were utilized along with brush recorders and temporary meters. A complete list of equipment used is listed in the test instruction.
B.1.
Test Configuration 1:
The configuration identified below is required for that portion of the ac auxiliary power system undergoing test.
This test imposes no other configuration restrictions during the test.
Eouipment CSST B 1614 Closed X-Winding CSST B 1612 Open X-Winding CSST B 1514 X-Winding 6.9-kV Common Bd B 1216 Czosed Loaded to USST 2A 6.9-kV Unit Bd 2B 1214 1224 2B 1622 & 1714 CSST B 1624 6.9-kV Shutdown Bd IA-A 1718 Additional requirements:
1.
The 480V Shutdown board I Al-A must be connected to 6.9kV shutdown board 1 A-A by its normal feeder breaker through transformer IAl-A.
2.
Motor control centers (MCC's) must be connected to 480V shutdown board m.;E 1Al-A by their normal feeder breakers and all alternate feeder breakers ~~ ~2 to or from the above MCC's must be open.
3.
Board loads can be connected as required, but must remain connected for.
the duration of the test.
If a large number of loads change status during the test, the test may be aborted.
086132.02 l
SGN-A PS-oc t c :::n:m rgI_;:.:.y g-n-es C[ L'a1.M fQ_:... i_f//f/j] (,l 4
Unit 2 loads and 6.9-kV common board loads must be backfed through their respective USST's.
B.2 Measured data for configuration 1 is located in Appendix B.
C.
Test 2 conducted on July 16, 1980 - Test Configuration 2 This test, as described in the special maintenance instruction more fully, was with 6.9-kV unit boards IB and ID connected to start bus B through CSST-B x-winding.
6.9-kV unit boards IA and IC were connected to start bus A through CSST B y-winding.
Unit 2 boards and common boards were backfed through their respective USST's.
Measurements for voltages, currents, kilowatts, power factor, and recording of closed breakers were taken in accordance with the points of measurement table.
In addition, a 6.6-kV and 460V motor were started and the results recorded.
C.1 Test Configuration 2: This configuration has all the requirements of configuration 1, with the exception of additional requirements test listed below:
Equionent Breaker No.
Status Remarks CSST B 1612 Closed Y-Winding CSST A 1512 Open Y-Winding
^
6.9-kV Common Bd A 1126 Closed Loaded to USST IB 6.9-kV Unit Bd 2A 1212 2A 2C 1222 2B 1A 1522 CSST B 1C 1524 & 1722 6.9-hV Shutdown Bd IB-B 1726 C.2 Measured data for configuration 2 is located in Appendix C.
..D
,,.; W3$75 s
086132.02 l
SQta-APS-ool egge:,7g gLgy,z g_g g C ' ':* ' c ^: fk..' E [f/f/8 6 }
Point for Measurement
~~~
~
Sequoyah Nuclear Plant Unit 1 t
Varmeter Recorder or Load Profile Data Points VM AM WM PF Meter C. Bkrs. Load Amps Start Bus A XE XE XE X
X B
XE XE XE X
X 6.9-kV Unit Bd 1A XE XE XE X
XE 1B XE XE XE X
X X
XE IC XE XE XE X
XE 1D XE XE XE X
XE 6.9-kV Motor Term X
X X
X X
XE 480V SD Bd 1Al-A XE XE XE X
X X
" 1A2-A XE XE XE X
Reac Vnt Bd 1A-A X
X X
X X
X 480V Motor term X
X X
C&A VNT 3d 1Al-A X
DSL Aux Bd 1Al-A X
X X
ERCW MCC 1A-A XE XE XE: Existing Indicating Inst X:
Non-installed Indicating Inst
)
4 1
..o
--} $"~h I 086132.02 SQ N-A PS-oo l c:::.:F':T?::. T_H___tr.!E E-19-tG ti"c:::r.' A L:.TE S//ffg 6 D.
Accuracy of equipment.
A.
Brush recorders were of the 3 percent class.
B.
Ammeters, voltmeters, and power factor meters connected temporarily to the boards were of the 3 percent class.
C.
Board meters were of the 5 percent class.
BOARD ACCURACY METER SCALE INCREMENT ~
FULL SCALE I.
6.9 kV start BD/B VOLT 0-9000V 200V
+450V AMPS 0-4000A 100A
+200A WATTS 0-50 MW IMW
+2.5MW II.
6.9 kV UNIT BD IB VOLT 0-9000V 200V
+450V AMPS 0-4000A 50A
+100A WATTS 0-50 MW 0.5MW
+1.25MW
- III, 6.9 kV SHUTDOWN BD 1A-A VOLT 0-9000V 200V
+450V AMPS 0- 800A 20A
+ 40A WATTS 0- 10MW 0.2MW
+0.5MW
)
IV.
480V SHUTDOWN BD 1Al-A VOLT 0- 600V 10V
+ 30V AMPS 0-3000A 100A
+150A WATTS 0-2500KW 50KW
+125KW i
.T 6,-
...-~.h,'-.
s e
086132.02 _ _ _... _ _. -,
SYPNo A P5-o o l C '.
...[t 9H _ _
i_ S-l 9 9(a C.
Acceptance criteria.
$.W. - -5//QGl.
~ - - - -
For this test, the accuracy of the installed board voltmeters was limiting. Five percent of the board voltmeter reading is established as the maxium acceptable difference between measured voltage and calculated voltage.
D.
Results.
Typically, the readings from the board meters and auxiliary supplied meters yielded more consistent results. The brush recorders results are generally within 5 percent of the meters but did not yield
~
consistent results. For the second test, ac RMS calibration voltages were recorded at each station but drift of the brush tracings were noticed within minutes of calibration. Also, PT and CT inaccuracies existed. The board meters were calibrated on the board whereas the brush recorders were calibrated in the lab. The current input into the brush recordrs were also modified by insertion of a special made shunt.
Starting motor voltage dip values were not reliably established by test because of limitations in the instrument capabilities.
In both cases, the dip was only for approximately one cycle.
APPROACH - Calculations BACKGROUND
(
On April 16, 1986, a meeting was held with NRC staff in Bethesda, Maryland to discuss the adequacy of the PSB-1 testing that was performed at Sequoyah Nuclear Plant.
The NRC staff was concerned that 1) implementation of ECN 5311. Addition of CSST C and the splitting of the existing two 6.9kV start buses into four buses, and 2) utilization of new voltage computer programs would invalidate the results of the 1980 test.
The NRC staff requested that TVA perform additional calculations using measured board loading instead of closed breakers utilizing our new computer programs RADIAL and VOLT.
CALCULATION METHOD A:
Voltage program VNEW was used to calculate distribution voltages and board loading using closed breakers for Train IA model the loading for both configurations.
RADIAL and Stone & Webster's Program was used to check the results. See Appendix D.
p
,. :- tv: :
CALCULATION B:
Voltage programs RADIAL and VOLT were used to calculate distribution 3
voltages using the following measured board loading as the basis for the models*
I 086132.02 4 r
Configuration 1 Configuration 2 Total Recorded Total Recorded Board or Motor Ioad Computer Input load Computer Input W
W 4
W W
6.9kV Start Bd A NA NA NA NA 14.8 25.5 14.8 25.5 6.9kV Start Bd B 12.0 21 4.2 15.1 13.7 24 5.9 19.8 6.9kV Unit Bd IB 7.8 24 5.15 24 7.8 27 5.41 26.5 6.9kV Shutdown Bd IA-A 2.65 24 1.98 20.2 2.4 28 1.75 24.7
- 480V Shutdown Ed 1Al-A
.67 34
.374 29.7
.65 36
.446 28.7
+480V Shutdown Bd 1Al-A
.294 39
.204 48 480V Reactor Vent Bd 1A-A
.0019 35
.0019 35
.0008 49
.0008 49 ERCW Pu=p Q-A (Starting)
NA NA NA NA 1.19 75.5 AB Gen Sup Fan (Starting) NA NA NA NA
.170 75.5
- high side of reactor
+1ow side of reactor The board loading inputs for the computer calculations were made by subtracting the next lower level board measured load from each board measured load.
The total loading for start Bus A was calculated using volts, amps, and W for Unit Boards lA and IC. The recorded data for Start Bd A appeared to be in error.
O "h'
1 086132.02,
-r
..y
SG N-A P.5-o o l REQUIREMENTS r""n :r, Igi, t 7EJ-n g
[,-
p 4
This calculatien determined and documented the following:
1.
Steady state voltages on the APS 6.9kV buses and 480V buses configured in B.1.
The calculations are made with the system supplied through the CSST B then again through the CSST C.
The loading for these calculations is that which was mesured during PSB-1 test.
For these calculations the grid voltage is set at 163kV.
2.
Steady state voltage on the APS 6.9kV buses and 480V buses configured in C.1.
Also, terminal voltages for a 6.9kV motor and a 460V motor during starting. The calculations are made with the system supplied through the CCST B then again through the CSST C.
the loading for these calculations is that which was measured during PSB-1 test.
For these calculations the grid voltage is set at 164.5 kV.
The calculations using the CSST B represent the 1980 configuration of the APS and the calculations using the CSST C represent the 1986 configuration.
The 1986 configuratiog.3 as the current limiting reactor on the 480V h
ACCEPTANCE CRITERIA As stated in 1.C, the accuracy of the installed board meters was limiting.
Five percent of the board voltmeter readings is established as the maximum aceptable difference between measured voltage and calculted voltage.
RESULTS See su= mary Tables I and II for comparison of voltages.
All calculated voltages are within 3 percent of measured voltages for both calculation methods (closed breakers v.s. measured load) for each distribution bus examined.
Calculated voltages for the 1980 configuration and for the 1986 configuration were also within 3 percent of each other and the measured voltages.
$~
,,. ] t!.*
s 0
086132.02 ;
Station servic bus voltage supplied from CSST B observed reading s calculated results Test configuration I s
161-kV Crid at 163-kV f PI" 1 T ' TJ d *
S -l *] - ( f.
CSST B voltage tap ratio: 156975V to 6900V g. g.
{}
l -.- -.
Calculated Results Using Measured load Measured Data +
Usinn Closed Breakers Volraces Usine Rndial Load load VOLTACES Board W
R Voltage W*
R*
VNEW RADIAL Stone & Webster 1980 Config 1986 Config 5.9-kV Start Bus A NA NA 7200 NA NA 7152 7151 7148 7154 7156 5.9-kV Start Bus B 12.0 21 7000 13.95 22.92 7011 7008 7005 7051 7045 i.9-kV Unit Bd IB 7.8 24 7100 7.77 21.72 7011 7008 7005 7051 70'5 i.9-kV Shutdown Bd 1A-A 2.65 24 7000 2.89 26.1 7004 7002 6998 7044 7038 4
680V Shutdown Bd 1Al-A 0.67 495 0.817 30.78 495 495 495 501 500
,680V Reactor Vent Ed IA-A 0.0019 35 4M 0.072 26.59 483 483 NC 493 500+
M Table II
.O 2
l Itation service bus voltage supplied from CSST B observed readings versus k
- talculated results U'
s l '61-kV Crid at IM.5-kV est configurat.m 2 O
0
- SST B voltage tap ratio
- 156975V to 6900V Calculated Results Using Measured load Mnnenrod nren+
Usine Closed Breakers Volt,3ges Usinst Radial Load load V0"TAf79 Board W
K Voltage W*
VNEW RADIAL Stone & Webster 1980 Config 1986 Config
.9-kV Start Bus A 14.8 25.5 7000 15.4 24.1
.7044 NC 7045 7041
.9-kV Start Bus B 13.7 24 7000 15.4 21.2 7057 NC 7067 7062
.9-kV Unit Bd IB 7.8 27 7090 7057 NC 7067 7062
.9-kV Shutdown Bd 1A-A 2.4 28 7100 2.94 26.5 70'49 NC 7060
'7055 30V Shutdown Bd 1Al-A 0.65 36 500 0.94 30.4 493 NC 501 501/50l**
30V Rcactor Vent Bd I A-A 0.0008 tart of ERCW pp QA (motor terin V) 49 489 0.072 26.6 NC NC 494 50l++
6787 6763 NC 6705 6695 tart of AB Gen Sup Fan IA (motor term V) 466 449 NC 459 458/457**
- Radial Figures / Volt figures, aid in MW at an angle 8 where Cos R equals the power factor.
Die load and voltage results. indicate meter readings versus the brush mcorder readings.
> Reactor removed t*j o :.,.
\\
SGN-A PS-cci nrcim TM_f O F-1 S-ec.
E//I/dE" CONCLUSIONS b W-Comparison of the test results with the analytical results are well within the acceptance criteria.
The SQN validation tests accomplished two things:
(1) the equipment parameters and assumptions that were being used in the as-built design verification calculations were shown to be valid, and (2) the calculation methods being used (both hand calculations and computer calculations) were shown to give acceptable answers.
In summary, TVA believes no additional calculations or tests are required to verify its calculational methods for the following reasons:
s 1.
The original Sequoyah Verification Test and these calculations i
demonstrated TVA's ability to duplicate test results by its 1
calculational methods.
I 2.
Although modifications to the offsite power circuits for the Sequoyah auxiliary power systems have occurred since the original test and calculations were performed, these modifications do not affect either the validation test that was performed or the data that was taken.
3.
As previously stated in detail, the RADIAL, VOLT, and VNEW computer programs have been acceptably validated by proven computer and/or hand calculations.
}
4.
The test results at WBN did verify the accuracy of the WBN electrical j
calculations using VNEW and checked by RADIAL.
i 5.
The acceptability of TVA,'s computer programs to adequately perform l
voltage analyses have been approved by the NRC review of the WBN auxiliary system and documented in NUREG-0847, section 8.3.1.2.
i 1
1 I
J
?
i
... $Wh 086132.02 4 a
,_..,,-q.
.__.-.w,,_
,.,c.~y.___
-.p y
,,,,y,,
..-...y~,9.+77m_,,py,-w,p.m-*,
.-_3
ATTACHMENT 2 SLIDES FRESENTED TO NRC 10 THE APRIL 16, 1986 TVA/NRC HEETING ON PSB-1 TESTIllG
AGENDA
- 1. INTRODUCT10tl................. LICENSING (J.
4 A. TVA REPRESENTATIVE B. PURPOSE OF MEETING (1) PSB-1 TESTING (2) 9_ECTRICAL CALCULATIONS SBilTTAL MTED FEBRUARY 27,1985
- 11. PSB-1 TESTING................... OE (HUTSO A.
INTRODUCTION B. %CKGROUND C. NRC CONCERNS (RESPONSE T0 tRC LETTER DATED 3/2 (1) POSITION 4 0F PSB-1 '41TH POSITION 4 0F QUESTION (2) ADDITION OC T40 START BUSES AND ONE CO TRANSCORMERS (3) CNANGE DJT 0 100 VALE MOTORS (4) COMPUTER PRCEESSING SYSTEM CHANGES D. CONCLUSIONS /SIMiARY 111. E!_ECTRICAL CALCULATIONS SUB'ilTTAL DATED FEBRUARY i
y
..-,.y
,y.
c.w,m._,_
l DACKGROU'49 PRE-0/L
, IRC ISSUED QUESTl03 8.33 TO S01 FSAR (J!!LY 28,1978)
. FRC ISSUEC /AY 5,1980 LETTER
. POSIT 10!14 TO REQUIRE lESTING
. TELEPHONE DISCUSSION WITH tRC - JJtE 24,1980
. SCOPE OF TESTING - AGREEiEllT REACHED '41TH tRC
. VERIFICATION TESTlilG PERFRED (JJLY 1980)
. DOCUMEilTATIO!! SJR11TTED T0 tRC (OCTOBER 1980)
. TELEPH0'E DISCUSSION WITH tRC - APRIL 2,198101 U2 TESTING POST-0/L i
. IRC SITE VISIT AT S0tl - 1/14/85
. tRC LtlitR REQUESTING JJSTIFICAT10tl T0 TDT PERFW1 ADDITIO.1A'. TESTING 1/31/85
. TVA RESP 0'E TO J@l!1ARY 31,1986 LETTER 04 RBRUARY 12, 1985 tRC RESP 0llSE TO TVA JJSTIFICATION - %RCH 26,1985 4
4 I
.. ~,. _ _
e i
16l KV GRID COMMON STATt011 l............... I SE RVIC E TR AHS A I
"9 5
Y X
a O
O 6.9 KV Ut4tT LO 1 A O
O O
O 6.9kV SHUTDOWt1 BOARD I A-A O
O 1
o)
U O
ESSE 14TIAL 700 RAW C00u%
O HP WATER Put4P a) 480V SHt1TDOWH^) 460V SHUTDOWN O
DOAHD lAl-A I BO ARD I A2-A T
9 A
A A
A A
I i) AuAlttARY BD 480V REAC 480V REN:
_i VE NT ED g
DIESEL i MOV BD 15 0 AUXILIARY BLDG 480V C 4 A GENERAL SUPPLY FAH BLOG VENT BD i
I
ITBi 4:
POSITION 4 0F PSB-1 VS. POSITION 4 0F QUESTION 8.33
. POSITIO!! 4 0F QUESTIDs) 8.33 - REQUIRBENTS
. VERIFY ADEQUACY OF ISIGN BY ACTUA. MEASURBi91TS
. CORR 0_ ATE fEASURED V4.UES WITH AN4.YSIS RESULTS
. PROVIDE A DESCRIPTIO!! T METHOD FOR V81FICAT10tl
. PROVIDE DOCUMENTATION OP \\ERIFICATION
. POSITION 4 0F PSB-1 REQUIREM91TS
. VERIFY At!ALYTICA'. TECHBil0UES/ ASSUMPTIONS BY ACTU4. M'ASURSOITS
. VERIFICATl0tl TEST CRITERI A SPECIFIED
. E LOADING OF STATION DISTRIBUTION BUSES (120/208V LEVEU
. RECORD VOLTAGES AT STEADY STATE AND AT MOTOR STARilNG
. CORR 8_ATEMEASURCDVALUES
. ESTABLISHED 3% CRilERIA
. TVA /GREES WITH tRC THAT l!ITENT IS THE SNE 5
, TVA SATISCIED LICENSING REQUIRE 8!TS
. SCOPE 0 TESTING DISCUSSED WITH tRC AND KREED TO P1 JUNE 24,1980 TELEPHONEDISCUSSION
, VALIDATIO?! TESTING PERFORMED JLY 1980
. SUBiliTED VA_IDATIO'l TEST RESULTS T0 tRC - OCTOBB 3,1980
FGuRE 1 ITEM i:
AddiHon of two darf buses and one common stahon service fransforener CONFIGURATION I - 1980 i
CONFIGUR ATION 2 - 1980 CONFIGURATIDH 3 - PRESENT COMHow stat:0H L.;
. _,y,"'[C,E "gy jg C6HMON STATS 0N t.
_1.
s v,ics 1$'Uv', sp
__s A
coggo, giar,ow cr' "'"
, q-6 s soevert TmAMs A T OPree r-1 T
K c- ~m 4)
K gg,,,3,,
t) 4i START tut B
"*)
d sTAmT aus A l'
d) staar sus e 6.9uV todtf LimV tasif acame ic i T soAan iA o)
,,)
,,)
)t) o)
,,)
)
(l i
4 3WV useif 6.9Ev tellT SOA8UP IA 11ARD 10 A9tiv.D SC testT A9WV uuff 1
SCA honap eA.
k9Ev useT E9 av ausaf gpAa# f& DOAa0 ID
)
,,)
9) f m.9 KV Sisu1N>Wat 6
a+*
r I)
(I t. List.y Sa.iuTDOWN (b
59xv I m..saan..powei
_t
.iny ass.trypown k
l
\\
0A..
N McM ETATiest
_ a....c. m,u c a
P e9 STAftT 64316 i
<,<v..o,,,,t )
,),.4.o...
.e
.. io i
A,,)
I db 1
6
?.9.m.v.SausiteWes i
. iA.a l
I
ITEM 2: CHANrf OUT Oc 100 VA'.tE MOTORS
. THE ffFECT OF Te,ESE CHEES HAVE EEN ADORESSED IN WA's B_ECTRICA'.
RESTART CA'_CULATIO!!S
k d
ITEM 3:
COMPUTER PROCESSING SYST91 CHANGES 4
4 RESTART B_ECTRICAL CA_CULATIONS USED MORE MODERN RfD F METHODOLOGY MICROCOMPUTERS VS. MAINR41E TVA "IN-H30E" PROGRA4S USED FOR APS S.ECTRICAL CALCULATIONS
- VBSl: MAINRAiE FCRTRR1 PROGRAi l
- RADIAL: MICR0/MAITRAiE PASIC LOAD FLOW PROGRAi
- VOLT:
MICR0BASICPROGRAM t
- VOLT 2: MICR0 BASIC PROGR41 (PERFORMS POST-TRANSIENT At!D RU4114G CALCS) 1 I
t i
i
-,-~y,,
.,,,----..yo,-y-~,-
wy,-
--r..--%,, ~,,,
\\
ll 6
l 8
9 1
6 S
~
8 C
9 L
S 1
A C
C L
s D
AC c
N l
A T
A H
R C
A T
T S
R E
I A
R TS H
E Q
R S
wq S
6 8
5 l
9 8
7 9
14 9
8 l
T 7
L 88 DI 199S 9
2 A
- E S
T 1
T L
C L
O A
Tn V
R SSo S
A CEi C
C LTT L
T A A A
S L
l CD C
P O
SI A
V S
L S
PS A APv P
N.
A t
NH H B
sBL N
(
[w W(S OS 9
N 7
I 9
AW 1
HO W
k oL f
pF
)
c' E
L 1
H c-V i
LE BG u
P l
((
ill
,11.
i SH4ARY/C0tEUJSTONS l
NO MODIFICATIOtls PERPRMED TO ATECT 1980 VN.lDATION TEST RAJin., VOLT, AND VOLT 2 HAVE BEEN VRIDATED BY R1/CCEPTABLE METHOD 4
PSB-1 TEST RESULTS ERIFIED ADEOUACY OF WEi AND RAD!R ACCEPTABILITY OF VB4 RfD RADIR TO PERFORM VOLTAGE ANRYSES AP NRCREVIBl0FWBN 1980 SON ERIFICAil0N TEST DEMONSTRATED TVA'S ABillTY TO MODEL R1D PERFORM VOLTAGE R R YSES 4
Y.
t
-i
---..-,-,_,,,.._,-_,,,m.
,..-m.
m
,r-
, =.-,.,,, _.. -. -
.