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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F9701999-10-14014 October 1999 Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections ML20217E4301999-10-12012 October 1999 Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations ML20211M7341999-08-30030 August 1999 Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times ML20211K1721999-08-30030 August 1999 Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves ML20209B7731999-06-30030 June 1999 Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196F2211999-06-24024 June 1999 Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20196G4701999-06-24024 June 1999 Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196G7961999-06-22022 June 1999 Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators ML20196G8071999-06-22022 June 1999 Revs to Technical Requirements Manual ML20195E9841999-06-0707 June 1999 Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1611999-04-29029 April 1999 Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20206E1391999-04-29029 April 1999 Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations ML20204E8501999-03-21021 March 1999 Plant,Four Yr Simulator Test Rept for Period Ending 990321 ML20204H4081999-03-19019 March 1999 Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual ML20199K6001999-01-15015 January 1999 Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection ML20195H6111998-11-16016 November 1998 Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting ML20154H7251998-10-0808 October 1998 Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1091998-08-27027 August 1998 Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F3001998-08-27027 August 1998 Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs ML20209J1631998-08-0707 August 1998 Rev 41 to Sequoyah Nuclear Plant Odcm ML20236G5961998-06-29029 June 1998 Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions ML20249C6371998-06-26026 June 1998 Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248F0051998-05-28028 May 1998 Proposed Tech Specs for Section 6, Administrative Controls Deletions ML20217N3511998-04-30030 April 1998 Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1681998-02-25025 February 1998 Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J6961998-02-13013 February 1998 Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20202J7601998-02-13013 February 1998 Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements ML20198T4311998-01-21021 January 1998 Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization ML20199F8231997-11-30030 November 1997 Cycle 9 Restart Physics Test Summary, for 971011-971130 ML20199K4571997-11-21021 November 1997 Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3191997-09-17017 September 1997 Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20203B9731997-08-0505 August 1997 Rev 1 to RD-466, Test & Calculated Results Pressure Locking ML20217J5581997-07-31031 July 1997 Cycle Restart Physics Test Summary, for Jul 1997 ML20210J1671997-04-30030 April 1997 Snp Unit 1 Cycle 8 Refueling Outage Mar-Apr 1997,Results of SG Tube ISI as Required by TS Section 4.4.5.5.b & Results of Alternate Plugging Criteria Implementation as Required by Commitment from TS License Condition 2C(9)(d) ML20137T0871997-04-0909 April 1997 Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria ML20137M8581997-04-0101 April 1997 Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits ML20137C8421997-03-19019 March 1997 Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel ML20136J0381997-03-13013 March 1997 Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks ML20134P8631997-02-14014 February 1997 Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b ML20134K9981997-02-0707 February 1997 Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs ML20138F2581997-01-17017 January 1997 Rev 39 to Sequoyah Nuclear Plant Odcm ML20134L9261996-11-0808 November 1996 Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable ML20129D2661996-10-18018 October 1996 Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units ML20129G7301996-09-26026 September 1996 Proposed Tech Specs 3/4.3.3 Re Fire Detection instrumentation,3/4.7.11 Re Fire Suppression Systems & 3/4.7.12 Re Fire Protection Penetrations ML20134J9991996-09-23023 September 1996 Fuel Assembly Insp Program 1999-08-30
[Table view] Category:TEST REPORT
MONTHYEARML20204E8501999-03-21021 March 1999 Plant,Four Yr Simulator Test Rept for Period Ending 990321 ML20199F8231997-11-30030 November 1997 Cycle 9 Restart Physics Test Summary, for 971011-971130 ML20203B9731997-08-0505 August 1997 Rev 1 to RD-466, Test & Calculated Results Pressure Locking ML20217J5581997-07-31031 July 1997 Cycle Restart Physics Test Summary, for Jul 1997 ML20210J1671997-04-30030 April 1997 Snp Unit 1 Cycle 8 Refueling Outage Mar-Apr 1997,Results of SG Tube ISI as Required by TS Section 4.4.5.5.b & Results of Alternate Plugging Criteria Implementation as Required by Commitment from TS License Condition 2C(9)(d) ML20064M0881994-03-0707 March 1994 Reactor Containment Bldg Integrated Leak Rate Test Sequoyah Nuclear Plant Unit 1 Conducted 931217-20 ML20099B8841992-07-0909 July 1992 Reactor Containment Bldg Intergrated Leak Rate Test Sequoyah Nuclear Plant Unit 2, Conducted on 920427-29 ML20029A3091991-01-31031 January 1991 Nonproprietary Sequoyah Nuclear Plant Unit 2 Cycle 5 Restart Physics Test Summary. ML20059H1881990-08-31031 August 1990 Nonproprietary Sequoyah Nuclear Plant Unit 1,Cycle 5 Restart Physics Test Summary ML20056A5321990-08-0606 August 1990 Reactor Bldg Containment Integrated Leak Rate Test, Sequoyah Nuclear Plant Unit 1 Conducted on 900504-06 ML20044B2191990-07-13013 July 1990 Eagle 21 Start-Up Rept for 900522- 0616. W/900713 Ltr ML20245B3631989-03-18018 March 1989 Reactor Bldg Containment Integrated Leak Rate Test ML20195J8251987-11-23023 November 1987 Insulation Wall Thickness Measurement of Silicone-Rubber Cables at Identified Failure Points ML20236V5171987-11-19019 November 1987 Qualification Test Program for Silicone Rubber Cables W/ Reduced Insulation Thicknesses for Use in TVA Sequoyah Nuclear Plant,Unit 2 ML20236T5381987-11-13013 November 1987 Rev 1 to DC High Voltage Cable Test Rept ML20236Q1871987-10-13013 October 1987 Elevated Temp Test Rept & Mechanical Pull Test Rept for Littelfuse Flas 5,5 AMP Fuses Lot 2,3,4 & 6 ML20236T9461987-09-0303 September 1987 Rev 0 to Special Test Instruction STI-23, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage Conduit MC1730B, Incorporating Instruction Change Icf 87-1616 ML20236T6421987-09-0101 September 1987 Rev 0 to Special Test Instruction STI-34, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage - Conduit Mc 1497B, Incorporating Temporary Change 87-1520 ML20195J8031987-08-31031 August 1987 Impact Testing of Rockbestos & Anaconda Cables ML20236T9891987-08-31031 August 1987 Rev 0 to Special Test Instruction STI-29, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage - Conduit MC1606A, Incorporating Temporary Change TCF 87-1623 ML20236T8481987-08-25025 August 1987 Rev 2 to Special Test Instruction STI-17, DC High Voltage Test for Selected Unit 2 1E Cables in Vertical Drop Configuration ML20236T6141987-08-17017 August 1987 Rev 0 to Special Test Instruction STI-33, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage ML20236T9781987-08-0303 August 1987 Rev 1 to Special Test Instruction STI-28, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage - Conduit MC1605A ML20236T8641987-07-29029 July 1987 Rev 1 to Special Test Instruction STI-19, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Jamming, Incorporating Change 87-1251 ML20236T9101987-07-29029 July 1987 Rev 0 to Special Test Instruction STI-23, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage - Conduit MC1748A, Incorporating Change 87-1176 ML20195J7721987-07-22022 July 1987 Impact Testing of Aiw Cable ML20236S0511987-07-22022 July 1987 Rev 0 to Special Test Instruction STI-31, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage Conduit MC1732B ML20236T8971987-07-21021 July 1987 Rev 0 to Special Test Instrustion STI-22, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage Conduit MC1728B, Incorporating Instruction Change Icf 87-1619 ML20236T9641987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-27, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage, Incorporating Change ICF-87-1283 ML20236T9261987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-25, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage Conduit MC1754A, Incorporating Change 87-1252 ML20236T9181987-07-21021 July 1987 Rev 1 to Special Test Instruction STI-24, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage, Incorporating Instruction Change ICF-87-1253 ML20236T8801987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-21, Cables ML20236T6521987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-35, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage ML20236T5931987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-32, Cables ML20236T5691987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-30, Functional ML20195J7581987-07-20020 July 1987 Tests on Silicone Rubber Insulated Control Cables ML20236A2541987-06-10010 June 1987 Rev 1 to Lab Tests of Air Entrapment in Slightly Sloped Sensing Lines & Consequent Pressure Transmission Error ML20215C5691986-05-30030 May 1986 Cable Sidewall Bearing Pressure Tests ML20154K7711986-02-14014 February 1986 Reactor Bldg Containment Integrated Leak Rate Test,Sequoyah Nuclear Plant Unit 1,Conducted 851203-05 ML20107F6541985-02-19019 February 1985 Reactor Bldg Containment Integrated Leak Rate Test, Conducted on 841120-21 ML20071B3981983-02-17017 February 1983 Reactor Bldg Containment Integrated Leak Rate Test, Conducted on 821208-09 ML18025B8521982-03-18018 March 1982 Revision a to Qualification Test Rept for Model 1801104-05 PSA 1/4 Shock. ML20039A7801981-12-10010 December 1981 Summary Auxiliary Feedwater Pump Endurance Test,Sequoyah Nuclear Plant Unit 2. ML20010H7341981-08-31031 August 1981 Catalytic Combustion Hydrogen in Presence of Methyl Iodide, Final Rept ML20004A9741981-05-19019 May 1981 Reactor Bldg Containment Integrated Leak Rate Test, Conducted 810214-15 ML20050D0091981-04-16016 April 1981 Main Steam Line Break Qualification Test on Okozel Insulation, Final Rept ML20008F8721981-04-13013 April 1981 Table 14.1-2a to Revised Startup Test Program ML20003F0931981-04-13013 April 1981 Startup Test Revisions. ML20050D0111981-04-0808 April 1981 Qualification Tests of Electric Cables Under Simulated Steam Line Break (Slb) by Sequential Environ Exposure to Environs of Thermal Aging,Radiation,Steam & Chemical Spray. ML20008E5551981-02-27027 February 1981 Insp Device in Lieu of Insp Ports. Photographs Encl 1999-03-21
[Table view] |
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o: .-
9 2
-e SEQUOYAH NUCLEAR PLANT UNIT 1 TEST REPORT: verification of the Adequacy of Calculations for the Sequoyah AC Auxiliary
, Power System l
OCTOBER 2,1980 8010070g;rgj
, ?! ', *
- S*
1 TABl.E OF C0" TENTS .-
I. Sumary II. TVA Conformance to NRC Staf f l'osit ion 4 - TVA propa. int t . at method III. Data Sheets:
Tabic 1: Test Configuration 1 Table 2: Test Configuration 2 IV. References and Test Results a
f e
e h
2 I. Summary On July 12, 1980 and July 16, 1980, TVA conducted tests on the Sequoyah Nuclear Plant AC auxiliary power system. The purpose of the tests was to collect data ( current, voltage, kilowatts, and running motors ) for a specific load configuration on a specified part of the power system.. Calculations were made for the same loading configuration on the same portion of the power system. The measured values were compared to the calculated values.
In all cases the calculated values were within the specified acceptance criteria for this verification exercise. Five percent
. was established as the maximum acceptable difference. As recorded in Section III of this report, the maximum deviation between an installed board voltmeter reading and its corresponding calculated voltage was less than two percent of the observed voltage. All voltmeter readings were near midscale. TVA believes that this exercise i establishes the adequacy of the analytical. methods ured in the design of the AC power systems for its power plants.
~ .
s
. 3 II. TVA Conformance to NRC Staff Position 4 -
A. Staff Position 4: Optimization of Transformer Tap Settings The voltage Icvels at the saf ety-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. Ve require that the adequacy of the design in this regard be verified by actual measurement and by correlation of measured values s analytical results. Provide a description of the method for making this verification and, before initial reactor
, power operation, provide the documents required to establish that this verification has been accomplished, B. TVA's Proposed Method of Testing:
The requirements set-forth above are not feasible nor realistic before initial reactor power operation, with the exception of optimizing the transformer taps for minimum load conditions.
Af ter reactor power is established, measurements could be taken for certain kinds of l'o ading such as normal operation, normal shutdown, etc. , but there would be no way to load the I =
system with all the emergency loads associated with an emergency r=w, = v - r 7 *
, y ,.
4 shutdown. In light of the above, our proposed method of verifying the adequacy of the design as calied for in the staff position is as follows:
For a given time, the configuration for a specified part of the auxiliary power system will be recorded along with data (current, voltage, kilowatts, and running motors) taken at specified medium- and low-voltage boards, and applicable grid ar.d/or generator voltages. Using this information, along with manufacturer's data for motors, transformers, etc., voltages will be calculated for the above boards using manual and computer-assisted methods.
Acceptance et?;eria for comparing the calculated voltages
! -with measured voltages will be established af ter test accuracy is established and before calculations are made.
Once the calculation methods are verificJ by comparison i
within the acceptance criteria, calculations performed previously by th'e same methods to predict operating vo1Iages and to verify transformer tap optimization for other conditions, loading, or configurations of the auxiliary power system, such as 2 unit trips, LOCA, etc.,
will be considered valid.
l 4
l-1
+ , , - - - - , . -m, - ~+> ,, ,r -
L.. -
S Data to be recorded Data Pofnts Voltage Current f }@[ Cloned Breakers 161-kV Crid X Start Bus B X X X 6.9-kV Unit Ed IB X X X X 6.9-kV Shu tdown Bd 1A-A X X X X 480-V Shutdown Bd 1Al-A X X X X 480-V Reactor Vent Ed 1A-A X X X X
' One Motor From Each Selected Board X (Measured at motor terminals) i e
b em
. e. **
. o C. Tests Conducted :
.~
The requirements for the testa defined above were Jr. ciporated in a special raaintenance Instruction in accordanco vi: 1 TVA's catablished procubires. Spec tal ?!a intenance in it suc
- i a, SMI-0-317-13, was written to incorporate the re.piir. c ta of EN DES. This di unent was rev Icwed and appreve.1 **y t it Plcnt Operating Review Committee (r011C) before imple~entat i. te': Ling was accomplished at the plant on July 12 and lo. I '.W* . Th+ is e tests were conducted as follow:
Test I conducted on July 12, 1980 - Tent Coniis: ara _ti.r 1_ ,
This test, as described inore fully in the special tair.t enance instruction, was with 6.9-kV unit boards 1B and ID conrected to the start hus B through CSST B x-winding with v-vir.:ing unloaded. Measurenents for voltages, current, hi i oin : t s ,
power factor, and recording of closid breakers were taien in i
accordance with the points of measurement tal le (at:qe! cd) .
Board met.crs, Ehere available, were utilizcJ aloan vit: brn:- h recorders and temporary meters. A complete list of . g:!pnent 1 .
used is listed in the test instruction.
i h
Tent 2 conducted on July 16, 1980 - Tes t Ccnf i+;a:;a,t i y 2, i
This test, as described tuore fully in the special r.i: enance 1
instruction, was with 6.9-kV unit boards 1B and !B . er . eted ~
to start hus H through CSST B x-winding. Thr.iu.h C.:PI P.
u er!r g* y -y -- e e e .3-# er ww--e py y* -*-++ve-mp .y- ,y ge m , <-eere.+,ey. ~~-- a v -+ e -=-e-, y,-,w---w-- w. --,,,,",: 9-,5w - ,- ~ - w ,-e ww-
. b y y-windir.g, 6.9-kV unit 1 oards IA and 1C were connect in to
~
start bus A. !'nf t. 2boardsandconm.inboaro)t,ere Iac' icd through their respective USST's. Measurement < fier ve!: age 44, currents, kilowatts, power factor, and recordinr. of riosed breakers were taken in accordance with the peit:t , of asurenant
, tabic (attached).
In addition, a 6.6-kV and 480-V motor were started ar. the results recorded.
9 6
6 m
. i j g Points for Meanu.c. ment ,-
- Sequoyah Nuclear Plant, tinit 1 f e
Va rtureter Recor.1 >r
. o:- 'end Frc, file Data Points VM AM k'M PF l'et er _
C . *i; r. . Long g ., ,
. ' Start Bus A XE XE XE X X Start Bus B XE XE XE X X 6.9-kV Unit Bd 1A XE XE XE 7 XI
'6.9-kV Unit Bd 1B XE XE XE X X X X!
6.9 kV Unit Bd 1C XE XE XE X- XI 6.9-kV Unit Bd 1D XE XE XE X XI
'6.9-kV Motor Term X X X
- 6.9-kV Sd Bd 1A-A XE XE XE X X ': XI
'480V Sd Bd 1 A1-A XE XE XE X X X
- 480V Sd Bd 1A2-A XE XE XE M
'P.eac Vent Bd 1A-A X X X X X Y
. 'l;80V !!otor Term X X X
'C&A Vent Bd 1A1-A~ X . X
'REAC MOV Bd 1A1-A X -
'DSL Aur Bd 1A1-A X X i 'ERCW MCC 1A-A XE XE Y i
(
XE: ExistingIndicatinginstrument
- X: l'oninutalled Indicating Ir.strument 4 .
8: Train A Only Tests 1 & 3 1 I
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m III. DATA SHEET _
A. Table 1 ,
Station-service bus voltage supplied from CSST B observed reading versus calculated results Test configuration 1 161-kV Grid ac 163-kV
- CSST B voltage tap ratio: 156975-V to 6900-V Obcerved Results+
Calculated Results Load Voltage Load MW Mtr/ Meter Brush Rec
' ~ - -
Board MW# 9' Voltage Brush 0+ V VAB/VBCX L
6.9-kV Start Bd A 0 0 71,52 0 0 7200 NC .
6.9-kV Start Bd B 13 95 22.92 7011 12/13 2 21 7000 6573/6363 6.9-kV Unit Bd 1B - -
7011 7.8/7 9 24 7130 6766/6681 6.9-kV Sd Bd 1A-A 2.89 26.1 7004 2.6/1.7 24 7000 -/7042 480V Sd Bd 1Al-A .817 30.78 495 .67/.69 24 495 495/491 480V Reactor Vent Bd 1A-A .072 26.59 483 -/.096 35 434 443/452
- - B. Table 2 -
Station-service bus voltage supplied from CSST B observed readings versus calculatei resul ts .-
Test configuration 2 161-kV Grid at 164.5-kV CSST B voltage tap ratio: 156975-V to 6900-V-Observed Beruits+
C,1culated Resulte Load Voltage M4 Mtr/ Me;er Brush Rec Load MW Voltage Brush $+ V VAB/VBCX
.y Board D*
6.9-kV Stare, Bd A 15.4 24.1 7044 10/ . - 7003 -
6.9-kV Start Ed B 15.4 21.2 7057 13 7/14.4 24 7090 6999/6999 6.9-kV Unit Bd 1B - -
7057 7.3/8.16 27 701] 6787/6570 6.9-kV Sd Bd 1A-A 2.94 26.5 7049 2.4/2.21 28 7103 6787/699c 480V Sd Ud 1Al-A 94 30.4 493 .65/.72 36 S90 502/495 480V Reactor Vent Bd 1A-A .072 26.6 NC -/.096 49 439 467/.
Start of ERCW pp QA (Motor term V) 6763 6787 Start of AB Gen Sup Fan 1A (Motor term V) 449 466 Load in MW at an angle 9 where Cos 9 equals the pewer factor.
The load and voltage results indicate meter readings versus the brush r? corder r ead:
Voltage between A to B phase and b6 tween B to C phase.
__ _- _ ._ _ .m._ - _ __
m :.y gan m w* *e^ ' ,' - u m ,< m w W xy ?<g w m .. - -
+ n m m ~. - .y n.
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- ,1 _w", -,,.;
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<v n IV.. REFERENCES AND TEST RESULTS
._p s -
p, . . , A. Purpos'e , , , , ,
.Toverifytheadequacyofthedesignreview
- ~
calculations for Sequoyah Nuclear Plant's ac '
auxiliary power system.
-B. Requirements-
.l To satisfy NBC Staff Position 4, FSAR QP.33; C. Sources TVA (Sequoyah Nuclear Plant) drawings i
i Main single lines 45N504 45N505 45N506 AC APS key diagram' 15!1500 3
6.9-kV switchgear single' lines . 45N713 l 45N721-1 45N724-1 l 480-kV switchgear and MCC 45N749-1,2
- single lines 45N751-1,2
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45N756-1.2 45N755-1,2 45N732-1,2 35W716-1 45N779-1
. 45N765-B,9 45N1755-1 i Manufacturer's drawings 33-47035-E62 contract 71-54499 807141-?,3,4 Manufacturer's motor data sheets-Manufacturer's transformer test sheets t
Sequoyah cable routing schedules FSAR k
4 i
i i
t
..~- -
d.6 L. .:n D. Discussion of Test .
July 12 ar.d .luly 16, 1980.
- 1. Accuracy n'~ equipment.
A. Board meters were of the 3-percet.t clavs.
B. Brush recorders were of the 3-percent cla w .
, C. Ammeters, voltmeters, and power fac*or neters connected temporarily to the boards vere of the 3-percent class.
- 2. Results.
Typically, the readings from the board roters and auxiliary supplied neters yicided more conr.istent resul:3. The brush recorded results are generally within 3 n.reent of the meters but did not yield consister.t resalt,. For the second test, ac RMS calibr.ition vol tages wer<. m ..rde.! at cach station but drif t of the brush trae:r.y.s 1:eri noticed within minutes of calibration. .\1so, "I and cl n.acc.:racies cxisted. The board rceters vera calibrated an th. rocrd whereas the brush recorders were calierat.:d in :3.e 1e.
The current input into the brush rcem di r- wt r : . ; so e
modified by Insertion of a special madt- shunt.
l
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=
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J r Starting motor voltage dip values were not rel):.1.i v established by test because of limitat tens in r l.e- I ns t rumen t-capabilities. In both cases, the dip us.s o.ily t i r approximately one cycle.
. 3. Acceptance criteria.
For this rest, the accuracy of t he installe.' h w i voltmeters was limiting. Five ocreent of t he b . nl voltmeter reading is established as the. n.1::imu.- ' rceptable difference between measured voltage c.nd c.ilculattt m.tane.
E. Results:
1 See sheet 9 for comparison of voltanes between calcaic:t ed and measured methods.
F.
Conclusions:
In all cases, the dif ferences between calcula tt-d .tnd rt asured l voltages were .lcss than the established limit.
i l
.