ML20085E143
| ML20085E143 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 09/23/1991 |
| From: | Piet P COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19298E647 | List: |
| References | |
| NUDOCS 9110180058 | |
| Download: ML20085E143 (30) | |
Text
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\ Downers Grove, Illinois 60515 September 23,1991 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
LaSalle County Station Units 1 and 2 Supplemental Response to Station Blackout (SBO) Rule NBC DocketNos. 50 37.3 and 50-3ZA______
References:
(a) B.L. Slegel (NRC) letter to T.J. Kovach (CECO) dated August 23,1931.
(b) M. Richter (CECO) to T.E. Murley (NRC) dated June 22,19C1.
Reference (b) provided Commonwealth Edison's (CECO) revised response to the SBO rule for LaSalle County Station. The NRC Staff has reviewed CECO's revised responso in the time period since Reference (b) and has requested additional information to enable the completion of their evaluation (Reference (a)) of SBO as applied to LaSalle Station. CECO's response to the Reference (a) questions are provided in the attachment to this letter. Supporting calculations are provided as an appendix to the attachment.
If there are any questions or concerns regarding this matter, plaase contact this Sincerely, E' 8 Peter L. Piet Nuclear Licensing Administrator 160,.
Attachment - CECe's Response to Questions on the LaSalle SBO Submittal N Appendix - Supporting Calculations to LaSalle's Supplemental SBO Submittal OJ cc: A.B. Davis, Regional Administrator - Rlli Senior Resident inspector - LaSalle Station (w/o Appendix) ,
- B.L. Siegel- NRR Project Manager j P. Gill - f4RR Electrical Systems Branch 0 i ),ta g Office of Nuclear Facility Safety - IDNS (w/o Appendix) 'y(
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ATTACHMEffT CECO'S RESPONSE TO QUESTIONS ON THE LASALLE SBO SUBMITTAL l
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- 1) ClassjEBatteryEmpacity Unit 1 and Unit 2 at LaSalle County Station (LSCS) each have a 125 VDC class 1E battery associated with their electrical division 1 and division 2. In addition, each unit has one 250 VDC class 1E battery, With the exception of the Unit 2, division 2 125 VDC battery all have been replaced to provide adcitional capacity. The replacement of the division 2 battery is schedulod for the 4th refuel outage (1st quarter of 1992), '
acity of the batteries for this Calculation 4266/19D30 event as discussed in Tab 5justifies the four of the LSCS SBOhour Ac ca11on tems calculation binder.
The loads which require sheddiny are tabulated on pages 8 & 33. They are also ,
repeated on pages 5-6 & 5 7 of 1 ab 5. Tabic 58, and in Calculation 4266/19D31, with additional references to the feeder breakers for the stripped loads and the riaximt'm time after SBO when the loads must be shed.
The load profile is included in Attachment B of Calculation 4266/19D30.
The methodology used to determine battery capacity is as follows:
.-The existing Electrical Load Monitoring System - DC (ELMS.DC) computer program files were used for this SBO calculation because they include the battery
. manufacturer's characteristics required in determining battery sizing, all de loads dwith their various characteristics such as intush and continuous current, when the load is energized, and the duration of the load), and they calculate the required number of positive plates and the battery capacity remaining. The ELMS DC loads for SBO were verified to be energized for the entire four hour SBO plus recovery, unless the load was shed. The exceptions to this are switchgear breaker cubicles, excitation cubicles, fire protection sirens, the TIP panel, and the diesel generator field flashing loads which are verified to be energized for fifteen minutes or less after the inception of SBO.
The assumptions pertaining to this calculation are listed on pages 2 & 28.
The design margin for t'is study was assumed as 1.0. The maximum temperature was set at the Technical S aecification limits. The aging factors are summarized on pages 46 & 47 for the existing and replacement batteries. The temperature factor, design margin and aging factor are allincoraorated in ELMS-DC. Note. ELMS DC calculates battery sizing using the methodo ogy of IEEE-485. The ELMS-DC program and Validation Program are discussed in further detail on pages 5 8 and 5-9 of Tab 5 of the LaSalle SBO Action items calculation binder.
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- 2) Effects.of_the.LostoflWAC The areas of concern at LaSalle Station due to the loss of ventilation were chosen from rooms that based on documented engineering judgment (1) contained SBO response equipment, (2) have substantial heat generation terms and (3) lack normal heat removal systems due to the blackout. The Ma!n Control Room, Auxiliary Electric Equipment Room and the RCIC room satisfy this criteria. Areas immediately adjacent to these areas of concern were considered, as well as the floors immediately above and below, in determinlreg heat flow and heat contributions. Additionally, a temperature transient analysis was performed on both the Drywoll and Suppression Pool to determine the maximum expected-temperature and equipment nperability.
The Main Steam Tunnel was considered for the temperature heat up analysis but a review revealed that it did not contain SSD equipment credited for SBO, nor RCIC iso;ation temperature instrumentation.
The RCIC pipe tunnel and the RHR A&B rooms contain ambient and differential temperature instrumentation for steam leak detection. However, the RCIC turbine isolation valves which are affected by this logic (1/2 E51-F008,1/2 E51 F003 & 1/2 E51-F076) are all normally o)en valves which are AC powered and AC controlled.
Thus, during an SBO event t1e loss of HVAC is not an isolation concern for RCIC operation as these valves remain open.
The HPCS dieselis available as an Alternate AC source during a station blackout.'
This source powers ventilation in the HPCS rooms. Since ventilation will be provided if the HPCS is used during a station blackout, equipment operability is established and no heatup analysis is required in this area. -
The methods used to calculate the temperature rises are identified in each calculation listed below.
Caledlom Subject 3C7-0290 001 Main Control Room Temperature Transient Following SBO 3C7-0290 002 RCIC Pump Room Temperature Transient Following SBO SB-1 Control Room & RCIC lemperature During an SBO 3C7-0289-001 Auxillary Electric Ecluipment Room ' :
Temperature Transient During an SBO !
3C7-0390 001 Sup Pool Temperature Transient following SBO 307-0390-002 Drywell Temperature Transient following SBO i The assumptions are identified in the calculations listed above.
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NDNO[@E IM 3-l Those specifically requested in this letter's reference document are noted below:
(A) Calc. 3C7-0290 001 - Assumptions are listed on page 6.
Initial room temperature is 73*F and heat load (held) constant) is 112,662 BTU /hr. Ma'.orial properiles are:
Concrete wall - density - 145 lbm /Il3 Cp- 0.156 BTU /lbrn- F K - 0.92 BTU /hr ft F Gypsum Board - density - 100 lbm/ft3 Cp- 0.2 BTU /lb m *F K - 0.42 BTU /hr ft *F The Time versus Temperature orofile is shown on page 10. Temperatures fur adjacent external rooms were c etermined by Calculation SB-1 and held constant for the entire four hour SBO.
(B) es 9 and 10.
Calculation 3C7temperature The initial room 0290-002 is- T120.2*F he Assumptions are and the heat listed load is 1on pah7,070 BTU /hr for the first minute and 80,067 BTU /hr for the remainder of the SBO. The tem 3eratures of the adjacent external rooms and soll were determined and helc constant for the entire four-hour SBO. The soil temperature of 52*F is based on the average ground water temperatures in lilinois at a depth of 30 to 60 feet. This temperature is appropriate since the floor of the RCIC pump room is located approximately 37 feet below ground and the average ground water and soil temperatures would tend to be equal to this depth. The materials properties of the walls are listed in Calculation 3C7-1082-003, page B4 and are:
Reinforced concrete wall - density - 145 lb /ft 3
- C KP=- 0.92 0.156BTU BTdb /hr ft$- F The Tamperature versus Time curve is shown on page 18 of Calculation 3C7-0290-002.
(C) Calculation SB The Assumptions are listed on page 3. l he maximum temperatures of the rooms adjacent to the Main Control Room and RCIC Pump Rooms are listed on pages 24 26 of the calculation.
(D) Calculation 3C7-0289-001 The Assumptions are listed on pages 8-10. The initial room temperatures are 75*F inside the four auxillary electrical equipment rooms (AEER), and the rooms above and to the sides of the AEER are held constant at 104*F. The rooms below the AEER are held constant at 100*F. The heat loads are listed on page 8 as:
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\ 4.939 BTL (S AEER, Unit 1 17.07 BTU /se 't AEER, Unit 1 19.91 BTU /sec. SE AEER, Unit 2) 2.636 BTU /sec. NW AEER, Unit 2)
The material proporties are:
Reinforced concreto - density = 145 lbni/ft3 Cp = 0.156 BTU /lb m *F K = 0.92 BTU /hr ft *F Firewr,lI,12" thick - density - 53.7 lb m ft 3 Cp = 0.156 BTU /lb m *F K = 0.300 BTU /hr ft *F Firewall, 8" thick - density - 53.5 lbm-ft 3 Cp= 0.156 BTU /lbm - F K = 0.203 BTU /hr ft- F The Temperature versus Time curve is shown on page 16 of the calculat!on.
The uninterruptible power supply (inverter) has an efficiency of 80 percent (minimum) on the 480 VAC input. For the DC input, the power requirements are 210 260 volts DC and 100 amperes for the 25 KVA output inverter fed from the 250 volt DC battery.
The main control room and RCIC pump rooms do not require any access doors or cabinet doors to be opened. The auxiliary electrical equipment rooms require the following doors to be opened:
Access Doors - D262 and D266 opened within 30 minutes of initiation of SBO. (page 10 of Calculation 307-0289-001)
Panel Doors - Open all doors within 30 minutes of initiation of SBO (Tab 4, page 4 6).
Engineering has recommended that procedure LOA-AP-08 be revised to orovide instructions for those access and panel doors during an SBO.
(E) The containment temperature analysis is found in Calculations 307-0390 001
(" Suppression Pool Temperature Transient Following SBO") and 3C7-0390-002 ("Drywell Temperature Transient Following SBO"). The suppression pool analysis is described un page 5 and the methodology on page 7 of Calculation 3C7 0390 001. The maximum expected temperature of the suppression poolis 215'F for RCIC operation and 233*F for HPCS operation (page 11 of the calculation), both within the acceptable range of CECO's HCTL curve. The drywell analysis is described on page 5 and the methodology on page4 610 of Calculation 3C7-0390-002. The maximum i
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- smwmuo 5-t expected drywell air temperature is 293*F, f ar below the Technical Specification /FSAR design limit of 340*F. (page 13 of the calculation). The initial suppression pool temperature is assumed to be 105'F and the drywell atmosphere temperature is assumed to be 135*F at the initiation of the SBO.
(See page 17 of Calculation 3C7-0390-002 for additionalinitial temperatures involved in dryweil heatup.) The material properties used in the drywell temperature analysis are listed on page 20 of Calculation 3C7-0390 002. The effect of these elevated temperatures was compared to the maximum design operating temperature of the SRV solenoids (320*F for six hours and 340'F for three hours) and the RCIC pump suction parameters hich requires that the suppression pool temperature must not exceed 228 F in calculation 4266/19Al29. It was concluded that the SRV soleno s and the RCIC pump will continue to operate as required. Additionally it was determined that although slight RCIC pump coalleakage occurs during the analyzed condition it does not adversely affect the RCIC equipment or seals.
- 3) ContainmentIsolation The LSCS list of containment isolation valves (FSAR Table 6.2 21) was reviewed to ensure that the isolation functions and position indication can be 3rovided during an SBO event. Position Indication is considered acceptable f it includes local mechanical indication, DC powered indication (including AC Indicators powered from inverters) and Alternate AC powered mdication. The acceptable means of valve closure include manual operation, air operation (including air operated valves that are mechanically closed on loss of air), DC powered operation and Alternate AC powered operation. As recommended in NUM/,RC 87 00 the following critoria was used to exclude valves from consideration:
1 valves normaily locked closed during operation; 2 valves that f ail closed on loss of AC power or alr; 3 check valves; 4 valves in non radioactive closed loop systems not ex aected to be breached in a station blackout (with the exception of ines that communicate directly with the containment atmosphere); and,
- 5) all valves less than 3-Inch nominal diameter.
Since independent valve f ailures are not assumed to occur during a station blackout, a valve in line with an excluded valve was also excluded from consideration. In addition, valves which continue to be powered and operablo during a station blackout do not require manual operation capability. The attached Table 5-1 lists the valves reviewed and their exclusion justification.
When multiple valves are in line with one penetration, all the valves are listed but only one valve would need to be closed. Table 5 2 (also attached) lists the valves that would require operator action and verificaVon of closure. The procedures that may requ to revisions to provide containment isolation guidance are LOA-AP-08, LOA PC 01, LOA MS-02, LOA-RH-04, LOA R 03, LOA RT-02, and LOS-HG SA-1. These procedure revisions will be completed one year after the notification provided by the Director, Office of Nuclear Reactor Regulation in accordance with 10CFR50.63(c)(3).
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Full containment isolation is not expected to be necessary as a result of a station blackout. However, Regulatory Guide 1.155 requires reactors to have the ability in station blackout conditions should this be to maintainfor" containment necessary other reasons.integrity Suc *h other reasons could include technical '
specification requirements to close certain valves following a loss of offsite power, loss of decay heat removal capability, or other casualties affecting the reactor coolant system.
- 4) Wahrt.and_ Heat hvorWory 7
LaSalle's station blackout coping method uses RCIC or HPCS to provide makeup water for core coolln;l. The LaSalle HPCS system normally takes suction from the suppression no , and RCIC suction automatically transfers to the suppression poo on low condensate storage tank level. Decay heat is removed by discharge of steam through the Safety / Relief Valves into the suppression pool, where the steam is condensed. As a result, gradual heatup of the suppression pool is expected.
A calculation (3C7 0189 001) has been performed showing that the suppression-pool water inventory is sufficient to make up for decay heat removal requirements -
and expected leakage during a four hour station blackout. A separate calculation (307-0390 001) has been performed to demonstrate that the suppression pool temperature can be kept below the heat capacity temperature limit curve (LGA G1, from procedure LGA 03,
- Primary Containment Control") while providing this water, The condensate inventory analysis was performed in Calculation 307-0189 001.
Specifics of this calculation are:
Methodology - Determine if the suppression pool contains sufficient water for a four hour SBO with the ,
reacto' at cooldown, (Using either RCIC or HPCS cooling system), Used NUMARC B7 00, Section ,
7.2.1 procedure.-(page 2 of calculation).
Astumptions - Water is not available from the condensate inventory tank. Losses in inventory through safety relief valves and RCIC turbine do not return to the suppression pool. The RCS leakage is 61 GPM, Gallon to LBM conversion is conservatively based on water at pump conditions.-
Water needed to decay heat removal removal - 166,500 allons, HPCS mode 166,936 allons, RCIC mode No mass is returnad to the suppression pool from RV operations, l
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Water lost from the suppression pool from SRV operations, RCS leakage, and RCIC turbine leakage - 14,640 gallons, HPCS mode
- 15,121 gallons, RCIC mode Suppression Pool Data: (Ref. calc. 307-0390-001, Page 17)
Initial Pool Temperature - 105'F Pool Heat Structure Surface Area - 46,350 ft 2 Pool Heat Structure Mass = 1,043,000 lb m Overall Heat Transfer Coefficient - 100 BTU /hr-ft2 F Pool structure Specific Heat - 0.111 BTU /lb m *F Suppression Pool Water Level af ter Four-Hour SBO - 695 feet, both rnodes (drop of 4.7 feet)
Since over 900,000 gallons of water are available in the suppression pool, adequate condensate Inventory exists.
The RCS inventory analysis was performed in Calculation 3C7-0390-001 (Tab 1).
Specifics of this calculation are:
Assumptions - SRV's cycle at their setpoints. The ANSI standard decay heat curve was used. Initial suppression pool temperature was 105"F Manual depressurization cooldown at 100"F/hr imposed until vessel pressure reached 167 psia. Following termination of manual depressurization cooldown, operator controlled SRV actuation was implemuted to control vessel 3ressuro between 167 pela and 172 asia. Primary system eakage of 61 gpm, with a latent heal load based upon 40 percent flashing, is assumed to be added directly to the suppression pool.
Sensible heat removal from RCS fluid and structure - this was included in the model using the following data:
RPV heat structure mass - 3.055 x 108 lb RPV heat structure specific heat - 0.111 gTU/lb n F RPV heat structute area - 1000 ft RPV heat structure heat transfer coefficient - 10,000 BTU /hr ft2.ep BEY _PlessutaaXersus.MassBowflate RCIC Pum RPV Mass Flow Rate Pressure (GEML- Cased JESIA).
0 0 0 164 600 165 600 1173 600 2000
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8 HPCS Pump RPV - l Mass Flow Rate- Pressure (GEM) - Case _2 .1PElA).
15.45 16795 215.45 6196- 515.55 <
5070 815.45 3774 1145.45 i 1611 1175.45 1339. :
Reactor levelis plotted on pages 26 and 32 of Calculation 3C7 0390 001,
- 5) SBOEquWmer(QAEragram The list of safe shutdown components required during SBO was reviewed cgainst i the LaSalle County O-list to determine which devices are not classified as either -
-safety related or regulatory related. The attached table lists the devices which will require a OA program meeting the requirements of Regulatory Gulde 1.155 AppervJices A and B.-
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STATION CLACKOUT DEVK:ES WHICH ARii NOT_SAFETYrHELATEDIREG ULATORYrRELATED
._DF.VIC EL _ DESCBIPllOR_
1/2E51-F261 RCIC GOV VALVE 1.2E51 F300 RCIC STOP VALVE 1/2G33 Z00132 A RWCU TO DEMIN VALVE 1/2G33 Z001328 RWCU TO DEMIN VALVE 1/2G33 Z00132C RWCU TO DENIM VALVE 1/2CM01M SUP POOL LEV GAUGE 1/2CM02M SUP POOL LEV GAUGE 1/2TE-CM037 SUP POOL TEMP ELEMENT 1/2T1-CM037 SUP POOL TEMP INDICATOR Ll1C61-R010 RX LEV INDICATOR Ll2C61 R010 RX LEV INDICATOR P11061-R011 RX PRESS INDIC Pl2C61 R011 RX PRESS INDIC
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LAsALLE COUNTY STATION BTATIEN BLACKOUT ANALY$15 }
COMMONWEALTH EDISON COMPANY _
Table 51 Containment Isolation Valves ;
+
ITNETRAT10N SIZE VALVE VALVE DESCRIFT10N (inches) NUMBER 1YIE DISPOSTT10N !
Main Steam 26 1&2521.F022A.B.C.D Air Opersand Globe shuu on loss of air '
26 l&2B21.F028 A.B.C.D Air Opersied Globe shuu on lou of air '
11/2 1&2B21.F067A.S.C.C Mow Opersind Globe less than 3" 11/2 1&2B32 F001 A.E.J.N Motor Opersand Osas less then 3" Reactor Feed 24 1&2821.P010A.B No Slam Cheek abeck valve :
24 l&2B21.PO?2A.B - AO No Slam Chesk dock valve 24 1&2B21.F065 A,B Motor Operaiad Geis in line with above check valve 24 l&2033.F040 _ Motor Operased Gene in line with above check valve i RHRS Shutdown Suction 20 1&2E12.F009 Motor Opernaed Gais .
20 l&2El2.F008 Motor Operased Gais RHRS Shuidown Retum 12 1&2E12 F050A,B No Slam Check check valve 12 1&2E12.F053 A.B Motor Opersind GW in line with above check valve 2 1&2E12 F099A.B Moiar Operated GW less than 3" LPCS lajertion 12 1&2E21.F006 No Slam Check check valve 12 l&2E21.F005 Moiar Operated Gau in line with above check valve HPCS Injection 12 1&2E22.F005 No Slam Check chuk valve 12 1&2E22 F004 Motor Opersed Gau in line with above check valve RHR/LPCI Infection 12 1&2E12 F041 A.B.C No Slam Check check valve 12 1&2E12 F042A.B.C Moiar Operased case in line with above check valve ,
S.eam to RCIC System - 10 1&2E51.F063. Motor Operated Gau I l&2ESt F016 Motor Opersied GW less then 3" 10 1&2E51.F064 Motor Operated Gate ,
4 1&2E51.F008 Mow Operated Gau ;
1 2E51.F091 Mon Operaad GW less than 3" >
Cooling Weer Supply 6 1&2WR029 Motor Operated Gese closed system in containment 6 1&2WRl79 Motor Operated Gme closed system in containment Cooling Water Retum 6 1&2WR040 Motor Operased Gus closed system in containtnent -
6 1&2WRiso Motor Operated Gais closed system in centunment RHRS/ Containment Spray 16 1&2E12.F017A.B Motor Operated Caie 16 1&2E12 F016A.B Motor Operaiad One Drywell Purte 26 1&2VQO30 Air Operated Buser0y shuu on loss of air 26- 1&2YQO29 Air Opersand Buser0y shuts on loss of air i 1/2 1&2VQ047 Motor Opersand Globe less then 3" 11/2 1&2VQ048 Motor Opermed Globe less then 3" 8 IA2VQ042 Air Operated Buno0y shuu on loss of air Vent from Drywell - 26 1&2VQO34 Air Operased Buner0y shuts on loss of air 2 1&2VQO35 Motor Operand Globe less than 3" 26 1&2VQO36 Air Operased Bun.'rcy shuts on loss of air 2 1&2VQ068 Motor Opernied Globe less than 3" Drywell Pressure 3/4 1&2CM102 Escess Flow Check less than 3"
( RPV Level and Pressure 3/4 1&2B11.F571 Excess Flow Check less than 3"
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LASALLE COUNTY STATION STATION BLACKOUT ANALYSl5 C0%tMONWr ALTil FDISON COMPANY Table 51. Containintel isolation Yalves, cont.
PENCTRA110N SIZE VALVE VALVE DLSCRIPT10N (inches) NUMBER 1YPE DIsIOSF110N Mun Steam Draus: 3 1&2B21J016 Motor Operated Gue 3 l&2B21.F019 Motor Opersted Oate Combuiuble Gu Control 4 1&2HOOOl A.B Motor Operated Gate Drywell Suction 4 1&2)l0002A.B Motor Operued Clote Chilled Water Supply 8 1&2VIO63A.B Motae Operated Gate closed eystem in containment 8 1&2VPil3 A.B Mf) Butserfly closed system in centunm.at Chilled Water Return 8 1 &2VP033 A.B Motor Operated Gus closed system in contatrtment 8 1&2VP114 A.B MO Butterfly closed system in containtnent RCIC RPY Head Spray 6 1& 2E51.F066 No slam Check chuk valve 6 l&2E51.F06S No Slam Check chuk valve 6 1&2E51.F013 Motor Operated Gate in line with aleve chuk vihe 6 1&2E12.F023 Motor Operned Glote in line with stove chuk valve Reactor Cleanup 6 1&2033 F001 Motor O ierated Gate 6 1&2033 F004 Motor Operced Gate Standby Uquid Control 1 1/2 1&2C41.F007 No Slam Check less than 3" 11/2 1 &2C41.F006 No Slam Check less than 3" 11/2 1 &2C41.F004 A.B Esplosive less than 3" Rutre loop Sampling 3/4 1 &2B33J019 Air Opeested Glote less than 3" 3/4 1&2B33.F020 Air Operated Glots less than 3" Clean Condensate 3 1&2MC033 Gass normally locked shut 3 1&2MC027 Gue normally locked shut Service Au 3 1& 25 A046 Gue normally locked shut 3 l&2S A042 Gue normally locked shut CRD inscruon i 1&2Cll.0001 120 Solenoid Operated Gate less than 3" 1 1&2Cil .0001 123 Solenoid Opetued Gue less than 3" CRD Withdraw al 3/4 1&2Cll.0001 121 Solenoid Operated Gate less than 3" 3/4 1&2Cl1 0001 122 Solenoid Operated Gue lus than 3" TIP Dnve 3/8 1&2C51 1004 solenoid Ball lus than 3" Air Sulyly 3/4 1&21NO31 Solenoid Opented Clotw Ins than 3" Hydieubc Piptng 3/4 1&21133.D38 A.B solenoid Operased Glotw lus than 3" 3/4 l&2B 33.F339 A.B solenoid Opersted Glots lui than 3" 1/2 1 &2B33.D40 A.B Solenoid Operated Glots less than 3" 1/2 1&2B33.M41 A.B Solenoid Operated Gbbe less than 3" 1/2 1&2B 33.M42 A.B Solenoid Crperated Clots less than 3" 1/2 1&2B33J343 A,B Solenoid Operned Ghte lets than 3" 3/4 l&2B33.M44 A.B Solenoid Operued Glotx lus than 3" 3/4 1&2B33 D43A.B Solenoid Operned Globe leu than 3" RTV level 3/4 1 &2B 21.F570 Estes flow Check len than 3" Atr Dner Bla*do.n 3 1 & 21N074 Au Operated Globe shuu on loss of str 3 1 &2tN075 Au Operued Giot< shuta on loss of au m_.m_m_____.___m__-_______.m_____-____--_______m___ . - - -_._ _____. _ _ _ -
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D I LASALL.E COUhTY STATION STATION BLACKOUT ,ANALYSl5 COMMONWl'A1.TH FDISON COMPANY Table 51, Containment isolation Valves, cent.
PENTFRA710N SIZE YAL%T VALNT DESCRil' HON (inches) NUMBER 'nTE DISPO5 MON Drywell Pneumane 2 l&2IN018 No Slam Chuk less than 3" Comp. Discharge 2 l&21N017 Air Operued Globe less than 3" Drywell Pn. Comp. Suc. 2 1/2 1&11N001 A.B Alt Opersed Globe has than 3" ADS Pneumatic Supply 1 1&21N100 Solenoid Opersed Gloin bs than 3" Reactor Wuce Level 3/4 l&2B21.F372 Encas now Check less than 3" Clean Condensate to 2 1&2FCll3 Globe Ws than 3" Refueliag Ballows 2 l&2FClle Globe less than 3" ADS Pneumanc Supply 1 1&2tN101 Solenoid Opersed Glone W s than 3" Recirculation Pump Seal 3/4 1 &2B33.F013 A.B No Slam Check less than 3" injection Supply 3/4 1&2B33.F017 A.B No Slam Check Ws than 3" Reutor Well Bulkhead 10 1&2FC11$ Gus normally locked shut Drain 10 1&2FC086 Gua nnrmally locked shut Suppression Chamber 26 1&2VQO27 Air Operned Buner0y shuts on loss of air Purge Line 26 1&2VQO26 Air Operned Bucerfly shuts on lots of sit i 1/2 1&2VQ050 Motor Operated Globe less than 3" 11/2 l&2VQ0$1 Motor Operated Globe less than 3" 8 1&2VQ043 Air Operund Buner0y shots on loss of air 26 1&2VQO31 Air Operaiad Bucer0y shuts on loss of air Sulvession Chunter Vent Line 26 1&2VQ040 Air Operated Bunerfly shuts on loss of ur 2 la2VQO32 Motor Operated Globe less thaA 3" LPCS Suc. fr. Sup. Pool 24 1&2E21.F001 Motor Operned Gus HPCS Suc. h. Sup. Pool 24 1&2E21.F015 Hotor Operated Gate powered by 10 minute AAC RHR Suc. fr. Sup. Pml 24 1&2E12.F004 A Motor Operated Gus Sup. P,wl Water level 3/4 1&2CM002 Encess now Check kas than 3" RHR Suc. fr. Strp. Pool 24 1&2E12.F004C Motor Operated Gate Sup. Pool Water level 3/4 1&2CM010 Encess now Check less than 3" RilR Suc. ft, Sup. Pool 24 !&2E12 F004B Motor Operued Gus RHR to Sup, Pool spray 4 1&2E12.F027 A,D Motor Oprated Gus RCIC Suc. fr. Sup. Pool 8 112E51.F031 Motor Operced Gue DC operced RCIC Turbine Enhaus 10 1&2E31.F040 Check check valve 10 1&2E51.F068 Motor Operned Gus in line with above chuk valve LPCS Minimum Flow I4 1&2E21.F012 Motor Operued Globe 4 l&2E21.F0ll Motor Operated Gue LPCS Test IJne 2 1&2E12.F085A Relief less than 3"
4 LASALLE COUNTY STATION STATION BLACKOUT ANALYSIS COMMONWEALTH FDISON COMPANY Table 51, Containment holsilon Valves, cont.
PENETRATION SEE VALVE VALVE DESCRF110N (inche:) NUMBLR TYiE DISIOSTT10N RilR Mirdmum Flow 18 l&2E12.F024 A.D Motor Operued Globe and Test Lines 18 1&2E12.F021 Motor Opeemed Globe 14 1&2E12 F302 Case ramally locked shui 8 1&2E12.F064 A.B.C Motor Opersed Cate 4 l&2E12 F011 A.B Motor Opersed Cate 2 1&2E12 F088B Ralief less than 3" l
RCIC Minimum flow 2 1&2E51.F019 Moiar Opermed Globe less than 3" i RCIC Vacvurn Pump i 1/4 1&2E51.F069 Motor Opeesied Globe less than 3" Dischar8e i 1/4 l&2E.51.F028 No Slam Check less than 3" llPCS Test line 14 l&2E22 F013 Motor Operuc4 Globe powerca by 10 minute AAC l 11PCS Mirumum Flow 4 1&2E22 F012 Motor Operated Gus powned by 10 minute AAC I LPCS Relief Valve 4 1&2E21.F018 Relief check valve (only allows now into containment) 2 1&2E21F031 Relief less than 3" R11R Relief Valve 2 1&2E12F025 A.B.C Relief less than 3" 2 1&2E12F088C Relief less than 3" 2 1&2E12F030 Relief less than 3" 2 1&2E12F005 Relief less than 3" RilR Relief ValveNent 3/4 1&2E12.F073A.B Motor Operated Globe less than 3" 3/4 1&2E12 F074 A.B Motor Opanied Globe less than 3" 6 1&2E12 F0$$ Relief check valve (only allows flow into containmenti 2 1&2E12F311 Relief less than 3" RCIC Rebef Valve 4 1&2E12 F036A.B Relief check valve (only allows flow into containment)
IIPCS Rebei Valve 2 l&2E22.F014 Relief less than 3" Drywell Equipment Disins 4 1&2RE025 Air Operated Globe shuu on loss of air 4 1&2RE024 Air Operated Globe shuu on loss of sar D ywell Drain Cooling 2 l&2RE029 Air Operated Gbbe less than 3" 2 1&2RE026 Air Operued Glots less than 3" Drywell Floor Drains 4 1&2RF012 Air Operated Globe shuu on loss of air 4 1 &2RF013 Air Opermed Globe shuu on loss of air RCIC Turbine Exhaust 2 1&2E51.F0B0 Motor Ope:ued Globe less than 3" Breaker Line 2 1& 2E5 ).F086 Motor Opevued Globe less than 3" Vacuum Ilreaket 24 1&2PC003 A.B,C,D Buttafly nortnally manually operated Sup. Pool Wuct Level 3/4 1&2CM012 Excess Flow Check less than 3" Combustible Gas 6 1& 2110005 A.B Motor Operated Gate Control Return 6 1&2}{G006 A.B Motor Operated Gue Sup. Pool Water level 3/4 1& 2CM004 Escess now Check less than 3" b
LASALLE COUNTY STATION STATION BLACKOUT ANALYSIS COMMONWEALTil EDISON COMPANY Table 51, Containment isolation Valves, coni.
PENCTRATION EIZE VALVE VALVE DESCRIFnON (inches) HUMBER TITE DISIOSmON Vacuum Breaker 24 1&2PC001 A,B,C.D Varuwn Bretkes che4k vehe 24 1& 2PC002A,B,C.D Bunerfly in line with ateve chuk ,st e RPV biet and husure 3/4 1 &2B21.F374 Escus now Check leu than 3" RPV Level and husure 3/4 1&2B21 F376 Excess now Check leu than 3" DryweU llumidity 3/4 1&2CM017A Solenoid Operated Glots lui than 3" Monitor 3/4 l&2CM017B Solenoid Operated C ote less than 3" RPV Level a 't 1%4sure 3/4 1 &2B21.D59 Escess now Check less than 3*
Dryseu flumidity 3/4 112CM018 A Solenoid Operated Globe less than 3" M onitot 3/4 1&2CM0llB Solenoid Operated Globe less than 3" RPV Level ud Pressure 3/4 l&2B21 D$$ Escess now Check less than 3" RPV Level and hetsure 3/4 1&2B21 F361 Esc 444 Row Chuk less than 3" RPV Level and Pressure 3/4 l&2B21.F378 Escent now Check less than 3" Dryweu heasure 3 /4 1- " 4061 Esc 4:s now Check lui than 3" RPV ilead Seal Leak Det. 3/4 1E31.b o) Glote lui than 3" RPV Level and Pressure 3/4 1&2B21.F370 Escen now Check lui than 3" ADS Accumulator Press. 3/4 1&2B21 042D,Y.S Manual less than 3" RPV Level and Pressure 3/4 IB21 D63 Escess now Check less than 3" 3/4 IB21.D 53 Eacesa now Check less than 3" RCIC Steam now 3 /4 1&2B21.F415B Escess now Check less than 3" 3/4 1&2B 21.F415 A Exc4ss now Check less than 3" P imary Containment 1/2 l&2CM031 Solenoid Operated Glote less than 3*
Air Sample 1/2 l&2CM032 Solenoid 0; crated Clot = lesi Aan 3" Post LOCA Contureneni 1/2 1& 2CM022A Solenoid Opesated Globe less than 3" Monitortng 1/2 1&2CM029 Solenoid Operated Globe less than 3" 1/2 1&2CM030 Solenoid Operated Globe ten than 3" RPV Level and Pressure 3/4 1&2B21 F357 Escess now Check less than 3" ADS Accumulsior Press, 3/4 1&2.B21 E342E.R U.C Manual less than 3" Drymeu Preuure 3/4 1&2B21 DB2 Excess now Check less than 3" Steam now 3/4 1 &2B21.F328 A,B Enc 4:n now Chuk less than 3" 3/4 1 & 25121.F327 A.B Excess now Check less than 3*
RWCU now 3/4 l&2G33 D12A.B Escess now Check less than 3*
RilR Line Integnty 3/4 1 A 2E12.D15 Excesa now Chuk leu than 3" RCIC Steam now 3 /4 1 &2B21.F413B Encess now Check lui than 3" 3/4 1&2B21 F413 A Escesa now Check lui than 3"
. - - . - - - - . - - - - - . ~ _ - _ ~ - - - - . . ..- _ - ,- - .-.~
.7
. t i
LASALLE COUNTY STAT 13N STATICN BLACKCUT ANALYSIS
, COMMONWEALTH EDISON COMPANY
- Tab;e 31, Containment isolalloa Yalus, cost.
PENETRATION SEE VALVE VALVE DESCRD'T10N (inches) NUMBER 'IYPE DISPO5fDON 1.PCS/LPCI diff Press. 3/4 1&2E21 F304 Escass Nw Check less than 3" i
hi Pump Presswa 3/4 1&2821.F344 Encess Nw Check b than 3" h- Drywen Pruswo 3/4 1&2821.F363 Encess' Nw Check he than 3" Jet Pwnp Mow 3/4 1&2821.F43.A Essess Nw Cheek less than 3" ;
3/4 1&2821.F439 8 Baseos Nw Cheek less then 3" 3/4 142821.F437 C Escess Nw Check tas than 3" 3/4 1&2821 F441.D Eseess Nw Check - less than 3" 3/4 1&2B21.F445A.E - Esoses Nw Check he than 3" 3/4 1&2821.F447.F Eseems Nw Check less thei 3" .
Jet Pump Nw 3/4 l&2821.F453 D Escess Nw Oieck less than 3" 3/4 - 1&2821.F4458 F Eacess Nw Check he than 3" 3/4 l&2821.F455B E Encess Nw Check less then 3" 3/4 -l&2821.F455A A Encess Nw Check less than 3*
3/4 1&2B21.F4518 Encess Nw Check bs then 3" 3/4 l&2821.F449.C Excess Nw Check be than 3"
' Recire. Pump Seal Press. J/4 1&2833 F319A Encess Nw Check less than 3" 3/4 1&2833 F317A Encess Nw Check be than 3" Restrc Pump Nw 3/4 1&2833.F313C Encess Flow Check less than 3" 3/4 1&2B33 F313D Excess Nw Check less than 3" I 3/4 1&2B33.F311C Eacess Nw Check less than 3" .
3/4 1&2833 F3 TID - Encess Flow Check less than 3" Rectrc. Pump Ddt, Press. 3/4 _1&2833 F315A Excess Nw Check less than 3" 3/4 '1&2833 F315B Esc 4s now Chek less than 3" Rectre. Pump Suc. Press. 3/4 1&2833 F302A Encess now Check less than 3" Rectrc. Pump Flow 3/4 1&2B33 F307C Escus Flow Chuk las than 3" '
3/4 l&2B33 F307D Encess now Chuk less than 3" 3/4 1&2B33 F305C Encess now Check less than 3"
. 3/4 1&2833 F305D ~ Excesa now Check b: than 3" .
RHR Shudown Nw 3/4 1&2E12 F359A Escass Nw Check less then 3*
3/4 l&2E12 F359B Esc 4ss now Chak less than 3" RHR Line Integnty; 3/4 I A2E12.F319 Encess Nw Chec'k less then 3" 3/4 1&2E12.Dl? Escus Nw Check less than 3" Drywen Presswe 3/4 1&2B21.F367 Escas How Check less than 3" Recire. Pump Row 3/4 1&2B33 F307A Excess Flow Chwk less than 3" 3/4 1&2B33 F307B Excess Row Check less than 3" 3/4 1&2B33 F305A Esc 4ss Row Chuk less then 3" ~>
3/4 1&2B33.F305B Escess now Check less than 3*
' RHR Shutdown Nw 3/4 1&2E12-F360A Esc 44: Nw Chuk less than 3" 3/4 1&2E12 F3608 Esc 44: Flow Check less then 3" Recas. Pump Seal Press. 3/4 1&2B33.F319B Excess Nw Check less than 3" 3/4 l&2B33 F317B Escess Flow Check less than 3"
- __ .y _ -. -
.--.- . _ .._ ..~--__ ..
...-..--_.-.. _-,.........._. _ __ _ _ .~ - - =.. _ _ ,._.
I . LASALLE CEUNTY STAT 13N STAT 1DN BLACKOUT ANALYSIS COMMONWEALTil EDl%0N COMP ANY Table 51, Containtuent Isolation Yahes, cont.
PENEntATION S!ZE val.YE VALVE DESCRIFDON (inches) NUMrlER DT'E DLSIOSinON Recire. Pump Suc. Press. 3/4 1&2B33 F30lB E.u4s now Out lus than 3" Rectre. Pump Diff. Preu. 3/4 1&t333.F315C Excess now Deck ins than 3" 3/4 1&2B33 F315D bcus now Dect less than 3" Recire. Pump Mow 3/4 1&2B33.F313 A Euen now Check less than 3*
3/4 1&2B33 F313B Escess now Deck less than 3" 3/4 1&2B33 F311 A Eic4*: Mow Check leu than 3*
3/4 l&2B33 F311B bc4u now Onck less than 3" RPV Drain Mow 3/4 1&2G33.F309 Eues Row Deck lus than 3" Steam Flow 3/4 1&2B21 F326D Escess Mow Oak less than 3" 3/4 l&2B21.F325D Excess now cak less thm 3" 3/4 1&2B21.F323C Escus now Onck less than 3" 3/4 1&2B21.F326C Eu4:s Mow Oeck less than 3" ,
Core Differential Press. 3/4 l&2B21 F350 Eneas now Oak lui than 3" RPV Bot. Hd. Dsun Flow 3/4 1&2B21.F346 Esc 4:s How Check lus than 3" RPV/IIPC3 Diff. Press. 3/4 1&2B21.F348 Encess now Oak less than 3" s 3/4 1&2B21.F304 Excess now Oak le:ss than 3" MSIV Accumulator Prest. 3/4 1&2B21.F329 A.B.C.D Manual less than 3" Jet Pump Flow 3/4 i&2B21 F471.A Esc 4:s Flow Check less than 3" 3/4 1A1B21.F473 C Excess now Oak leu than 3" 3/4 1&2B21.F469 B Encus now Oak lass than 3" 3/4 1 &2B21.F469B.D Escans now Check less than 3" 3/4 1&2B21.F475B E Escus now Owck less than 3" 3/4 l&2B21.F47$A F Escus Row Check lus than 3" Jet Pump Flow 3/4 1&2B21.F465A A Excess now Dak less than 3" 3 /4 1&2B21.F467 B Eues Dow Check less than 3" 3/4 1&2B21.F457 E Eneas now Oak less than 3" 3/4 1&2B21 F459 D Escesa now Oak less than 3" 3/4 1&2B21 F461.F Enes: Row Oak lui than 3" 3/4 1&2B21 F463 C Encess now Check less than 3" Drywell Pressure 3/4 1&2G33 F380 Excess Flow Cak less than 3" Steam Flow 3/4 1&2B21 F328D Eacn now Oak less than 3" 3/4 1&2B21 F327D Esc 4s: Row Check less than 3" 3/4 1&2B21.F327C Esceas Row Oak less than 3" 3/4 1&2B21.F328C Escui now Oak less than 3" Post LOCA Cont Monit.1/2 IA2CM023B Solenoid Operated Globe tus than 3" Post LDCA Containment 1/2 1&2CM024A Soler oid Operated Globe less than 3" Monitoring 1/2 1&2CM027 Solenaid Operated Globe less than 3" 1/2 I A2Cn4038 Solenoid Cperated Globe less than 3" Steam Flow 3/4 1&2B21 Fl25 A Escess How Check les2 i tm 3" 3/4 1&2B21 F326A Enes: Flow Gak lese :n 3" 3/4 1&2B21 F323B Ene's now Check leu man 3" 3/4 1&2B21 F3263 Esc 4:s Mow Oak lus than 3" l
LASALLE COUNTY STATION STATION ,gLACKCUT ANALY&ls COMMONWEALTH E!11 SON COMPANY j
l Table 51. Contalansett 1solallos Valves, cost.
ITNETRATION SIZE VALVE VALVE DESCRFnON (laches) NUMBER T)TE ' Dl3fo$rnON Supp. Ch. Air Temp. I 1/4 none (cont. pen. l.38 & 39) (RTD penevation) We than 3" Supp. Pcol Water Level 3/4 l&2CM039 manual Ws than 3" 3/4 1&2CM040 manual be than 3" 3/4 1&2CM041 manual be than 3" 3/4 1&2CM042 manua' be than 3" 3/4 1&2CM043 manual less than 3" 3/4 1&2CM044 manual less ska 3" 3/4 1&2CM043 manual be than 3" 3/4 l&2CMG46 manual less than 3" Supp. Pcol Wstn Temp. l 1/4 norw (cont. pen. l.44) (RTD penepotion) b e than 3" 11/4 none (cont. pen l.46) (RTD peneustice) less than 3" Drywell Air Sampling 1 1&2CM034 Solenoid Operated Globe less than 3" 1&2CM033 Solenoid Operstad Globe less than 3" Post LOCA Cont, Mordt. 1&2CM023A Solenoid Operated Globe less than 3" Drywell Humiday 1&2CM020A Solenoid Operated Globe W: then 3" Sampling 1&2CM019A solenoid Operated Globe bs then 3" l&2CM0208 Solenoid Opersied Globe bs than 3" l&2CM0198 solenoid Operated Globe W : than 3" Posi LOCA Cont. Mon. I 1/4 1&2CM026B Solenoid Operated Globe We than 3" Suppression Pcol 11/4' 1&2E22.F341 Escens How C W s than 3*
Water level 1 1/4 1&2E22 F342 Excess now Check less than 3" Post LOCA Cont. Mon. 1/2 1&2CM021B Solenoid Operated Globe less than 3"
-gN-wet v m- *w *a&-e- w w- M--*w'w*ymm'g 's --t*-1--t-3-agum+9 ww-w*-" W-N'e--+-a w- y wwt ey-g---- g w-wweves-,i-o,-,9<
,~. LASALLE COUNTY STATION STATION BLACKOUT ANALYsls '
COMMONWEALTH EDISON COMPANY ,
l Table 5 2 3 Containment Isolation Yalves For Whict Postilon Indication and Manual Operation-Capability Should Be Provided During Station Blackout surma 110N S!ZE VALVE VALVE DESCRFi1ON (8nches) NUMBER TYFE NOTFJ RHRS Shuidon Suetion 20 1&2E12 F009 Mow Operated unu E12.F008 is in line with 20 1&2El2 F008 Mom Opunned case E12.F009 !
10 l&2ESt.F063 Motor Opermed Gus E51.F063 la in hne with Stearn to RCIC System - 10 I A2E31.F064 Motor Operaned One E$1.F064 4 l&2E$1.F008 . Motoe Operated Gus RHRS/ Containment sprey16 l&2E12.F017A.B Motor Operated Oate E12 F016 la in line with 16 1&2E12.Fol6A.B Motor Operated Gais E12.F017 Main Steam Drains 3- 1&2B21.F016 Motor Opermed Gate B21.F016 la in liras with 3 l&2B21.F019 Motor Operated One B21.F019 Combustible cas comrol 4 1&2HG001 A.B Motor Opermed om HO.001 is in line with Drywell Suction - 4 1 A 2HG002A.B Motor Operued Globe HO.002
- Reacict Cleanup 6 l&2G33.F001 Motor Opermed Gus G33.F001 is in line with 6 1&2G33.F004 Motor Opermed Gm 033.F004 LPCS Soc ir. Sup. Pool 24 l&2E21.F001 Motor Operated om RHR Suc. fr. Sup. Pool 24 1&2E12-F004 A Motor Operated Gus RHR Suc.1*. Sup. Pool 24 1&2E12 F004C Motor Opersted Gue RHR Suc. fr. Sup. Pool 24 l&2E12.F004B Motor Oswrmd Gate RilR to Sup. Pool Spray 4 1 &2E12.F027A.B Motor Operned Gue LFCS Mirumum Flow 14 1&2E21.F012 Motor Operated Globe 4 l&2E21.F0ll Motor Operated Gus RilR Minimum Flow 18 1&2E12.F024 A.B Motor Opernied Globe and Tesi Lines 18 l&2E12.F021 Motor Operated Globe
- 8 1&2E12 F064 A.B.C Motor Operated Gus 4 1&2E12.Foll A.B Motor Operated Gue Combustible Gas 6 1&2HG00$ A.B Motor Opetued Gaie HG005 is in line with Control Return 6 1&2HG006A.B Motor Operued Gene HG006 Yu:uum Breder 24 1&2PC003A.B.C.D Butterfly formally manually opeisted Note: when two or more valves are in line, manual operability need be provided for only ons of the valves t
?
L - - -
y.
APPENDIX SUPPORTfNG CALCULATIONS To LASALLE'S SUPPLEMENTAL SBO SUBMITTAL
,3.
d L
i-l l
/ sci:1204:14
CAROENT & LUNDY w ako Class 1E Battery Caoacity Analysis (Cooina with loss of AC Power Durina SBO)
(']
V IntroductiQD Six 125-Vdc Class 1E batteries and two 250-Vdc Class 1E batteries are installed at LaSalle County Nuclear Station. Six of the original batteries have been or will be replaced with larger capacity batteries during the following outages:
Unit 1 Third Refuel -
125-Vdc Division 1 (1DC07E)
Unit 2 Third Refuel -
125-VdcDivision1(2DC07E) 250-Vdc(20C01E)
Unit 1 Fourth Refuel -
125-Vdc Division 2 (10C14E) 250-Vdc(10C01E)
Unit 2 Fourth Refual -
12'5-Vdc Division 2 (2DC14E)
Tht, original 125-Vdc Division 3 batteries are not scheduled to be replaced at this time.
Battery capacity calculations were performed for the original and the replacement batteries for each of these eight batteries to determine if their g capacity is adequate for feeding SB0 loads for four hours. The calculations f addressed the following NUMARC 87-00 requirements listed in Section 7.2.2 of 87-00.
A. Use lowest electrolyte temperature anticipated under normal operating conditions.
B. If load stripping is required, stripped loads shall not be required to cope with SB0 and can be stripped comencing 30 minJtes after the initiation of SBO.
C. Load stripping must be achievable under SB0 conditions.
D. Model the SB0 load duty cycle and calculate required battery sizing using battery manufacturer's capacity curves.
E. DC loads must be powered by only the batteries during entire four-hour SBO.
Assumotions A. The 5B0 event occurs while the reactor is operating at 100% thermal power and has been at this power level for at least 100 days.
B. Imediately prior to the postulated SB0 event, the reactor and supporting systems are within normal ranges.
,T
[U Page 5-1
j CAl'.*ENT Q LUNDY
" 7EE" C. There is not a coincident design basis accident occurrence prior to/or
/]
(/ during the coping duration of four hours.
D. All non-ae power plant equipment is operable and experiences no single failure.
E. The plant is maintained in a shutdown mode during the four-hour coping period.
F. The SB0 coping duration is four hours.
G. AC power is restored at the end of four hours of SB0 conditions.
Method of Analysis ..
The SB0 battery capacity calculations for the replacement b.tteries and for the Division 3 batteries were performed on S&L's Electrical Load Monitoring System for DC Loads (ELW5-DC) computer program. This program computes composite duty cycle and battery sizing in accordance with the method of battary sizing in IEEE Standard 485. Each battery has its own file of loading data, and these loads and the battery sizing are included as hardcopy attachments to the SB0 battery capacity Calculation 4266/19030 Revision 1, titled " Capability of 125-V and 250-V Batteries to Feed Loads During Station Blackout." For the original batteries, existing (non-SBO) ELWS-DC loading files were modified for SB0 and then manually calculated for battery capacity.
c These manual calculations are also included in Calculation 4266/19030.
()
N During 5BO, the station will use SRV and either the RCIC system or the HPCS system for condensate inventory and decay heat removal. The ELMS-DC computer program was used to calculate required battery sizing during SB0 using only the RCIC system because the RCIC system places a larger burden on the batteries than that of the HPCS system as explained later in this section under "Results." RCIC operation is assumed to begin simultaneously with the initiation of SB0 and than operate (e.g., valves cycling open and closed) as modeled in S&L Calculation 3C7-0390-001, Rev. O.
The ELMS-DC load files were reviewed against EPM's Tables 3-1, 3-2, 3-3, and 3-4 from EPM's " Station Blackout Analysis Report" submitted for LiSa11e in 1989, and all de loads in these tables are included in the ELMS-DC load files.
Continuous loads are fed by the batteries for the entire 5B0 except for the leads listed in Table 5B and S&L Calculation 4266/19031 Revision 0.
The batteries were analyzed to verify that the battery capacity is sufficient to feed the safety relief valves for the additional operations required by S&L Calculation 3C7-0390-001, Rev. O.
Calculation 4266/19030 also verified that the batteries have ad3quate capacity to restore ac power from offsite power after a four-hour 5B0. This load is referred to in the calculation and on ELMS-DC as " recovery."
O Page 5-2
CARCENT O LUNDY
" " E ' "M "
p v
The design criteria for the batteries requires a minimum electrolyte temperature of 65T and this temperature was used in calculating the battery capacity of the 250-Vdc batteries. However, the temperature used in calculating battery capacity for the 125-Yde batteries was 607 because the Technical Specification allows a minimum eketrolyte temperature of 60T for these batteries (even though the minimum HVAC design limit is still 65T). An aging factor of 1.25 (recomended by IEEE Standard 485) was used for all batteries except the Division 3 batteries. Division 3 batteries were sized with a.1.11 aging factor.
Ratults The replacement Class 1E batteries and the Class 1E Division 3 batteries have adequate capacity to faed SB0 loads for a four-hour duration and to restore ac power at the conclusion of SB0 assuming that the loads are stripped as listed in Table SB. The original Class 1E batteries do not have adequate caaacity for a four-hour SBO, even with load shedding (with the exception of tne Division 3 batteries). The results of the analysis are shown on Table 5A and documented in Calculation 4266/19D30, Revision 1.
The results in Table SA are based on using the OCIC system and SRVs for condensate inventory and decay heat removal. If the HPCS system is used instead of the RCIC system, the results in Table SA are st*ll applicable as they bound (i.e., are more conservative than) results using HPCS for the following reasons:
O ^- o4 4 4 unaffected.
1 d 2 tas-vec 8 tt r4 e t < e secs i d e r-B. The 250-Vdc batteries do not feed HPCS loads and would result in less load since the 250-Vdc fed RCIC system would not be required.
C. Division 3 feeds the HPCS loads for the entire four-hour SBO.
However, if the HPCS diesel generator is operating, these loads are transferred from the Division 3 battery to the, Division 3 diesal generator (which feeds the Division 3 battery charger) within thirty minutes after a SB0 begins.
Calculations 4266/19D30 and 4266/19031 are included in this section for reference.
O Page 5-3
ENMm Jm e O O Table SA - Battery Capacity Analysis for Cocina With loss of AC Power Durina a Four-Hour Station Blackout l
ELMS-DC Margin Margin Minimum Load File After After Aging Electrolyte Shedding Battery Temperature (*F) Epouired?
Descriotion Number 4-Hr S80 Recovery Factor Unit 1, 125-Vdc Div. 1 (1DC07E)
-72.9% --
1.25 65 NA Original Battery --
1.25 60 Yes Replacement Battery IDC07E.501 8.3% 6.3%
Unit 1, 125-Vdc Div. 2 (IDC14E) 65 NA Original Battery --
-40.0% --
1.25 Replacement Battery IDC14E.501 13.9% 25.0% 1.25 60 Yes y 5.0% 5.0% 1.11 60 None Unit 1, 125-Vdc Div. 3 BATTIC.S01
?o z Unit 1, 250-Vdc (1DC01E) aid
-123.3% --
1.25 65 NA Ear Original Battery --
11.5% 1.25 65 Yes "g Replacement Battery 1DC01E.S01 11.5%
- z o
Unit 2, 125-Vdc Div. 1 (2DC07E)
- 2.5% --
1.25 65 Yes Origina; Battery --
8.4% 1.25 60 Yes Replacement Battery 2DC07E.501 10.4%
Unit 2, 125-Vdc Div. 2 (2DC14E) 65 NA
-24.3% --
1.25 Original Battery --
32.8% 1.25 60 Yes.
Replacement Battery 20C14E.501 33.1%
3.9% 1.11 60 None Unit 2, 125-Vdc Div. 3 BATT2C.501 3.7%
Unit 2, 250-Vdc (2DC01E) 1.25 65 NA Original Battery --
-123.3% --
11.5% 1.25 65 Yes Replacement Battery 2DC01E.501 11.5%
Page 5-4
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Notes to Tabit _ W
- 1. Battery margins are band on using RCIC ard SRV operation for condensate inventory and decay heat removal. Batteries will have the same or greater margin if HPCS is used instead of RCIC.
- 2. Divis on 3 batteries are not scheduled for replacement.
- 3. See Table SB for loads involved in load shedding.
- 4. "NA" is listed und9r " Load Shedding Required?" for those batteries which have inadequate margin. These batteries were analyzed with load shedding but still lacked the capacity to feed the expected SB0 loading for a four-hour 580.
- 5. "Nargin After Recovery" was not determined for the original batteries.
- 6. The difference in the electrolyte temperature for original and replacement batteries is because the minimum electrolyte temperature required at LaSallo was understood as 65 F when the original batteries were analyzed (Rev. O of Calculation 4266/19D30) but was confirmed as 60 F for the 125-Vdc batteries when the replacement batteries were reanalyzed in Revision 1 of Calculation 4266/19D30,
- 7. Margins with negative entrics represent inadequate battery capacity g (battery is undersized for 580 as modeled).
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U b Table SB - Load Sheddina for Station Blackout - ,
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Battery Load Location of Feeder Breaker - Breaker Number Reactor B1dg. Ltg. Cab. 140 125-Vdc Dist. Pni. 111Y (1DC11E), Cow artment 4A-11 Unit 1, 125-Vdc 125-Vdc Dist. Pnl.111Y (IDC11E), Cowartment 4A-14 Div. 1 (IDC07E) LFMG Aux. Relay Panel Turbine B1dg. Ltg. Cab. 141 125-Yde Dist. Pnl. 111X (IDC10E), Cowartment 1A-12 125-Vdc Dist. Pnl. 111X (IDC10E), Cow artment IA-8 Radwaste Cont. Panel OPLO1J 125-Vdc Dist. Pni. 111X (IDC10E), Cow artment IA-4 Radwaste Annunciator OPL60J 125-Vdc Dist. Pnl. 111X (1DC10E), Com artment 1A-2 i
FW Pump Turbine 1A Control Reactor Bldg. Ltg. Cab. 14? 125-Vdc Dist. Pn1. 112Y (1DC13E), Compartment 4A-13 Unit 1, 125-Vdc 125-Vdc Dist. Pnl. 112Y (1DC13E), Com artment 4A-9 m LFMG Aux. Relay Panel Div. 2 (IDC14E)
EHC Cabinet 125-Vdc Dist. Pn1. 112X (1DC12E), Compartment IA-3 "$o 125-Vdc Dist. Pnl. 112X (1DC12E), Compartment IA-2 FW Control Panel 125-Vdc Dist. Pnl. 112X (1DC12E), Compartment IA-1 ao E FW Pump Turbine IB Conteel Ai-1 125-Vdc Dist. Pni. 112X (IDC12E), Com artment 1A-4 Hyd. & Stator Cooling Cabinet 125-Vdc Dist. Pn1. 112X (IDC12E), Cowartment IA-19 Cap
' Turbine 81dg. Ltg. Cab. 143 "r l -- 5E Unit 1, 125-Vdc None 3
Div. 3 Emergency Bearing 011 Pump 250-Vdc NCC 121X (IDC05E) - 3A Unit 1, 250-Vdc 250-Vdc MCC 121X (IDC05E) - 3C l
I (1DC01E)
Emergency Seal Oil Pug l
Reactor Bldg. Ltg. Cab. 240 125-Vdc Dist. Pnl. 211Y (2DC11E), Comp etment 4A-11 l Unit 2, 125-Vdc 125-Vdc Dist. Pnl. 211Y (2DC11E), Compartment 4A-14 Div. 1 (20C07E) LFMG Aux. Relay Panel Turbine B1dg. Ltg. Cab. 241 125-Yde Dist. Pnl. 211X (2DC10E), Compartment 1A-12 125-Vdc Dist. Pnl. 211X (2DC10E), Com artment 1A-2 FW Pump Turbine 2A Control Page 5-6
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9 O O Table 58 (Cont.)
Batterv Load Location of Feeder Breaker - Breaker Number _
Reactor Bldg. Ltg. Cab. 242 125-Vdc Dist. Pn1. 212Y (2DC13E), Compartment 4A-13 Unit 2, 125-Vdc 125-Vdc Dist. Pnl. 212Y (2DC13E), Compartment 4A-9 q Div. 2 (2DC14E) LfMG Aux. Relay Panel EHC Ccbinet 125-Vdc Dist. Pnl. 212X (2DC12E), Compartment IA-3 i FW Control Panel 125-Vdc Dist. Pnl. 212X (2DC12E), Compartment 1A-2 FW Pump Turbine 28-Control 125-Vdc Dist. Pal. 212X (2LC12E), Conpartment IA--I Hyd. & Stator Cooling Cabinet 125-Vdc Dist. Pnl. 212X (2DC12E), Compartment 1A-4 Turbine Bldg. Ltg. Cab. 243 125-Vdc Dist. Pnl. 212X (2DC12E), Compartment 1A-19 Unit 2, 125-Vdc None g Div. 3 250-Vdc MCC 221X (2DC05E) - 3A Eb Unit 2, 250-Vdc Emergency Bearing Oil Pump Emergency Seal Oil Pump 250-Vdc NCC 221X (2DC05E) - 3C ;oE (2DC01E) 3z*
50't-All loads are shed within 30 minutes after SB0 begins, with the exception of the 5E NOTE: o 250-Vdc loads which are shed within 180 minutes after 5B0 begins.
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4 l CARCENT Q LUNDY
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) ELMS DC Prooram and Validation Proaram used in bizina Batteries for Station Blackout Overview The capacity of the LaSalle County Station batteries was assessed for Station Blackout.(SBO) using Sargent & Lundy's (S&L) Electrical Load Monitoring System for DC Loads (ELMS DC) computer program. ELMS-DC calculates the composite duty cycle and then calculates the required battery size in accordance with IEEE Standard 4B5. For LaSalle County Station, ELMS DC calculates the battery size based on the following battery performance data from the manuf acturer:
. Original 12S Vdc Division 1 and 2 Batteries - Gould Type FPS (to be replaced during third and fourth refueling outages)
. Replacement 125 Vdc Division 1 and 2 Batteries - GNB Type NCX-17
- Original 250 Vdc batteries - Gould Type FPS (to be replaced during the third and fourth refueling outages)
- Replacement 250 Vdc Batteries - GNB Type NCX-27
. 125 Vdc Division 3 Batteries - C&D Type DCU/DU RMS-DC Prooram The ELMS DC computer program used for LaSalle County's SB0 analysis consisted (s') of two separate versions of ELMS-DC as follows:
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ELMS-DC Battery Proaram No. Version 125 Vdc Div. 1 & 2 03.7.010 1.2 1.2 Original Batteries ,
125 Vdc Div. 1 & 2 03.7.010-2.0 2.0 Replacement Batteries 250 Vdc Original Batteries 03.7,010-1.2 1.2 25C Vdc Replacement 03.7,010-2.0 2.0 Batteries 125 Vdc Div. 3 Batteries 03.7,010-1.2 1.2 ELMS-DC Version 2.0 is an enhancement of Version 1.2. The validation calculation of Version 2.0 (see heading " Validation Calculation") included a comparison of results from both versions of ELMS-DC and concluded that the calculated required battery sizes are virtually identical. Version 1.2 calculates overall duty cycle and battery size required for the duty cycle, and the manufacturer's battery performance curves are " built into" Version n 1.2. Version 2.0 also performs these calculations but the manuf acturer's
- ] battery performance curves are not included ir. Version 2.0. The performance
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r-CAFCENY Q LUNDY ENClNEEQO CMICAO3 V
"') curves are placed in data files created by S&L computer program BATDAT Version 1.00 (Battery Data File Creation Program for ELMS-DC) and these files are read by Version 2.0. This eliminates the need to revise ELMS-DC each time battery characteristics are add?d or revised.
Versions 1.2 and 2.0 of ELMS-DC both calculate battery sizing in accordance with IEEE Standard 485, first by calculating the duty cycle and secondly by calculating the required battery size (i.e., number of positive plates) for a particular manufacturer and tell type. In the duty cycle calculation, the largest loading during any second in each minute is taken as the load throughout that minute. The battery sizing calculation determines the required battery size, taking into account the minimum electrolyte temperature, cell type, nominal and minimum voltage, ntaber of cells and positive plates, design margin, and aging factor. .,
BATDAT Version 1.0 is identifitd as S&L Program Number BAT 0717710R.
Loading data for ELMS-DC was originally tabulated in S&L calculations 4266/19019 and 4266/19020. The-load data was entered onto data files (one for each battery) for ELMS-DC calculations. Changes to the load data are not made to calculations 4;66/19D19 and 4266/19D20 but are made instead to the load data files. Separate files are maintained for installed (" existing") and future (" modified") loading conditions.
- Validation Versions 1.2 and 2.0 of ELMS-DC and BATDAT 1.0 are validated per S&L's QA Program (which complies with 10 CFR 50, Appendix B) under these calculation
-numbers:
Version 1.2 - S&L Calc. . No. ELMS-2, Rev. 2 Version 2.0 - S&L Calc. No. ELMSDC-2.0, Rev. O BATDAT 1.0 - S&L Calc No. BATDAT-1.0, Rev. O Calculation ELMS-2-confirmed that ELMS-DC correctly calculates overall duty cycle and required battery site and the validity of the battery performance data. Calculation ELMSDC-2.0 performs the same calculations as ELMS-2 and compares the results. In addition, calculation ELMSDC-2.0 validates that BATDAT-files are read and interpreted correctly, that data files prepared with Version 1.2 can be read correctly, and validates the enhancements included in Version 2.0 which were not in Version 1.2. The data files in BATDAT were created for LaSalle County's replacement batteries (GNB NCX-17 and NCX-27) in S&L Calc. 4266/19D32, Revision 1.
ELHS-DC also complies with S&L Procedure B-14 for notification to program users and license holders of potential defects and/or noncompliance as per 10 CFR 21.
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