ML19253C279
| ML19253C279 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/12/1979 |
| From: | UNITED ENGINEERS & CONSTRUCTORS, INC. |
| To: | |
| Shared Package | |
| ML19253C267 | List: |
| References | |
| NUDOCS 7911300426 | |
| Download: ML19253C279 (75) | |
Text
{{#Wiki_filter:' UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET N0. 50-324 LICENSE NO. DPR-62 C AROL INA P01(ER & L IGHT COMP ANY RALEIGH, NORTH CAROLINA es Ks N LICENSING SUPPORT INFORMATION FOR PROPOSED CHANGES TO TECHNICAL SPECIFICATION PRESSURE SWITCH TO ANALOG REPLACEMENT BRUNSWICK STEAM ELECTRIC PLANT UNIT NO. 2 cn g cn cn g cc Tr J o o A\ o Ju.0.. o OCTOBER 12, 1979 7011300 /c5k [3 144p248
UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-324 LICENSE NO. DPR-62 CAROLINA POWER & LIGHT COMPANY RALEIGH, NORTH CAROLINA
.ICENSING SUPPORT INFORMATION FOR PROPOSED CHANGES TO TECHNICAL SPECIFICATION PRESSURE SWITCH TO ANALOG REPLACEMENT BRUNSWICK STEAM ELECTRIC PLANT UNIT NO. 2 PREPARED BY:
UNITED ENGINEERS & CONSTRUCTORS INC. PHILADELPHIA, PA. OCTOBER 12, 1979 144V ?49
14 4'r .?50 TABLE OF CONTENTS SECTION DESCRIPTION I GENERAL
- 1. Background
- 2. System Design
- 3. System Components
- 4. Equipment Qualifications
- 5. Interconnections (See Figure 5-1)
- 6. Surveillance Test Intervals
- 7. Control Wiring Diagrams - Typical (Before/Af te r)
II CHART OF EXISTING DEVICES REPLACED WITH TRANSMITTERS AND TRIP UNITS III TRIP CALIBRATION CABINETS AND INSTRUMENT RACKS
- 1. Location, General Arrangements of ECCS and RPS Cabinets in Control Room
- 2. Location of Instrument Racks in Reactor Building IV PRESSURE AND LEVEL TRANSMITTERS DATA SHEETS V MASTER AND SLAVE TRIP CALIBRATION UNITS DATA SHEETS VI TECHNICAL SPECIFICATIONS (REVISED) 14 4'r' 25 i
144Y 252 144tP 253
- 1. BACKCROUND 1.1 For each device (a) being replaced, this modification consists of removing one existing device and replacing it with one or two channels (b) to perform the same function or functions. Replacing certain devices with two channels- (See Section II for tabulation and Section I, 5.3 for discussion) provides additional redundancy and system separation - but does not change the logic or protective functions of the syst ms.
(a) Device - pressure or differential pressure switch (b) Channel - a pressure or differential pressure transmitter and one or more trip units , 1.2 This document references, and the modifications meet, the requirements outlined in General Electric Licensing Topical Report NEDO 21617-A as applicabic. (NEDO 21617-A was accepted for reference in license applications by NRC to G.E. letter dated June 27, 1978.) This document also covers the following areas: 1.2.1 Differences and justifications for differences between this specific plant system and the systems covered by NEDO 21617-A. 1.2.2 Interface information specific to this installation. 14W 254
1444 255'
- 2. SYSTEM DESIGN The system design parameters are essentially the same as the NhD0 report with the following exceptions:
2.1 Power Source for the RPS Channels A1, B1, A2 and B2 The change consists of obtaining power from the 125 volts D-C batteries similar to the ECCS systems. The change from 115 volt A-C RPS distribution power to 125 volt D-C battery power was based on the negative effect that an A.C. voltage decay would have on the RPS trip units in the event of a BOP power loss and the subsequent trans fer to the diesel generators. Power source availability is assured through power supply redundancy for both the ECCS and RPS systems, (see Figure 5-1 for redundant power supply layout for ECCS and RPS systems). 2.2 Effects of Addition of Trip Calibration Cabinets on DC Load Study 2.2.1 For Unit No. 2 the Trip Calibration Cabinets have been connected to Distribution Panels 4A and 12A which are fed from Battery 2A-1 and to Distribution Panels 4B and 12B which are fed from Battery 2B-2. Review of the expected loads of the Trip Calibration Cabinets by calculation and by observation of ammeters during functional test indicates the following loads for the equipment: 2.2.1.1 ECCS cabinet power supply - 6 amps 2.2.1.2 ECCS cabinet standby power supply - 2 amps 2.2.1.3 RPS cabinet power supply - 4 amps 2.2.1.4 RPS cabinet standby power supply - 2 amps 2.2.2 As there are four (4) power supplies on a battery, the total load would be approximately 14 amps per hour or 112 amp-hours over an eight hour time period. Addition of this load to the loads calculated in the D.C. Load Study of May 9, 1975 causes the following changes: 2.2.2.1 Time to Discharge to 1.75 volt / cell for Normal Operation for Battery 2A-1 is reduced from 38 hours to 27 hours. 2.2.2.2 Time to Discharge to 1.75 volt / cell for Normal Operation for Battery 2B-2 is reduced from 24 hours to 19 hours. 2.2.2.3 Time to Discharge to 1.75 volt / cell for Normal Ope ation plus UPS and 2A, 2B Lighting Inverter is reduced from 5.5 hours to approximately 5 hours. 144'r 256
- 2. SYSTEM DESIGN (cont'd) 2.2 Ef fects of Addition of Trip Calibration Cabinets on DC Load Study (cont'd) 2.2.2.4 Design Basis Accident (DBA) with no DC Failures would require a total of 809 amp-hours on Battery 2A-1 and 687.64 amp-hours on Battery 2B-2. This is below the 960 amp-hours (807. of 1200 amp-hours) rated end of life capacity for batteries.
2.2.2.5 DBA with 2A Battery failure would require a total of 856.35 amp-hours on Battery 2B-2. This is below the 960 amp-hours rated end of life capacity for the battery. 2.2.2.6 DBA with 2B Battery failure would require a total of 1011.92 amp-hours on Battery 2A-1. This is above the 960 amp-hours rated end of life for battery; however, the 1011.92 amp-hours will be reduced to within rating if non-essential loads (for example: Reactor Building Emergency Lighting) are disconnected. NOTE: The Reactor Building Emergency Lighting (DC) was considered in the DC Load Study as a constant lond during the eight hours that the supply to the battery charger would be considered out of service. A recent review has determined the following:
- a. The emergency lighting (DC) is controlled by a contactor which is energized by the Reactor Building Standby Lighting system (AC) such that if the Standby Lighting system is in operation the emergency lighting (DC) will be de-energized,
- b. The Standby Lighting system (AC) is fed from the Div. II emergency bus which is fed f rom either the off site power system or a diesel generator.
- c. It is highly unlikely that a Div. II battery would be out of service along with the loss of a Div. II emergency bus.
Therefore, under the conditions hypothesized, the Reactor Building Emergency Lighting (DC) would not be required and is automatically disconnected without creating an unsafe condition. 2.2.2.7 DBA with 1A Battery failure would require a total of 814.90 amp-hours on Battery 2A-1 and 687.64 amp-hours on Battery 2B-2. This is below the 960 amp-hours rated end of life capacity for the batteries. 2.2.2.8 DBA with IB Battery failure would require a total of 809 amp-hours on Battery 2A-1 and 789.86 amp-hours on Battery 2B-2. This is below the 960 amp-hours rated end of life capacity for the batteries. 1449r 157
144Y 258
- 3. SYSTEM COMPONENTS The system components are the same as outlined in NEDO 21617-A report except for the power supplies and transmitters.
3.1 This exception consists of a redundant power supply system using two Lambda LXS-EE-24R regulated power supplies with overvoltage protection and diode isolation instead of an Elma ferroresonant power supply. The Lambde redundant power supply system was selected to assure verv high availability and good output voltage stability against input voltage, input frequency, load, and ambient temperature variations. 3.1.1 Subjective comparisons of the failure modes of the two power supply systems - redundant series regulated with overvoltage protection versus ferroresonant (Lambda versus Elma) - indicate that the " Conclusions of System Availability Analysis" (NEDO 21617-A, paragraph 3.4.4) are applicable when the redundant Lambda power supply system is used. 3.1.2 The Lambda overvoltage protectors are specified to operate in a voltage range of 27.3 i 0.8 volts. When actuated the individual Lambda power supp'ly overvoltage protector will short circuit its current limited power supply output and drive and hold the output voltage to near zero initiating an alarm. Note: The maximum specified operating voltage of the over-voltage protector, 28.1 volts, exceeds the maximum input voltage of the trip units (28 volts) and the maximum continuous voltage of the trip relays (27 volts). The individus1 power supply isolating diode forward voltage drop (approximately 0.6 volts) reduces the maximum power supply ;fstem bus voltage (af ter the isolating diodes) to an acceptable value. 3.1.3 Redundant Lambda power supplies, each with a MTBF (mean time between failures) rate of 100,000 hours; annunciated failures; and early replacement of failed supplies with spare supplies provide very high power supply system availability. 3.1.4 Periodic tests of the power supplies can be conducted to detect non-annunciated failures and further improve power system availability. Suggested test and test intervals are listed: TEST TEST INTERVAL Power Supply Output Voltage: Before Diode M (once per 31 days) Af ter Diode M ,once per 31-days) Overvoltage Protector R (once per 18 months) 1444 259
- 3. SYSTEM COMPONENTS (cont'd) 3.1.5 The redundant Lambda power supply system discussed above is to be compared to the Elma power supply referenced in NEDO 21617-A, paragraphs 1.3.5, 2.3.1.1, and 3.1.1.
3.2 Transmitters This installation utilizes Rosemount Model 1152 transm* tters instead of the Rosemount Model 1151 transmitters referenced in NEDO 21617-A. 3.2.1 The Model 1152 has been qualified and exceeds the requirements for this installation as noted in Section I, 4 Equipment Qualifications. 3.2.2 Rosemount transmitter Models 1151 and 1152 response times are the same. This makes the Response Tine conclusions (NEDO 21617-A, paragraph 3.3.2) applicable to this installation. 1449' 26d0
a 1 4 4't ?61
- 4. EQUIPMENT QUALIFICATIONS 4.1 Qualification Summary All Class it, equipment was specified to meet, and does mee t or exceed, applicable environnental service conditions. Environmental qualification documentation is on file and is av,ailable at the plant.
An " Environmental Interface Comparison Chart" (Figure 4-1 this section) compares the NEDO 21617-A equipment maximum environments to the normal and accident environments for this installation. 4.2 Service Environment The environmental service conditions were defined in Design Report No. 12 and have been summarized in the " Service Environment Chart - Normal and Accident Conditions - Units No. I and No. 2" FSAR FIGURE NO. M7.9-1. A copy of the chart is included in this section of the report. The environmental parameters applied to the pressure switch to analog replacement sa fety sys tem t ransmit ters are for " Reactor Building - Other" and " Turbine Building" as applicable. " Reactor Building,
-17' Level" parameters are applicable to two non-safety transmitters.
The environmental parameters applied to the trip calibration system components; trip units, trip relays, inverters, power supplies and cabinets are for the " Control Building, Control Room". 4.3 Qualification Documentation Environmental qualification documentation is ava Llable at the plant for all equipment except inverters and trip relays which are covered b y NE DO 21617- A . (Trip unit documentation supplements coverage by NEDO 21617-A. ) 4.3.1 Trio Unit Documentation I.ist F.P. NO. (BP0/252-55) REPORT NO. DE SCR IPTION 9527-70271 127531 Qualification tes t report for trip / (2 volumes) calibration system - Rosemount Model 510DU 9527-/0274 6453C Qualification test p rocedu re for trip / calibration sys tem - Rosemount Model 510DU 9527-70275 12777D Qualified life test report for trip / calibration system - Rosemount Model 510DU b-
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4.3.1 Trip lini t Documentation List (cont'd) F.P. NO. _(BP0/252-55) REPORT No. DESCRIPTION 9527-70295 3768A Qualification test summary for the trip /calibra, tion system - Rosemount Model 510DU 9527-70296 27723 Qualified life test procedure for the trip / calibration system - Rosemount Model 510DU 9527-70254 510DUA010 Product specification for the trip / calibration system - Rosemount Model 510DU 4.3.2 Transmi t te r Documenta t ion Lis t F.P. NO. (BP0/252-51) REPORT No. DESCRIPTION 9527-70298 67710A Environmental qualification test report for 1151 and 1152 pressure t ransmit te rs 9527-70300 117415 Qualification tests summary for \ 1152 pressure transmitters 9527-70301 127516 Seismic simulation test re port for t131 and 1152 pressure t ransmi tte rs 9527-70299 10763 Radiation qualification test report for 1152 pressure transmitters 9527-LL-7044 UE6C New Local Transmit te r Mountings - Sheet 174 In te rnal Seismic Evaluation (:elsmic Memo: Analyzed M. M. Tahara and to Approved) B. J. Huselton Nov. 17, 1978 UE&C New Transmitters Mounted on Existing In te rnal G.E. Design Racks Memo: T. C. Chang to E. R. Forman (Seismic Analyzed and Approvel) kk( .
4.3.3 Power Supply Docum?ntatiot; List F.P. NO. REPOR? NO. DESCRIPTION 9527-70303 DTB04R75 Dayton T. Brown Report tested dated per MIL-STD-810B " Environmental 22 March 1975 Test Metho,ds" (by similarity to tested equipment) (Lambda LXS-EE-24R is fungus inert Model LXS-EE-24) N.A. N.A. Tested to MIL-I-6181D 25 Nov. 1959
" Interference Control la quirements, Aircraft Equirr nt" 4.3.4 Trip Calibration Cabinets (Includes Inverters, Power Supplies Trip Units, Trip Relays and Cabinets)
F.P. NO. (BP0/252-56) REPORT NO. DE SCRI PTION 9527-70292 14660 Seismic vibration Testing of one dated RPS Trip Calibration Cabinet May 7, 1979 9527-70293 14660-1 Seismic Vibration Testing of one dated RPS Trip Calibration Cabinet May 7, 1979 4.4 Electromagnetic Interference (EMI) All system components are the same as referenced in NEDO 21617-A (equivalent transmitters) except for the 24 volt D-C power supplies. 4.4.1 The susceptibility of this installation to EMI ef fects is evaluated to be equal to or less than the susceptibility of the NEDO 21617-A re f erence system. 4.4.2 The Lambda " del LXS-EE-24R power supply meets the requirements of MIL-I-6181D, 25 Nov. 1959, "Inte rfe rence Control Requi remen ts , Ai rc ra f t Equipment". 4.4.3 The NEDO 21617-A ins trumentation susceptibility tests were based on worst-case transient and radio frequency tests in and around nucita r con trol ror,n s (see NEDO paragraph 4.4) for 24 volt D-C power supplies located in the reactor building (125 volt A-C lines exposed for EMI pickup), and for inter; snel 24 volt D.C. bilS t% . 4.4.4 This inst.,llation utilizes inverters and 24 volt D-C power supplies located in the same enSinets and in the control room environment for the FCCS and RI'S svstems - reducing the exposure to EMI pickup in the A-C power lines. The 24 volt D-C b'uses are not interpanel - again educing the exposure to EMI pickup.
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- 5. INTERCONNECTIONS 5.1 Refer to chart shown in Section II for a complete list of pressure and level switches which were replaced with analog transmitter devices and to Figure 5-1 for conduit and cable routing.
5.2 The original plant separation criteria has been followed in routing of new cables and the location of n-u equipment. All transmitters, with the exception of ten (10) ' ocal transmitters which are mounted on new steel supports, are mounted on existing instrument racks in the same approximate location as the devices which they replaced. (See Section I, 4 for seismic qualification of supports.) 5.3 Separation of ECCS and RPS Circuits Eight (8) pressure switches (B21-LS-N017A, B, C, D; B21-LS-N024A, B; and B21-LS-N025A, B) were utilized for both ECCS and RPS circuitry. These pressure switches have been replaced by sixteen (16) t ra ns - mitters. Eight (8) of the transmitters (B21-LT-N017A-2, B-2, C-2, D-2; B21-LT-N024A-2, B-2; and B21-LT-N025A-2, B-2) are utilized in the ECCS system logic and eight (8) of the t ransmi t te rs (B21-LT-N017A-1, B-1, C-1, D-1; B21-LT-N024 A-1, B-1; and B21-LT-N025 A-1, B-1) are utilized in the RPS system logic. This increases the separation between systems and assures that a failure of .the above transmitters or its respective trip calibration unit in the ECCS system does not af fect the RPS system and vice-versa. 144t ?69
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- 6. SURVE TT.TANCE TEST INTERVAT.S 6.1 This modification requires changes to the surveillance requirements as noted below and in the revised Technical Specification pages in Section VI.
6.2 The recommended surveillance inte rvals listed, either simultaneous or staggered, are based on the following: (NEDO 21617-A paragraphs are referenced) 6.2.1 NEDO 3.4. 2, "Mean-Time-Be tween-Failures (MTBF) Analysis", the MTBF conservatism indicated in paragraph 3.4.2, and on the low trip unit stress level in the control room environment of this installation. 6.2.2 NEDO 3.4.4, " Conclusion of System Availability Analysis". 6.3 Recommended surveillance intervals for all instrument channels which are being changed - and are niso covered by Technical Specifications: TRANSMITTER TRIP UNIT Channel Check N. A.
- D Channel Functional Test N. A.
- M Channel Calibration R ** M N. A. - not applicable R - at least once per 18 months (550 days)
D - at least once per 24 hours M - at least once per 31 days
- the transmitter channel is satisfied by the trip unit channel check. A separate trans-mitter check is not required.
** transmitters are exempted f rom the monthly channel calibration.
144'r 172
144W 273
- 7. CONTROL WIRING DIACRAM3 - TYPICAL (BEFORE/AFTER)
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C AROLIN A POWER & LIGHT COMPANY CAROLIN A POWER S LIGHT COMPANY emusswica sit au rLacimic etaNr B RU N SWICK STEAM ELECTRIC PLANT TRIP CALIBRATION CABINET *A26' UNIT NO. 2 RPS CHANNEL Al C B -X U-65 TRIP CALIBRATION CABINET CONTROL WIRING DI AG R AM RPS CHANNEL "Al" CB-XU-65 UNIT 2 PARTIAL CONTROL WIRING DIAGRAM unitvo rsciseras a coustnectons twe. TY'PICAL
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CAROLINA POWER & LIGHT COMPANY m., _7 . . . . . . . vt. L; u .\ N o DRUNSWICK STEAM E L E C T Ft ! C PLANT l RE. SED I UNIT NO. 2 N:C V ORC E UE&Ci CONTROL WLRING DIAGRAM 3j _.; g 'yb a w,- M! .'. n E E N'5 E RS AFTER CHANGES f.ML. 4 ;.1 P wt. s.=c aa'"** FOR i,* i .._r. LOOPS B21-PTM-N006A,' 7A, 8A AND 9A
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1447 ?78 CAROLINA PO'a*ER c. LIGHT COMPANY 3RUNSWICK STEAM ELECTRIC PLANT PRESSURE SWITCH TO ANALOG CHANGEOUT LICENSING TECHNICAL REPORT INFORMATION NOTES:
- 1. For more detailed information on transmitters (*) see Specification No. 9527-01-252-51, page XXA as noted and on trip calibration units (#)
see Specification No. 9527-01-252-55, page XXA as noted.
- 2. Symbol shown thus (**) in column calls attention to (M) = master trip unit and (S) = slave trip unit, both of which are located in card files at the trip calibration cabinets.
- 3. Under the column heading for schematic data the complete drawing number and cabinet designation consists of the heading and the data listed below the column, e.g.
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Drawing No. Cabinet No. 9527-3933, Sh. 2 CB-XU-65 9527-3934, Sh. 2 CB-XU-66 9527-3935, Sh. 2 CB-XU-67 etc. etc. 4 Instrument Number Corelation with Technical Speci. '. cations The change from mechanical sensors to analog transmitters requires a re-definition of instrument numbers. The following examples will meet the requirements between __. transmitters and master / slave trip units: 42 B21-PT-N023A, pressure transmitter located at instrument rack 4E B21-PTM-N023A-1, mas te r trip unit, located in card file in trip caldbration cabinet B21-PTS-N023A-2, slave trip unit, located in card file in trip calibration cabinet i sa B21-LT-N017A-1, level transmitter, located at instrument rack
J B21-LT-N017A-2, level transmitter, located at instrument rack 'd3 B21-LTM-N017 A-1, mas te r trip unit, located in card file in trip calibretion cabinet B21-LTM-N017A-2, mas te r t rip unit, located in card file in trip caliarati7n cabinet Unit No. 2 ATTACHMENT "B" Date: August 15, 1979 Sheet 1 of 5
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L44't 519 SECTION V TRIP CALIBRATION SYSTEM - TAC NUMBER INDEX MIT NO. TAG NO. PAGE NO. UNIT NO. TAG NO. PAGE NO. 2 B21-N006A-1 26 B 2 B21-N024B-1 30 B 2 B21-N006A-2 26 B 2 B21-N024B-2 24 B 2 B21-N006B-1 30 B 2 B21-N025A-1 28 B 2 B21-N006C-1 28 B 2 B21-N025A-2 21 B B21-N025B-1 2 B21-N006D-1 32 B 2 32 B [ 2 B21-N007A-1 26 B 2 B21-N025B-2 24 B 2 B21-N007B-1 30 B 2 B21-NO31A-1 20 B 2 B21-N007B-2 30 B 2 B21-NO31A-2 20 B 2 B21-N007C-1 28 B 2 B21-N031A-3 20 B 2 B21-N007D-1 32 B 2 B21-N031A-4 20 B 2 B21-N008A-1 26 B 2 B21-N031B-1 23 B 2 B21-N008B-1 30 B 2 B21-N031B-2 23 B 2 B21-N008C-1 28 B 2 B21-NO31B-3 23B 2 B21-N008C-2 28 B 2 B21-N031B-4 23 B 2 B21-N008D-1 32 B 2 B21-N031C-1 20 B 2 B21-N009A-1 26 B 2 B21-N031C-2 20 B 2 B21-N009B-1 30 B 2 B21-NO310-3 20 B 2 B21-N009C-1 28 B 2 B21-N031C-4 20 B
' B21-N009D-1 32 B 2 B21-NO310-1 23 B 2 B21-N009D-2 32 B 2 B21-N031D-2 23 B 2 B21-N015A-1 26 B 2 B21-N0310-3 23 B 2 B21-N015B-1 30 B 2 B21-N031D-4 23 B 2 B21-N015C-1 28 B 2 B21-N036-1 22 B 2 B21-N0150-1 32 B 2 B21-NO37-1 25 B
, , 2 B21-N017A-1 26 B 2 B21-N042A-1 22 B 2 B21-N017A-2 21 B 2 B21-N042B-1 25 B 2 B21-N017B-1 30 B 2 B21-N056A-1 26 3 2 B21-N017B-2 21 B 2 B21-N056B-1 30B 2 B21-N017C-1 28 B 2 B21-N056C-1 28B 2 B21-N017C-2 24 B 2 B21-N0560-1 32B 2 B21-N017D-1 3? B 2 B21-4033 20 B 2 B21-N017D-2 24 B 2 B21-4036 23 B 2 B21-N021A-1 20 B 2 B21-4039 26B 2 B21-N021A-2 20 B 2 B21-4040-1 (Spare) 27 B 2 B21-N021B-1 23 B 2 B21-4040-2 (Spare) 27B 2 B21-N021B-2 23 B 2 B21-4041 28 B 2 B21-N021C-1 20 B 2 B21-4042-1 (Spare) 29B 2 B21-N021C-2 20 B 2 B21-4042-2 (Spare) 29 B 2 B21-N0210-1 23 B 2 B21-4043 30B 2 B21-N021u-2 23B 2 B21-4044-1 (Spare) 31B 2 B21-N023A-1 26 B 2 B21-4044-2 (Spare) 31B 2 B21-N023A-2 26 B 2 B21-4045 32B 2 321-N023B-1 30 B 2 B21-4046-1 (Spare) 33B 2 B21-N023B-2 30 B 2 B21-4046-2 (Spare) 33B 2 B21-N023C-1 28 B 2 B21-N023C-2 28 B 2 B21-N0230-1 32 B 2 B21-N0230-2 32 B 2 B21-N024A-1 26 B 2 B21-N024A-2 21 B 2 B21-4053 19B Specification No. 9527-01-252-55 Page 17 8
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SECTION V TRIP CALIBRATION SYSTEM - TAG NUMBER INDEX (Cont'd) UNIT NO. TAG NO. PAGE NO. 2 C72-N002A-1 26 B 2 C72-N002B-1 30 B 2 C72-N002C-1 28 B 2 C72-N0020-1 32 B 2 E11-N010A-1 22 B 2 E11-N010B-1 25 B 2 Ell-N010C-1 22 B 2 E11-N010D-1 25 B
, 2 E11-N011A-1 21 B
- 2 E11-N011A-2 21 B l 2 E11-N011B-1 24 B 2 Ell-N011B-2 24 B
- 2 E11-N0 llc-1 21 B 2 E11-N011C-2 21 B 2 E11-N011D-1 24 B 2 E11-N011D-2 24 B 2 E11-N019A-1 22 B gg} 2 E11-N019B-1 25 B 2 E11-N019C-1 22 B 2 E11-N019D-1 25 B 2 E11-4034-1 (Spare) 22 B 2 E11-4034-2 (Spare) 22 B 2 E11-4035-1 (Spare) 22 3 ,
2 E11-4035-2 (Spare) 22 8 2 E11-4037-1 (Spare) 25 B i 2 E11-4037-2 (Spare) 25 B 2 E11-4038-1 (Spare) 25 B 2 Ell-4038-2 (Spare) 25 B 2 E41-N004-1 21B 2 E41-N004-2 21 B 2 E41-N005-1 24 B 2 E41-N005-2 24 B 2 E41-N014-1 22 B 2 E51-N017-1 21B 2 E51-N017-2 21B 2 E51-N018-1 24B } (klf h 2, } 2 E51-N018-2 24B 2 E51-N010-1 25B Specification No. 9527-01-252-55 Page 18 B
SECTION V TRIP CALIBRATICN SYSTEM - TAC NUMBER INDEX (Cont'd) NOTES:
- 1. The tag number index, as shown on Specification No. 9527-01-252-55, Sheet Nos. 17B and 18B, is recorded on the following data sheets and on the plant modification drawings, whereas the instrument tag numbers noted on the technical specification sheets reflects the distinction between master and slave trip units in accordance with the following examples:
DATA SHEETS & DRAWINGS TECHNICAL TRANSMITTERS MASTER /3 LAVE TRIP UNITS SPECIFICATIONS (Ex.) B21-PT-N023A B21-N023A-1 (Master) B21-PTM-N023A-1 B21-N023A-2 (Slave) B21-PTS-N023A-2 (Ex.) B21-LT-N017A-1 B21-N017A-1 (Master) B21-LTM-N017A-1 B21-LT-N017A-2 B21-N017A-2 (Master) B21-LTM-N017A-2 etc.
- 2. The sumbol (c) shown in trip setpoint column on the following specification data sheets reflect nominal trip setpoints. Actual trip setpoints will be determined and set in the Field to be consistent with the technical specifications.
144tt 522 Specification No. 9527-01-252-55 Page 18 B1
SECTION VI SPECIFICATION SHEET TRIP CALIBRATION SYSTEM Rosemount Model 510DU Trip Calibration System consisting of one hundred seventy-two (172) Master Trip Units, eighty (80) Slave Trip Units, twelve (12) Calibration Units and twenty-eight (28) unwired card files complete with accessories as listed below. Refer to specification sheets, pages 20B thru 33B for tag numbers, scales, trip setpoints and card file locations. The master, slave and calibration units shall be furnished completely assembled in their respective card file positions as shown in the specification sheets. ACCESSORIES: Three (3) Trip Unit Card Extenders Two (2) Spare Parts Kits One (1) Readout Assembly Card Extender One (1) Calibration Card Extender One (1) Bench Test Facility Eighty-Eight (88) Blanks for Trip Units Sixtcen (16) Blanks for Calibration Units Two (2) Readout Assembly tagged as follows: 2-B21-4053 144tr 523 Spec. No. 9527-01-252-55 Page 19B
SECTION VI SPECIFICATION SHEET (CONT'D) CABINET TAG No.: 2-CB-XU-63 (ECCS 3/M J.) I CARD FILE CARD FILE INSTRUMENT TRIP c TAG NO. POSITION TAG NO. TYPE SC.iLE (RANGE) SETPOINr SERVICE 2-CB-XU-3897 1 2-B21-N021A-1 M 0-500 PSIC *10 P9TC Rv Pra==_ Ynu 2 2-B21-N021A-2 S (0-500 PSIG) 410 PSIG Rx Press. Low 3 2-B21-N02'C-1 M 0-500 PSIG 310 PSIG 'dx Press. Isa o 4 2-B21-N021C-2 S (0-500 PSIG) 410 PSIG Rx Press. Low
-150 to 60 IN 5 2-B21-h031A-1 M H09 -e38 IN H 2O Rx Level Low
(-150 to 60 IN 6 2-B21-N031A-2 S H9 0) -38 IN H,,0 Rx Ievel Low (-150 to 60 IN -147.5 IN 7 2-B21-NO31A-3 S ,H,0) H,30 Rx Level Low (-150 to 60 IN -147.5 IN 8 2-B21-NO31A-4 S IL,0) H09 Rx Level Low
-150 to 60 IN 9 2-B21-N031C-1 M Hm0 -38 IN H&0 Rx LeveLIsa l (-150 to 60 IN 10 2-B21-NO31C-2 S H,0 -38 IN HoO Rx Level Low
(-150 to 60 IN -147.5 IN 11 2-B21-NO31C-3 S H7 0) H;0 Rx Level Low (-150 to 60 IN -147.5 IN 12 2-B21-NO31C-4 S H,0) H0 Rx Level Low y 13 2-B21-4033 C Sigital - Calibratic n NOTES (1) M = Master Trip Unit; S = Slave Trip Unit; C = Calibration Unit.
, Spec. No. 9527-01-252-5 A
Page 20B 24
SECTION VI SPECIFICATION SHEET (CONr'D) CABINET NO.. 2-CB-XU-63 (ECCS DN f) CARD FILE CARD FILE INSTRUMENT TRIP c TAG NO. POSITION TAG NO. TYPE SCALE (RANGE) SETPOINI SERVICE 2-CB-XU-3898 1 2-B21-N017A-2 M 0-60 IN H 2O 58 IN H 2O Rx Level High 2 2-B21-N017B-2 M 0-60 IN H 2O 58 IN H 2O Rx Level High
-150 TO 60 3 2-B21-N024A 2 M IN H 2O -38 IN H 2O Rx Level Low
-150 TO 60 4 2-B21-N025A-2 M IN H 2O -38 IN H 2O Rx Level Iow
-300 TO 300" -219 IN 5 2-E41-N004-1 M HO2 HO 2 HPCI Stmline6P Hi
(-300 TO 300 +219 IN 6 2-E41-N004-2 S IN H2O) HO 2 HPCI Stmline 6P Hi
-550 TO 550" -387 IN 7 2-E51-N017-1 M HO2 HO 2 RCIC Staline OP Hi
(-550 TO 550" +387 IN 8 2-E51-N017-2 S H2O) HO 2 RCIC StmlineOP Hi 9 2-Ell-N011A-1 M 0-5 PSIG 2 PSIG Drywell Press Hi , 10 2-Ell-N011A-2 S (0-5 PSIG) 2 PSIG Drywell Press Hi 11 2-E11-N0 llc-1 M 0-5 PSIG 2 PSIG Drywell Press Hi 12 2-Ell-N011C-2 S (0-5 PSIG) 2 PSIG Drywell Press Hi Blank for 3p 13 Calib. Unit - - - - NOTES (1) M = Master Trip Unit; S = Slave Trip Unit; C = Calibration Unit. R5' Spec. No. 9527-01-252-55 i Page 21 B q 5}}
SECTION VI SPECIFICATION SHEET (CONr'D) CABINET NO.: 2-CB-XU-63 (E'cC6 DM f) CARD FILE CARD FILE INSTRUMENT TRIP c TAG NO. POSITION TAG NO. IYPE SCALE (RANGE) SETPOINI SERVICE 2-CB-XU-3899 1 2-Ell-N010A-1 M 0-5 PSIG 2 PSIG Drywell Press Hi 2 2-Ell-N010C-1 M 0-5 PSIG 2 PSIG Drywell Press Hi 3 2-Ell-N019A-1 M 0-5 PSIG 2.5 PSIG Drywell Press Hi 4 2-E11-N019C-1 M 0-5 PSIG 2.5 PSIG Drywell Press Hi 12.5 IN 5 2-B21-M042A-1 M 0-60 IN H 2O HO 2 Rx Level Low
-100 TO 200 6 2-B21-NO36-1 M IN H 2O -39 IN H 2O Rx Level low 7 2-Ell-4034-1 M - -
Spare R5 8 2-Ell-4034-2 S - - Spare HPCI Drain Pot 9 2-E41-N014-1 M 0-30 IN H 2O 15 IN H 2O Level High , l 4 10 2-Ell-4035-1 M - - Spare 11 2-Ell-4035-2 S - - Spare 12 Blank - - - - Blank For 13 Calib. Unit - - - - y NOTE: (1) M = Master Trip Unit; S = Slave Trip Unit; C = Calibration Unit N Spec. No. 9527-01-252-55 Page 22 B jgfg j}{
SECTION VI SPECIFICATION SHEET (CONT'D) CABINET TAG NO.: 2-CB-XU-64 (ECCS E/ v- 'I ) CARD FILE CARD FILE INSTRUMENI TRIP c TAG NO. POSITION TAG NO. IYPE SCALE (RANGE) SETPOINI SERVICE 2-CB-XU-3900 1 2-B21-N021E-1 M 0-500 PSIG 310 PSIG Rx Press Low 2 2-B21-N021B-2 S (0-500 PSIG) 410 PSIG Rx Press Low 3 2-B27-N021D-1 M 0-500 PSIG 310 PSIG Rx Press Lo ' 4 2-B21-N021D-2 S (0-500 PSIG) 410 PSIG Rx Press Low
-150 TO 60 5 2-B21-NO31B-1 M IN H90 -38 IN H 9 0 Rx ' Level Low
(-150 TO 60 6 2-B21-N031B-2 S IN H90) -38 IN H 2O Rx Level Low (-150 TO 60 -147.5 IN 7 2-B21-N031B-3 S IN H 2O ) HO2 Rx Level Low (-150 TO 60 -147.5 8 2-321-N031B-4 S IN H 2O) IN H 2O Rx Level Low
-150 TO 60 9 2-B21-N031D-1 M IN H 2O) -38 IN H 2O Rx Level Low
(-150 TO 60 10 2-B21-N031D-2 S IN H 2O) -38 IN H 2O Rx Level Low (-150 TO 60 -147.5 11 2-B21-N031D-3 S IN H 2O) IN H 2O Rx Level Low (-150 TO 60 -147.5 12 2-B21-N031D-4 S IN H 2O) IN H 2 O Rx Level Low 3r 13 2-B21-4036 C Digital - Calibration NOTE: (1) M = Master Trip Unit; S = Slave Trip Unit; C = Calibration Unit l
- I Spec. No. 9527-01-252-55 Page 23B i
4 g }}J
SECTION VI
, SPECIFICATION SHEET (CONT'D)
CABINET TAG NO.: 2-CB-XU-64 (E c C S .D/v. 5 ) CARD FILE CARD FILE INSTRUMENT TRIP C TAG NO. POSITION TAG NO. TYPE SCALE (RANGE) SETPOINT SERVICE 2-CB-KU-3901 1 2-B21-N017C-2 M 0-60 IN H 2O 58 IN H 2O Rx Level High 2 2-B21-N017D-2 M 0-60 IN H 2O 58 IN H 2O Rx Level High
-150 TO 60 3 2-B21-N024B-2 M IN H 2O -38 IN H 2O Rx Level Low
-150 TO 60 4 2-B21-N025B-2 M IN H 2O -38 IN H 2O Rx Level Low
-300 TO 300 -292 5 2-E41-N005-1 M IN H 2O IN H 2O HPCI Stmline s&P Hi
(-300 TO 300 + 292 6 2-E41-N005-2 S IN H 2O) IN H 2O HPCI Stmline 21P Hi
-550 TO 550 -516 7 2-E51-N018-1 M IN H 2O IN H 2O RCIC Stmline a&P Hi
(-550 TO 550 + 516 8 2-E51-N018-2 S IN H 2O) IN H 2O RCIC Stmlinet1P Hi 9 2-Ell-N011B-1 M 0-5 PSIG 2 PSIG Drywell Press Hi I 10 2-Ell-N0llB-2 S (0-5 PSIG) 2 PSIG Drywell Press Hi 11 2-Ell-N0llD-1 M 0-5 PSIG 2 PSIG Drywell Press Hi 12 2-Ell-N0llD-2 S (0-5 PSIG) 2 PSIG Drywell Press Hi Blank for gp 13 Calib. Unit - - - - NOTE: (1) M = tbste c Trip Unit; S = Slave Trip Unit; C = Calibration Unit ^ - Spec. No. 4527-01-252-55 l Page 24 8 144't t28
SECTION VI SPECIFICATION SHEET (CONT'D) CABINET TAG NO.: 2-CB-KU-64 (recs riv ZE) CARD FILE CARD FIE INSTRUMENI TRIP C TAG NO. POSITION TAG NO. IYPE SCALE (FAtCE) SETPOINT SERVICE 2-CB-KU-3902 1 2-Ell-N010B-1 M 0-5 PSIG 2 PSIG Drywell P ess Hi 2 2-Ell-N010D-1 M 0-5 PSIG 2 PSIG Drywell Press Hi 3 2-Ell-N019B-1 M 0-5 PSIG 2.5 PSIG Drywell Press Hi 4 2-Ell-N019D-1 M 0-5 PSIG 2.5 PSIG Drywell Press Hi 12.5 5 2-B21-N042B-1 M 0-60 IN H 2O IN H 2O Rx Level Low
-100 TO 200 6 2-B21-N037-1 M IN H 2O -39 IN H 2O Rx Level Low 7 2-Ell-4037-1 M - -
Spare l R5! 8 2-Ell-4037-2 S - - Spare i RCIC Drain Pot 9 2-E51-N010-1 M 0-30 IN H 2O 8 IN H 2O Level High 10 2-Ell-4038-1 M - - Spare 11 2-Ell-4038-2 S - - Spare 12 Blank - - - - Blank For y, 13 Calib. Unit - - - - NOTE: (1) M = Master Trip Unit; S = Slave Trip Unit; C = Calibration Unit 8
. 2h l
Spec. No. 9527-01-252-55 Page 25 B
SECTION VI SPECIFICATION SHEET (CONT'D) CABINET TAG No. : 2-CB-XU-65 (RPS (M NNE4 A2) CARD FILE CARD FILE INSTRUMENT TRIP c TAG NO. POSITION TAG NO. TYPE SCALE (RANC-E) SETPOINr SERVICE _ 2-CB-XU-3903 1 2-B21-N006A-1 M 0-150 PSID 9 PSID Main Stm. Flo High 2 2-B21-N006A-2 S (0-150'PSID) 115 PSID Main Stm. Flo High 3 2-E21-N007A-1 M 0-150 PSID 115 PSID Main Stm. Flo High 4 2-B21-N008A-1 M 0-150 PSID 115 PSID Main Stm. Flo High 5 2-B21-N009A-1 M 0-150 PSID 115 PSID Main Stm. Flo High 6 2-B21-N015A-1 M 0-1200 PSIG 825 PSIG Main Stm. Press Lo
-150 to 7 2-B21-U024A-1 M" 60IN H 2O -381N H 2O Rx Level Low 2-B21-N056A-1 8 M 0-30 IN HgVAC_ 7 IN HgVAC_ Cond. Vacuum Low ]
9 2-C72-N002A-1 M 0-5 PSIG 2 PSIG Drywell Press High 10 2-B21-N017A-1 M 0-60IN H 2O 12.5IN 1120 Rx Level Iow 11 2-B21-N023A-1 M 600-1200 PSIG 1045 PSIG Rx Press High 12 2-B21-N023A-2 S (600-1200PSIG: 1035 PSIG Rx Press High y 13 2-B21-4039 C Digital - Calibration NOTE: (1) M = Master Trip Unit; S = Slave Trip Unit; C = Calibration Unit 14W 530 -_ Spec. No. 9527-01-252-55
- ~ l Page 26B
SECTInN VI SPECIFICATION SHEET (CONT'D) CABINET TAG NO. : 2-CB-XU-65 ('NPS cNANNEL A 2 ) ._ CARD FILE CARD FILE INSTRUMENI TRIP C TAG NO. POSITION TAG NO. TYPE SCALE (RANGE) SETPOINI SERVICE _ 2-CB-XU-3904 1 2-B21-4040-1 M - - Spare 2 2-B21-4040-2 S - - Spare 3 Blank - - - - 4 Blank - - - - 5 Blank - - - - 6 Blank - - - - 7 Blank - - - - 8 Blank - - - - 9 Blank - - - - we a 10 Blank - - - - 11 Blank - - - - 12 Blank - - - - Blank for 13 Calib. Unit - - - - hTJI: (1) M = Master Trip Unit; S - Slave Trip Unit; C = Calibration Unit [k g'c - Spec. No. 9527-01-252-55 Page 27 B
SECTION VI SPECIFICATION SHEET (CONT'D) CABINET TAG NO. : 2-CB-XU-65 (RPS CNANNEL A2) .- CARD FILE CARD FILE INSTRUMENT TRIP C TAG NO. POSITION TAG NO. TYPE SCALE (RANGE) SETPOINI SERVICE _ 2-CB-XU-3905 1 2-B21-N006C-1 M 0-150 PSID 115 PSID Main Stm Flo High 2 2-B21-N007C-1 M 0-150 PSID 115 PSID Main Stm Flo High 3 2-B21-N008C-1 M 0-150 PSID 9 PSID Ma . n Stm Flo High 4 2-B21-N008C-2 S (0-150 PSID) 115 PSID Main Stm Flo High 5 '-B21-N009C-1 M 0-150 PSID 115 PSID Main Stm Flo High 6 2-B21-N015C-1 M 0-1200 PSIG 825 PSIG Main Stm Press Lo
-150 to 60 7 2-D21-N025A-1 M IN H20 -38 IN H 2O Rx Level Low ,
8 2-B21-N056C-1 M 0-30 IN Hg VAC 7 IN HgVAC Cond. Vacuum Low 9 2-C72-N002C-1 M 0-5 PSIG 2 PSIG Drywell Press Hi 4 10 2-B21-N017C-1 M 0-60 IN H 2O l2.5IN H 2O Rx Level Low 11 2-B21-N023C-1 M 600-1200 PSIG 1045 PSIG Rx Press High 12 2-B21-N023C-2 S (600-1200 PSIG )1035 PSIG Rx Press High 13 2-B21-4041 C Digital - Calibration NOTE: (1) M - tbster Trip Unit; S = Slave Trip Unit; C = Calibration Unit j 440f h)2, i R Spec. No. 9527-01-252-55
, Page 28B
SECTION VI SPECIFICATION SHEET (CONT'D) CABINET TAG No. : 2-CB-XU-66 (RPS CHANNEL A2) .- CARD FIIR CARD FILE INSTRUMENT TRIP C TAG NO. POSITION TAG NO. TYPE SCALE (RANGE) SETPOINT f.ERVICE _ 2-CB-XU-3906 1 2-B21-4042-1 M - - Spare 2 2-B21-4042-2 S - - Spare 3 Blank - - - - 4 Blank - - - - 5 Blank - - - - 6 Blank - - - - 7 Blank - - - - 8 Blank - - - - 9 Blank - - - - 10 Blank - - - - 11 Elank - - - - 12 Blank - - - - Blank For 13 Calib. Unit - - - - 9 NOTE: l (1) M = Master Trip Unit; S = Slave Trip Unit; C = Calibration Unit !44 533 1 Spec. No. 9527-01-132-55 Page 29 B
SECTION VI SPECIFICATION SHEET (CONT'D) CABINET TAG No.: 2-CB-XU-67 (RPS cNANNc4 SI) _ CARD FILE CARD FILE INSTRUMEffr TRIP C TAG NO. POSITION TAG NO. TYPE SCALE (RANGE) SETPOINr SE_RVICE _ 2-CB-XU-3907 1 2-B21-N006B-1 M 0-150 PSID 115 PSID Main Stm Flo High 2 2-B21-N007B-1 M_ 0-150 PSID 9 PSID Main Stm Flo High 3 2-B21-N007B-2 S (0-150 PSID) 115 PSID Main Stm Flo High 4 2-B21-N008B-1 M 0-150 PSID 115 PSID Main Stm Flo High 5 2-B21-N009B-1 M 0-150 PSID 115 P,SID __ Main Stm Flo High 6 2-B21-N015B-1 M 0-1200 PSIG 825 PSIG Main Stm Press Lo
-150 To 60 7 2-B21-N024B-1 M IN H2O -38 IN H2O Rx Level Io 8 2-B21-N056B-1 M 0-30 IN HgVAC 7 IN HgVAC Cond. Vacuum Io 9 2-C72-N002B-1 M 0-5 PSIG 2 PSIG Drywell Press Hi 10 2-B21-N017B-1 M 0-60 IN H 2O 12.5IN H 2O Rx Lev?.1 In 11 2-B21-N023B-1 M 600-1200 PSIG 1045 PSIG Rx Press High 12 2-B21-N023B-2 S (600-1200PSIG) 1035 PSIG Rx Press High y 13 2-B21-4043 C Digiual -
Calibration NOTE: (1) M = Master Trip Unit; S = Slave Trip Unit; C = Calibration Unit } kk bhk Spec. No. 9527-01-252-55 RI Page 30B
SECTION VI SPECIFICATION SHEET (CONT'D) CABINET TAG NO. : 2-CB-XU-67 (RFS cNANNE4 Sf) .- CARD FILE CARD FIII INSTRUMENT TRIP c TAG NO. POSITION TAG NO.' TYPE SCALE (PANGE) SEIPOINI SERVICE _ 2-CB-XU-3903 1 2-B21-4044-1 M - - Spare 2 2-B21-4044-2 S - - Spare 3 Blank - - - - 4 Blank - - - - 5 Blank - - - - 6 Blank - - - - 7 Blank - - - - 8 Blank - - - - 9 Blank - - - - 10 Blank - - - - 11 Blank - - - - 12 Blank - - - - Blank for Calib. Unit 4 - g NOTE: L (1) M = Master Trip UnitJ S = Slave trip Unit; C = Calibration Unit J s Spec. No. 9527-01-252-55
! Page 31B
SECTION VI SPECIFICATION SHEET (CONT'D) CABINET TAG NO.: 2-CB-XU-68 (RPS CNANNEZ S2) _ CARD FILE CARD FILE INSTRUMENT TRIP C TAG NO. POSITION TAG NO. TYPE SCALE (RANGE) SETPOINI SERVICE _ _ _ _ 2-CB-XU-3909 1 2-B21-N006D-1 M 0-150 PSIG 115 PSID Main Stm Flo High 2 2-B21-N007D-1 M 0-150 PSID 115 PSID Main Stm Flo High 3 2-B21-N00CD-1 M 0-150 PSID 115 PSID Main Stm Flo High 4 2-E21-N009D-1 M 0-150 PSID 9 PSID Main Stm Flo High 5 2-B21-N009D-2 S (0-150 PSID) 115 PSID Main Stm Flo Mich 6 2-B21-N015D-1 M 0-1200 PSIG 825 PSIG Main Stm Press Low
-150 To 60 7 2-B21-N025B-1 M IN H 2O -38 IN H 9 0 Rx Level low 8 2-B21-N056D-1 M 0-30IN HgVAC 7 IN HgVAC Cond. Vacuum Low 9 2-C72-N002D-1 M 0-5 PSIG 2 PSIG Drvwell Frees Hi _
10 2-B21-N017D-1 M 0-60 IN d 20 12.5IN H 2O Rx Level Iow 11 2-B21-N023D-1 M 600-1200 r3IG 1045 PSTC Rr Press High 12 2-B21-N023D-2 S :600-1200PSIG) 1035 PSIG Rx Press High 3r 13 2-B21-4045 C Digital - Calibration NOTE: (1) M = Master Trip Unit; S = Slave Trip Unit; C = Calibration Unit
! 44 f '36~
4,_ Spec. No. 9527-01-252-55 Page 32 B
SECTION VI SPECIFICATION SHEET (CONT'D) CABINET TAG NO : 2-CB-XU-68 (RFS CNANNEL B2) ._ CARD FILE CARD FILE INSTRUBENI TRIP C TAG NO. POSITION TAG NO. TYPE SCALE (RANGE) SETPOINI SERVICE _ 2-CB-XU-3910 1 2-B21-4046-1 M - - Spare 2 2-B21-4046-2 S - - Spare 3 Blank - - - - 4 Blank - - - - 5 Blank - - - - 6 Blank - - - - 7 BlarA - - - - 8 Blank - - - - l 9 Blank - - - - 10 Blank - - - - 11 Blank - - - - 12 Blank - - - - Blank for
, 13 Calib. Unit ,
NOTE: (1) M = Master Trip Unit; S - Slave Trip Unit; C = Calibration Unit i 1444 '37 Spec. No. 9527-01-252-55 Page 33 B
1444 538 TABLE 2.2.1-1 en REACTOR PROTECTION SYSTEM INSTRUllEtHATION SETPOINTS
- o E ALLOWABIE FUNCTIONAL UNIT AND INSTRUMENT tRIMBER TRIP SETPOItn VAIATES
- 1. Intermediate Range Monitor, Neutron Flux - liigh I} $120 divisions of full scalc $170 divisions c: (C51-IRM-K601 A,B,C,D,E,F,G,II) of full scale d
.-i ro
- 2. Average Power Range Monitor (C 51-APRM-Cil . A , B ,C , D,E , F )
- a. Neutron Flux - liigh, 157. 1157. of RATED TilERMAL POWER 1157. of RATED TilERMAL POWER
- b. Flow Biased Neutron Flux - liigh(3)(4) S(0.66 W + 547.) 1(0.66 W + 547.)
- c. Fixed Neutron Flux - Iligh(4) 31207. of RATED TIIERMAL POWER $1207. of RATED TilERFML POWER Y
t~
- 3. Reactor Vessei Steam Dome Pressure - Iligh (B21-P".1-N023A-1,B-1,C-1,D-1) < 1045 psig < L045 psig
_ l .w. b d #I
- 4. Reactor Vessel Water Level - Low, Leve1
- ( B21-LTM-N017A-1, B-1, C-1, D-1 ) >12.5 inches above instru-
~
>17.5 inches above U ment zero ~ instrument zero D *
- 5. Main Steam Line Isolation valve - Closure (5) $107. closed $107. closed
> (B21-F022 A,B,C,D; B21-F028 A,B,C,D) o W Main Steam Line Radiation - Iligh $3 x full power background 13.5 x full power to 6.
N (D12-RM-K603 A,B,C,D) background
.E
TABLE 2.2.1-1 (continued) g REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOIFTTS z y ALIDWABLE FUNCTIOh\L UNIT AND INSTRUMEtTr NUMBER TRIP SETPOINT VALUES 8
- 7. Dryuell Pressure - liigh 53 (C 72 - PTM-N002 A-1, B-1, C-1, D-1 ) <2 psig 12psig l M
e N
- 8. Scram Discharge Volume Water Level - High $109 gallons $109 gallons (C11-LSil-N013 A,B,C,D)
Y C o n a _ z a
- O
TABLE 3.3.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION N APPLICABLE MINIMUM NUMBER OPERATIONAL OPERABLE CIIANNc.LS h CONDITIONS PER TRIP SYSTEM (a)(b) ACTIM C FUNCTIONAL UNIT AND INSTRUMENT NUMBER ( l. Intermediate Range Monitors: ( C 51 - I RM-K601 A , B , C , D, E , F , G ,II)
$ a. Neutron Flux - liigh 2, 5 3 I 3, 4 e 2 w
2, 5 3 1
- b. Inoperative 3, 4 2 2
- 2. Average Power Range Monitor:
( C S I - APRM-CII . A , B , C , D, E , F , ) 2, 5 2 3
- a. Neutron Flux - liigh, 157.
2 4 R b. Flow Blased Neutron Flux - liigh 1
- Fixed Neut ron Flux-liigh, 1207. I 2 4 c.
1, 2, 5 2 5 g d. Inoperative 2 4 L e. Downscale 1 E. LPRtl 1, 2, 5 (c) NA
- 3. Reactor Vessel Steam Dome Pressure -
liigh
-*. (B71-PT-N023A,B,C,D)
A (B21-PTM-N023A-1,B-1,C-1,D-1) 1, 2(d) 2 6 4
- 4. Reactor Vessel Wate r I.evel Low, Level #1 (B21-LT-N017A-1,B-1,C-1,D-1)
[ (B21-LTM-N017A-1,B-1,C-1,D-1) 1, 2 2 6 m 5. Main Steam Line Isolation Valve - N Closure (B21-F022 A, B,C, D, and B21-F028A,B,C,D) 1 4 4
TABLE 3.3.1-1 (Continued) m REACTOR PRCTTECTION SYSTEM INSTRUMENTATION APPLICABLE MINIMUM NUMBER OPERATIONAL OPERABLE CIIANNELS y FUNCTION UNIT AND INSTRUMENT NUMBER CONDITIONS PER TRIP SYSTEM (a)(b) ACTION
- 6. Main Steam Line Radiation - liigh 1, 2(d) 2 7
,.; (D12-RM-K603A,B,C,D)
H N
- 7. Drywell Pressure - liigh (C72 -PT-N002 A , B ,C , D) (e)
(C72-PTM-N002A-1,B-1,C-1,D-1) 1, 2 2 6
- 8. Scram Discharge Volume Water Level -
High (C12-LSil-N013A,B,C, D) 1, 2, S II) 2 5
- 9. Turbine Stop Valve - Closure 1(g) 4 8 w
) (EllC-SVOS-1X,2X,3X,4X) y 10. Turbine Control Valve Fast Closure g) " Control Oil Ptessure - Low 1 2 8 (EllC-PSL-17 56,1757,17 58,1759
- 11. Reactor Mode Switch in Shutdown 1,2,3,4,5 1 9 Position (C72A-SI)
- 12. 'lanual Scram (C72A-S3A,B) 1,2,3,4,5 1 10 I
- i.
R P, a .?
1 TABLE 3.3.1-2
, REACTOR PROTECTION SYSTEM RESPONSE TIMES E
- 2: FUNCTIONAL UNIT AND INSTRUMENT NUMBER RESPONSE TIME (Seconds )
E h 1. Intermediate Range Moni tors (C51-IRM-K601 A,B,C, D,E , F,G,II): e
- a. Neutron Flux - liigh* NA h b. Inoperative NA a
N'
- 2. Average Power Range Monitor * (C51-APRM-Cll.A,5,C,D,E,F):
- a. Neut ron Flux - liigh, 157. <0.09
- b. Flow Biased Neutron Flux - IILgh NA
- c. Neutron Flux - liigh,1207. $,0.09
- d. Inoperative NA
- e. Downscale NA
- f. LPRM NA M
- 3. Reactor Vessel Steam Dome Pressure - liigh w ( B21-PT-N02 3A , B , C , D) $y0.55
& (B21-PTM-N023A-1,B-1,C-1,D-1)
- 4. Reactor Vessel Water Level - Level #1 (B21-LT-N017A-1,B-1,C-1,D-1) <1.05 (B21-LTM-N017A-1,B-1,C-1,D-1)
- 5. thin Steam Line Isolation Valve-Closure (B21-F022A, B,C,D and B21-F028A,B,C, D) 50.06
- 6. thin Steam Line Radiation - liigh (D12-RM-K603A,B,C,D) NA g 7. Drywell Pressure - liigh
@ (C72 -PT-N002A , B , C, n) NA (C72-PTM-N002A-1,B-1,C-1,D-1)
{ o a=>
" 4 p. Scram Discharge Volume Water Level - liigh (C12-LSil-N013A,B,C,D) NA
- 9. Turbine Stop Valve - Closure (EllC-SVOS-1X,2X,3X,4X) $j0.06 CrJ
TABLE 3.3.1-2 (Continued) w REACTOR PRUTECTION SYSTEM RESPONSE TIfES w h FUNCTIONAL UNIT AND INSTRUMENT NUMBER RESPONSE TINE (Seconds) 5 pj 10. Turbine Control Valve Fast Closure,
, Control Oil Pressure - Low (EllC-PSL-17 56,17 57,17 58,17 59) 5,0.08 h 11. Reactor Mode Switch in Shutdown Position (C72A-SI) NA H
63
- 12. Manual Scram (C72 A-S3A,B) NA R
v Y C A A
-P
[' .s
- g. am.
R R y
- Neutron detectors are exempt from response time testing. Response time shall be measuced from detector o'itput or input of first elec tronic componeret in channel.
TABLE 4_.3.1-1 RF"CR)R E PROTECTION SYSTEM INSTRUMEtr1AT10N SURVEILWC,E_REQUIRDIENTS CllANNEL OPERATIONAI h CliANNEL FUNCTIONAL C11ANNEL CONDITIOM IN WCN p FUNCTIONAL UNIT CALIBRATION (g) SURVEILLANCE REQUIRED AND INSTRUMENT NUMBER CllECK TEST h 1. Intermediate Range Ilonitors: H (C51-IRM-K601 A,B,C,D,E,F,G,II) w S/U(b)(c) R 2
- a. Neutron Flux - liigh D D W R 3,4,5
- b. Inoperative NA W NA 2,3,4,5
- 2. Average Power Range Monitor:
(C51-APRM-Cll. A, B,C, D,E, F)
- a. Neutron Flux - liigh 157. S S/U(b) , g(d) Q 2 S W 5
- b. Flow Biased Neutron Flux-liigh S S/U(b) y Q g (e)(f) ,q t y
2 c. Fixed Neutron Flux - liigh, S S/U(b) ,y g(e) ,q y w 1207. NA W NA 1,2,5 O d. Inoperative
- e. Downscale NA W NA 1
- f. LPRM D NA (g) 1, 2, 5
- 3. Reactor Vessel Steni.i Dome Pressure - liigh (E21-PT-NO23A, B, C, D) nab) NA R(1) ,
(B21-PTM-N023A-1, B-1, C-1, D-1) D M M 1, 2 $ _.__h . Reactor Vessel Water Level - Low f O' p Level #1 ! w (B21-LT-N017A-1, B-1, C-1, D-1) NA( } NA R(1) i y (B21-LTM-N017A-1, B-1, C-1, D-1) D M M 1, 2 Ei v9 . Main Steam Line Isolation Valve - , A Closure (B21-F022 A,n,C,D and NA M R(h) i i W B21-F028 A, B,C, D)
TABLE 4.3.1-1_(continued)
@ REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIRDfENTS U
" CllANN EL OPERATIONAL b FUNCTIONAL UNIT CilANNEL FUNCTIONAL CllANNEL CONDITIONS IN WilICll
' AND INSTRUMENT NUMBER CllECK TEST CALIBRATION (") SURVEILLANCE REQUIRED c:
- 6. Main Steam Line Radiation-liigh S M(1) R(l) 1, 2 m (D12-RM-K603 A,B,C,D)
- 7. Drywell Pressure - liigh (C72-PT-N002A, B, C, D) NA(k) NA R(I)
(C72-PRI-N002A-1,B-1,C-1,D-1) D M M 1, 2
- 8. Scram Discharge Volume W. iter Level - liigh NA Q R 1,2,5 (C12-LSil-N013 A, B, C, D) u 9. Turbine Stop Valve - Closure NA M R(h) 1 S ( EllC-SVOS -1X , 2X, 3X, 4X)
So 10. Turbine Control Valve Fast Closure, Control Oil Pressure-Low (EllC-PSL-1756,1757,1758, NA M R 1 1759)
- 11. Reactor Mode Switch in Shutdown NA R NA 1,2,3,4,5 Position (C72A-S1)
- 12. Manual Scram NA Q NA 1,2,3,4,5
$ (C72A-S3A,B)
$ a. Neutron detectors may be excluded f rom CllANNEL CALIBRATION. '
O' b. Within 24 hours prior to startup, if not performed within the previous 7 days.
$ c. The IRM channels shall be compared to the APRM channels and the SRM instruments for overlap during each startup, if not performed within the previous 7 days.
q o d. When changing from CONDITION 1 to CONDITION 2, perform the required surveillance within 12 hours
# after entering CONDITION 2. .c> e. This calibration shall consist of the adjustment of the APRM readout to conform to the power values CD calculated by a heat balance during CONDITION 1 when TilERMAL POWER 2 257. of RATED 'IllERMAL POWER.
i TABLE 4.3.1-1 (continued) REACIOR PROTECTION SYSTEM INSTRUMENTATION SURVEIILANCE REQUI,REMENTS $ i ?! M This calibration shall consist of the adjustment of the APRM flow biased detpoint to conform to a " f. .'
' calibrated flow signal.
E y g. The LPRM's shall be calibrated at least once per effective full power month (EFPM) using the sa TIP system.
- h. This calibration shall consist of a physical inspection and actuation of these position switches.
- i. Instrument alignment using a standard current source.
J. Calibration using a standard radiation source.
- k. The transmitter channel check is satisfied by the trip unit channel check.
A separate trans- :t';er check is not required, t" Transmitters are exempted from the monthly channel calibration. 1. Y s F g __.
& 4s-
@ 4:=
-){
P. us, b N
TABLE 3.3.2-1 ISOLATION ACTUATION INSTRUMENTATION N @ VALVE GROUPS MINIMUM NUMBER APPLICABLE 2 OPERATED BY OPERABLE CHANNELS OPERATIONAL 8 TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a) PER TRIP SYSTEM (b)(c) CONDITION ACTION X t
- l. PRIMARY CONTAINMENT ISOLATION E
[j a. Reactor Vessel Water Level - Low w
- 1. Level #1
( B 21 -LT-N017 A- 1, B- 1, C- 1, D- 1 ) (B21-LTM-N017A-1,B-1,C-1,D-1) 2,6,7,8 2 1, 2, 3 20
- 2. Level #2 (B21-LT-N024A-1,B-1,and ,
B21-LT-N025A-1,B-1 u, (B21-LTM-N024A-1,B-1 and 3: B21-LTM-N025A-1,B-1) 1, 3 2 1,2,3 20 i' b. Drywell Pressure - High [ (C72 -PT-N002A,P C, D) (C72-PTM-N002A-1,B-1,C-1,D-1) 1, 6, 7 2 1,2,3 20
- c. Main Steam Line
- 1. Radiation - High (d) 1 2 1,2,3 21
( D12- RM-K603 A , B , C , D)
- 2. Pressure - Low
( B21 -PT-N015 A , B , C , D)
- (B21-PTM-N015A-1,B-1,C-1,D-1) 1 2 1 22 E.
R a~ o .w.
~
O W CO
l l j TABLE 3.3.2-1 (Continued) es ISOLATION ACTUATION INSTRUMENTATION E M VALVE GROUPS MINIMUM NUMBER APPLICABLE
$ OPEP3.TED BY OPERABLE CHANNELS OPERATIONAL Q TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a)_ PER TRIP SYSTEM (b)(c) CONDITION ACTION i '
I e 1. PRIMARY CONTAINMENT ISOLATION (Continued)
! M
[ c. Main " team Line (Continued) 4 j 3. Flow - High , i (B21-PDT-N006A,B,C,D; ' j B21-PDT-N007A,B,C,D; l B21-PDT-N008A,B,C,D; , B21-PDT-N009A,B,C,D) ! ( B21- PDTM-N006 A-1, B-1, C-1, D-1 ; i B21-PDTM-N007A-1,B-1,C-1,D-1; i t'. B21-PDTM-N008A-1,B-1,C-1,D-1; 1 2/line 1 22 l b21-PDTM-N009A-1,B-1,C-1,D-1) . a - i , 4. Flow - High I i E (B21-PMS-N006A-2: ( f .! B21-PMS-N007 B-2 ; ! ! B21-PDTS-N008C-2; 1 2 2, 3 21 l l B21-PDTS N009D-2) i i I I d. > Min Steam Line Tunnel i l Temperature - High 1 2(e) 1, 2, 3 21 ; ( B 21-TS -N010A, B , C, D; B21-TS-N011 A, B, C , D; B21-TS-N012A,B,C,D and B21-TS-N013A,B,C,D)
$ e. Condenser Vacuum - Low
$ ( B 21 - PI-N0 56 A , B , C , D) ;
~
$~ (B21-PTM-N056A-1,B-1,C-1,D-1) 1 2 1, 2(f) 21 -
.Pf . Turbine Building Area
$ & Temperature - High 1 4(e) 1, 2 , 3 21 4 (B21-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; B21-TS-3227A,B,C,D; B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; and B21-TS-3232A,B,C,D) --
P W
TABLE 3.3.2-1 (Continued) ISOLATICt1 ACTUATION INSTRUMENTATION VALVE GROUPS MINIMUM NUMBER APPLICABLE $ OPERATED BY OPERABLE CitANNELS OPERATIONAL , sj CONDITION ACTION y TRIP FUNCTION AND INSTRUMENT NUMBER SIGN AI.(a) PER TRIP SYSTEM (b)(c)_ j o M 2. SECONDARY CONTAINMENT ISOLATION g e Ej a. Reactor Building Exhaust 23 1, 2, 3, 5 and
- y Radiation - !!Igh 6 1 m (D12-RM-N010A,B) ,
I
- b. Drywell Pressure - lii gh
( C72 - PT-N002 A , B , C , D) 2, 6, 7 2 1,2,3 23 ( C 72 - PTM- N002 A-1, B- 1, C-1, D-1)
- c. Reactor Vessel Water Level - Low, Level #2 (B21-LT-N024A-1,B-1 and t', B21-LT-N025A-1,B-1) n u,
(B21-LTM-N024A-1,B-1 and , B21-LTM-N025A-1,B-1) 1, 3 2 1,2,3 23 S w
- 3. REACTOR WATER CLEANUP SYSTEM ISOLATION 3 1 1,2,3 24
- a. A Flow - liigh (G 31 -d FS-N603-1 A , l B) 2 1,2,3 24
- b. Area Temperature - lii gh 3
( G31 -TS-N600 A , B , C , D, E , F) 3 2 1, 2, 3 24
- c. Area Ventilation a Temp. - liigh g (G31-TS-N602 A,B,C, D,E F)
SLCS Initiation (C41A ,1) 3(g) NA 1, 2 , 3 24 ,
@ d. !
y- __ e . Reactor Vessel Wa*- c Level -
@ gy, Lo' '. eve t ft2 a== (B21-LT-N024A-1,B-1 and B21-LT-N025A-1,B-1)
{ -( s/* (B21-LTM-N024A-1.B-1 and 1,2,3 24 W B21 -LIM-N025 A-1,3-1) 1, 3 2 CD
TABLE 3.3.2-1 (Continued) ISOLATION ACTUATION INSTRUMENTATION VALVE GROUPS MINIMUM NUMBER APPLICABLE g OPERABLE CIIANNELS OPERATIONAL OPERATED BY @ SICNAL(a) PER TRIP SYSTEM (b)(c) CONDITION ACTION TRIP FUNCTION AND INSTRUltENT NUMBER O 4. CORE STANDhY COOLING SYSTEMS ISOLATION g a, liigh Pressure Coolant y Injection Isolation l " 1. IIPCI Steam Line Flow - II1gh (E41-PDT-N004 and E4 ? -PITT-N005 ) 1, 2, 3 25 4 2 (E41-PITIM-N004-1 and E41-PirrM-N005-1) (E41-PIrrS-N004-2 and E41-PITIS-N005-2) t'
- 2. HPCI Steam Supply Pressure - 1,2,3 25 4 2 u Low (E41-PSL-N001A,B,C,D) 0
- 3. IIPCI Steam Line Tunnel 1,2,3 25 4 2 Temperature - liigh (E41-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488 and E41-TS-3489) 1/ bus 1, 2, 3 26
- 4. Bus Power Monitor *!A(h)
(E41-K55 and E41-K56)
- 5. IIPCI Turbine Exhaust 1, 2, 3 25 fg _
Diaphragm Pressure - High ( E41-PSil-N012 A, B , C , D) 4 2 R ^ c .. 6. IIPCI Steam Line Ambient 1, 2, 3 25 4 2
-- Temperature - liigh o
(E51-TS-N603C,D) A m
I TABLE 3.3.2-1 (Continued) ISOLATION ACTUATION INSTRUMENTATION en M VALVE GROUPS MINIFRRI NUMBER APPLICABLE OPERATED BY OPERABLE CIIANNELS OPERATIONAL _, SIGNAL (a) PER TRIP SYSTEM (b)(c) CONDITION _ ACTI ON $ TRIP FUNCTION AND INSTRUMENT NUMBER O
- 4. CORE STANDBY COOLING SYSTEMS ISOLATION (Continued) s H a. liigh Pressure Coolant
" Injection Isolation (Continued) I 4 2 1, 2, 3 25
- 7. IIPCI Steam Line Area A Temp . -
i liigh ( E 51-dTS-N604 C , D) .
- 8. Emergency Area Cooler 1,2,3 25 Tempe rature - liigh 4 2 ,
u, (E41-TS-N002A,B) E i' C i i I
; as, $bas, g
n Z W P LJ7 rs]
TABLE 3.3.2-1 _y atinued) ISOLATION ACTUATION INSTRDIENTATION N VALVE CROUPS MINIMUM NUMBER APPLICABLE g cn OPERATED BY OPERABLE CIIANNELS OPERATIONAL b TRIP FUNCTION AND I!!STRUtIENT NUMBER SIGNAL (a) PER TRIP SYSTEM (b)(c) CONDITION ACTION O i b. Reactor Core Isolation g Cooling System Isolation s
- 1. RCIC Steam Line Flow - liigh (E51-PIYT-N017 and E51-PDT-N018)
(E51-PDTM-N017-1 and 5 2 1,2,3 25 E51-PITn?-N018-1) i (E51-PDTS-N017-2 ar.d E 51-PITIS-N018-2 )
- 2. RCIC Steam Supply Pressure -
Low (E51-PS-N019A,B,C,D) ' 2 1,2,3 25 t
- 3. RCIC Steam Line Tunnel Temperature -
liigh 5 2 1,2,3 25 i (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; E51-TS-3323; E51-TS-3355 and E51-TS-3487)
- 4. Bus Power Mor.itor NA(h) 1/hus 1, 2, 3 26 (E51-K42 and E51-K43)
- 5. RCIC Turbine Exhaust Diaphragm Pressure - liigh 5 2 1, 2, 3 25 g (E51-PS-N012A,B,C,D) m E. m 6. RCIC Steam Line Ambient Temp - liigh 5 2 1, 2, 3 25 l
A n (E51-TS-N603A,B) Z -P 7. RCIC Steam Line Area A Temp - liigh 5 2 1,2,3 25 . (E51-dTS-N604A,B) u W 8. RCIC Equipment Room Ambient U Temp - 111gh (E51-TS-N602A,B) 5 2 1, 2, 3 25
- 9. RCIC Equipmeut Room A Temp - liigh 5 2 1,2,3 25 (E51-dTS-N601A,B)
i TABLE 3.3.2-1 (Continued) ISOLATION ACTUATION INSTRUMENTATION N ll VALVE GROUPS MIt' MUM NUMBER APPLICABLE y] OPERATED BY OPERABLE CitANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a) PER TRIP SYSTEM (b)(c) CONDITION ACTION M m
- 5. SilUTDORN COOLING SYSTEM ISOLATION E!
y a. Reactor Vessel Water - Low, Leve:1 #1 (B21-LT-N017A-1,B-1,C-1,D-1) ( B21-LTM-N017 A-1, B-1, C-1, D-1 ) 2,6,7,8 2 3, 4, 5 25
- b. Reactor Steam Dome Pressure - liigh 7, 8 1 1,2,3 27 (B32-PS-N018A,B) ti e
h C i I ppO
, a=.
h* J5m i "9E y ~ ,- LJ7 P=
TABLE 3.3.2-2 m ISOLATION ACTUATION INSTRUMENTATION SETPOINTS w E m ALLOWABLE b TRIP FUNCTION AND INSTh4FENT NUMBER TRIP SETPOINT VALUE i 1. PRIMARY CONTAINMEFT ISOLATION C d a. Reactor Ve5sel Water Level - Low d
- 1. Le.vtl . #1 (B21-LTM-N017A-1,3-1,C-1,D-1) > +12. 5 inch > +12. 5 inches
- 2. Leveli #2 (B21-LTM-N024A-1,3-1 and }[-38 inches jh-38 inches B21-LTM-N025A-1,3-1)
- b. Drywell Pressure - High < 2 psig < 2 psig (C72-PTM-N002A-1,B-1,C-1,D-1) l
- c. Main Steam Line
- 1. Radiation - High M
( D12- RM-K603 A , B , C , D) $ 3 x full power background 5 3.5 x full power background w 2. Pre s s u re - Low (B21-PTM-N015A-1,B-1,C-1,D-1) j> 825 psig 2 825 psig l h
- 3. Flow - High $ 140% of rated flow < 140% of rated (B21-PDTM-N006A-1,B-1,C-1,D-1; B21-PDTM-N007A-1,B-1,C-1,D-1; flow B21-PDTM-N008A-1, B-1, C-1, D-1; B21-PDTM-N009A-1, B-1, C-1, D-1)
- 4. Flow - High $ 40% of rated flow $ 40% of rated
( B21-PDTS-N006A-2, B21-PDTS-N007B-2 flow B21-PDTS-N008C-2, B21-PDTS-N009D-2) $ J5 d. Main Steam Line Tunnel $ 42" Temperature - High ~< 200 F < 200 F
~
$ -Y' (B21-TS-N010A,B,C,D; B21-TS-N011A,B,C,D; $ B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D) n us~ z LJ7 ,o ty, e. Condenser "acuum - Low > 7 inches Hg Vacuum 277 inches Hg ( B21-PTM-N0 5 6A-1, B-1, C-1, D-1) Vacuum l
- f. Turbine Building Area Temp. - High < 200 F < 200 F
~~
(B21-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; B21-TS-3227A,B,C,D; B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; B21-TS-3230A,B,C,D; B21-TS-3231 A, s, C, D and B21-TS-3232A, B,C,D)
I TABLE 3.3.2-2 (Continued) E ISOLATION ACTUATION INSTRUMENTATION SETPOINTS si ALIDWABLE y VALUE M TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT n
- 2. SECONDARY CONTAINMENT ISOLATION N <
U a. Reactor Building Exhaust Radiation - liigh _ 11 mr/hr i 11 mr/hr M (D12-RM-N010 A, B)
- b. Drywell Pressure - liigh $ 2 psig $ 2 psig l
(C7 2-PTM-N002A-1, B-1, C-1, D-1)
- c. Reactor Vessel Water Level - Low, Level #2 > -38 inches > -38 inches I
(B21-LTM-N024A-1, B-1 and B21-LTM-N025A-1, B-1) g 3. REACTOR WATER CLEANUP SYSTEM ISOLATION c-
- a. i 53 gal / min 1 53 gal / min y Zs Flow - liigh g (G 31 -d FS -N 603 -1 A , IB)
- b. Area Temperature - iligh $ 150 F < 150 F (G31-TS-N600A, B,C,D,E, F)
I
- c. Area Ventilation Temperature ts Temp - liigh 5 50 F $ 50 F (G31-TS-N602A, B, C, D, E, F)
- d. SLCS Initiation (C41A-SI) NA NA
$' c. Reactor Vessel Water - Low, Level #2 > -38 inches > -38 inches ! $ (B21-LTM-N024A-1, B-1 and B21-LIM-N025A-1, B-1) l g n a=> Z 4D*
-{-
W CB
I TABLE 3.3.2-2 (continued) N ISOLATION ACTUATION INSTRUMENTATION SETPOINTS I3 ALLOWABLE $ TRIP FUNCTION AND INSTRUMENT NUMBER TRIP _SETPOINT VALUE M
- 4. CORE STANDBY COOLING SYSTEMS ISOLATION N
U a. liigh Pressure Coolant Injection Isolation w
- 1. IIPCI Steam Line Flow - liigh 1 3007,of rated flow < 3007. of rated (E41-PDIM-N004-1 and E41-PDTM-N005-1) flow (E41-PDTS-N004-2 and E41-PDTS-N005-2)
- 2. IIPCI Steam Supply Pressure - Low > 100 psig >_ 100 psig (E41-PSL-!!001A, B, C, D)
- 3. IIPCI Steam Line Tunnel Temperature - liigh < 200 F S 2000 F t) ,
(E41-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; o E41-TS-3318; E41-TS-3354; E41-TS-3488 and E41-TS-3489) T g 4. Bus Power Monitor NA NA (E41-K55 and E41-K56)
- 5. IIPCI Turbine Exhaust Diaphragm Pressurc-Iligh i 10 psig < 10 psig
( E41 -PSit-N012A, B, C, D)
- 6. IIPCI Steam Line Ambient Temp. - liigh < 200 F < 200 F (E51-TS-N603C, D) 1 50 F 1 50 F
- 7. IIPri Steam Line Area oTemp. - liigh g.
m (851dTS-N604C, D) E. (E51-dTS-N604C, D) M S
- 8. Emergency Area Cooler Temp. - Iligh < 175 F
< 175 F
~
z #* (E41-TS-N602A, B) O 45= __g C N
I TABLE 3.3.2-2 (continued)
$5 g ISOLATION ACHIATION INSTRUMENTATION SETPOINTS I4 ALLOWABLE N TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE g b. Reactor Core Isolation Cooling System Isolation N
s,
- 1. RCIC Steam Line Flow - liigh { 3007,of rated flow 1 300% of rated (E51-PDTM-N0l7-1 and E51-PDRI-N018-1) flow (E51-PDTS-N017-2 and E51-PDTS-N018-2)
- 2. RCIC Steam Supply Pressure - Low > 50 psig > 50 psig (E51-PS-N019A, B, C, D)
- 3. RCIC Steam Line Tunnel Temp. - liigh 1 175 F i 175 F (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; u, E51-TS-3323; E51-TS-3355 and E51-TS-3487)
N u, 4. Bus Power Monitor NA NA
', (E51-K42 and E51-K43)
O
- 5. RCIC Turbine Exhaust Diaphragm Prc.=sure - Pigh (E51-PS-N012A, B, C, D) i 10 psig i 10 psig
- 6. RCIC Steam Line Ambient Temp. - liigh < 200 F 1 2000 F (E51-TS-N603A, B)
- 7. RCIC Steam Line Area o Temp. - liigh 1 50 F i 50 F (E51-dTS-N604A, B) i g __, 8. RCIC Equipment Room Ambient Temp. - liigh i 175 F $ 175 F g 43 (E51-TS-N602A, B) '
g z=.
-q2 9. RCIC Equipment Room o Temp. - liigh 1 50 F $ 50" F ,
y - (E51-dTS-N601 A, B) ; us-C33 ,
i TABLE 3.3.2-2 (continued) g 0 IS_01ATION ACTUATION INSTRUMENTATION SETPOINTS 1: ALLOWABLE [' TRIP FUNCTION AND INSTRUMENT NUMBER _ TRIP SETPOINT VALUE 9 h 5. SilUTDOWN COOLING SYSTD1 IS01ATION a y a. Reactor Vessel Water - Low, Level #1 > +12.5 inches
> +12.5 inches (B21-LTM-N017A-1, B-1, C-1, D-1) l
- b. Reactor Steam Dome Pressure - liigh i 140 psig < 140 psig (B32-PS-N018A, B)
M e Y E' B - W n B
- 9
.? ., W W
TABLE 3.3.2-3 ISOLATION SYSTEM RESPONSE TIME TRIP FUNCfION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)
- 1. PRIMARY CONTAINMENT ISOLATION
- a. Reactor Vessel Water Level - Low
- 1. Level #1
( B 21 -LT-N017 A-1, B-1, C-1, D- 1 ) B21-LTM-N017A-1, B-1, C-1, D-1 ) 5.13
- 2. Level #2 (B21-LT-N024A-1,B-1 and B21-LT-N025A-1,3-1)
(B21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) <1.0**
- b. Drywell Pressure - High (C72-PT-N002A,B,C,D)
C72-PTM-N002A-1,B-1,C-1,D-1) < 13
- c. Main Steam Line
- 1. Radiation - High*
(D12-RM-KC03A,B,C,D) $ 1. 0 **
- 2. Pressure - Low
( B 21- PT-N015A, B , C , D) (B21-PTM-N015A-1,B-1,C-1,D-1) 5.13
- 3. Flow - High (B21-PDT-N006A,B,C,D; B21-PDT-N007A , B , C , D; B21-PDT-N008A,B,C,D; B21-PDT-N009A,B,C,D)
(B21-PDTM-N006A-1,B-1,C-1,D-1; B21-PUIM-N00 7A-1, B-1, C-1, D-1 ; B21-PUIM-N008A-1,B-1,C-1,D-1; B21-PDTM-NC09A-1,B-1,C-1,D-1) <0.5**
- 4. Flow - High (B21-PDTS-N006A-2; B21-PDTS-N007B-2; B21-PDTS-N008C-2 ;
B21-PDTS-N009D-2) <.5** 144tP 560 BRUNSWICK - UNIT 2 3/4 3-22 An.endmen t No.
A++. _e. .. <e TEST TARGET (MT-3) 1,. A'+ I l.0 l;au an I e
- u. Ett En D
l,l b_N_ O8 1.25 1.4 1.6
< 6,, ,
#4 '4
+4%
A
- g,777f I
#q^^,,
i 0"
9 o
%er A><4>> //g f.
~$
$g,N, b*'*
%'>++ > , _ . .. < e -
%44<
TEST TARGET (MT-3) 1.0 5 E4 EM n y @ EE I.i ['a HM L8 l 1.25 'j' l.4 1.6
< 6- . #*r4 ' +4%
'it$Vh/ bi 1+}V 2 V> I a
4 4 '*kk'
'$$l<,
TEST TARGET (MT-3) 1.0 E DE IIM
~ y @ I!OE I.l y," EB l.8 1.25 1.4 1.6 l
4 6" 9
! b h'*/ OO
;! e
+%fif' Op k<t,;y&
TABLE 3.3.2-3 (Continued) ISOLATION SYSTEM RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TINE (Seconds)
- 1. PRIMARY CONTAINMENT ISOLATION (Continued)
- d. Main Steam Line Tunnel Temperature - High $13 (B21-TS-N010A,B,C,D; B21-TS-N011A,B,C,D; B21-TS N012A, B,C, D and B21-TS-N013A, B,C, D)
- e. Condenser Vacuum - Low (B21-PT-N056A,B,C,D)
(B21-PTM-N056A-1,B-1,C-1,D-1) $13
- f. Turbir.e Building Area Temperature - High NA (B21-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; B21-TS-3227A,B,C,D; B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; B21-TS-3232A,B,C,D)
- 2. SECONEARY CONTAINMENT ISOLATION
- a. Reactor Building Exhaust Rac 'stion - High * $_13 (D12-RM-N010A,B)
- b. Drywell Pressure - High (C72-PT-N002A,B,C,D)
(C72-PTM-N002A-1,B-1,C-1,D-1) 5,13
- c. Reactor Vessel Water Level - Low, Level #2 (B21-LT-N024A-1,B-1 and B21-LT-N025A-1,B-1)
(B21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) 1(1.0** f4 W 00l MM BRUNSWICK - UNIT 2 3/4 3-22A Amendment No.
TABLE 3. 3. 2-3 (Continued) ISOLATION SYSTEM RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)
- 3. REACTOR WATER CLEANUP SYSTEM ISOLATION
- a. 21 Flow - High G31-dFS-N603-1A,lB) 113
- b. Area Temperature - High 113 (G31-TS-N600A, B , C , D, E , F)
- c. Area Ventilation Temperature Zh T - High 113
( C31-TS-N602 A,B , C , D,E , F)
- d. SLCS Initiation (C41A-S1) NA
- e. Reactor Vessel Water - Low, Level #2 (B21-LT-N024A-1,B-1 and B21-LT-N025A-1,B-1)
B21-LTM-N024A-1,B-1 and B21-LTM-N025A-1,B-1) <l.0**
- 4. CORE STANDBY COOLING SYSTEFG ISOLATION
- a. High Pressure Coolant Injection Isolation
- 1. HPCI Steam L'ne Flow - High
, (E41-PDT-N004 and E41-PDI-N005)
/ (E41-PDTM-N004-1 and E41-PDTM-N005-1) 1,13 (E41-PDTS-N004-2 and E41-PDTS-N005-2)
- 2. HPCI Steam Supply Pressure - Low 113 (E41-PSL-N00L4, B, C, D?
- 3. HPCI Steam Line Tunnel Temperature - High $13 (E41-TS-3314; L41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488 and E41-TS-3489)
- 4. Bus Power Monitor (E41-K55 and E41-K56) NA
- 5. HPCI Turbine Exhaust Diaphragm Pressure - High NA (E41-PSH-N012A, B, C, D)
- 6. HPCI Steam Line Ambient Temperature - High NA (E51-TS-N603C,D)
- 7. HPCI Steam Line Area /1 Temp - High NA (E51-dTS-N604C,D)
- 8. Emergency Area Cooler Temperature - High NA (E41-TS-602A, B) 1445 002 BRUNSWICF. - UNIT 2 3/4 3-23 Amendment No.
TABLE 3.3.2-3 (Continued) ISOLATION SYSTEM RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)
- b. Reactor Core Isolation Cooling System Isolation
- 1. RCIC Steam Line Flow - High (E51-PDT-N017 and E51-PDT-N018)
(E51-PDTM-N017A-1 and E51-PDTM-N018A-1) NA (E51-PDTS-N017A-2 and E51-PDTS-N018A-2)
- 2. RCIC Steam Supply Pressure - Low NA (E51-PS-N019A,B,C,D)
- 3. RCIC Steam Line Tunnel Temp - High NA (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; E51-TS-3323; E51-TS-3355 and E51-TS-3487) 4 Bus Power Monitor (E51-K42 and E51-K43) NA
- 5. RCIC Turbine Exhaust Diaphram Pressure - High NA (E51- PS-N012A, B , C , D)
^
- 6. RCIC Steam Line Ambient Temperature - High NA (E51-TS-N603A,B)
- 7. RCIC Steam Line Area o Temp - High NA (E51-dTS-N604A,B)
- 6. Emergency Area Cooler Temperature - High NA (E51-TS-N602A,B)
- 9. RCIC Equipment Room o Temp - High NA (E51-dTS-N601A,B)
- 5. SHUTDORN COOLING SYSTEM ISOLATION
- a. Reactor Vessel Water Level - Low, Level #1 (Bil-LT-N017A-1,B-1,C-1,D-1) NA (B21-LTM-N017A-1,B-1,C-1,D-1)
- b. Reactor Steam Dome Pressure - High NA (B32-PS-N018A,B)
- Radiation monitors are exempt from response time testing.
Response time shall be measured from detector output or the input of the firs t electronic component in the channel.
** Isolation actuation ins trumentation response time only.
BRUNSWICK - UNIT 2 3/4 3-24 Amendment No. 1445 003
TABLE 4. 3'. 2-1 ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS
% CilANNEL OPERATIONAL @ CilANNEL FUNCTIONAL CIIANNEL CONDITIONS IN WlIICil l@ SURVEILLANCE REQUIRED g TRIP FUNCTION AND INSTRUMENT NUMBER CIIECK TEST CALIBRATION
- r.
8
- 1. PRIMARY CONTAINMENT ISOLATION k
y a. Reactor Vessel Water Level - Low w 1. Level #1 (B21-LT-N017A-1,B-1,C-1,D-1) NA(a) NA R(b) (B21-LTM-N017A-1,B-1,C-1,D-1) D M M 1, 2, 3
- 2. Level #2 (B21-LT-N024 A-1, B-1 and NA(8) NA R(b)
B21-LT-N025A-1,B-1) (B21-LTM-N024A-1, r -1 and D M M 1, 2, 3 B")1-LTM-N025A-1,B-1)
" b. Drywell Pressure - liigh * (C 72-PT-N002 A, B: C , D) NAI *} NA R (C72-PTM-N002 A-1, B-1, C-1, D-1) D M M 1, 2, 3 w ?> " c. Main Steam Line
- 1. Rad ia t i on - lii gh
( D12-RM-K603 A , B , C, D) D W R 1, 2, 3 1
- 2. Pressure - Low )
( B 21 - PT-N015 A, B , C , D) NA(a) NA R , ( B21 -PTM-N015 A-1, B-1, C- 1, D-1) D M M i i
- 3. Flow - liig;i
- (B21-PUr-N006A,B,C,D; NA " NA R i @ A B21-PDT-N007A,B,C,D; 4 B21-PDT-N008A,B,C,D; !
U B21-PUr-N009A,B,C,D) to ( B 21-P UrM-N006 A-1, B-1, C-1, D-1 ; D M M 1 < $ 4 B21-PUrM-N007A-1,B-1,C-1,D-1; B21-PUrM-N008 A-1, B-1, C-1, D-1 ; B21-PUTM-N009A-1,B-1,C-1,D-1) {
TABLE 4. 3. 2-1 (Continued)
$ ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREFENTS E
y CHANNEL OPERATIONAL M CHANhEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION AND INSTRUFENT NUMBER CHECK TEST CALIBRATION Sf.dEILLANCE REQUIRED E 1. PRIMARY CONTAINMENT ISOLATION (Continued) U y c. Main Steam Line (Continued)
- 4. Flow - High (B21-PDTS-N006A-2; B21-PDTS-N007B-2; B21-PDTS-N008C-2; B21-PDTS-N009 D-2) D M M 2, 3 w d. Main Steam Line Tunnel 3: Temperature - High NA M R 1,2,3 (B21-TS-N010A,B,C,D; B21-TS-N011A,B,C,D; B21-TS-N012A,B,C,D and B21-TS-N013A,B,C,D)
Y D$ e. Condenser Vacuum - Low
> (B21-PT-N056A,B,C,D) NA(a) NA R(b)
(B21-PTM-N056A-1,B-1,C-1,D-1) D M M 1, 2#
- f. Turbine Building Area Temp - High NA M R 1, 2, 3 (B21-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; B21-TS-3227A,B,C,D; B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; B21-TS-32 30A, B, C, D; B21-TS-3231 A,L , C, D and B21-TS-32 32A, B, C, D) 4d-3 a 43~
{ 9 LJ7 Q C" ) n CE) y LJ7
# When reactor steam pressure >500 psig.
i-TABLE 4.3.2.-1 (Continued) ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS en
- CilANNEL OPERATIONAL CllANNEL FUNCTIONAL CIIANNEL CN DITIONS IN WilICH h SUh'YC ' ' ANCE REQUIRED CIIECK TEST CALIBRATION
$ TRIF FUNCTION AND INSTRUMENT NUMBER O
, . SECONDARY CONTAINMENT ISOLATION
- a. Reactor Building Exhaust H Radiation - liigh D M R 1, 2, 3, 5 and *
(D12-RM-N010A,B)
- b. Drywell Pressure - Iligh (C72-PT-N002A,B,C,D) NA NA R (C72-PTM-N002A-1,B-1,C-1,D-1) D M M 1,2,3
- c. Reactor Vessel Water Level - Low, Level #2 }
(B21-LT-N024A-1,B-1 and NA(a) NA R w ) B21-LT-N025A-1,B-1) (B21-LTM-N024A-1,B-1 and D M M 1, 2, 3 w B21-LTM-N025A-1,B-1)
- 3. REACTOR WATER CLEANUP SYSTEM IS01ATION D M R 1, 2, 3
- a. A Flow - liigh (C31-dFS-N603-1A,1B)
Area Temperature - liigh NA M R 1, 2, 3 b. A ( G31 -TS-N604 A, B , C, D,E , F) W4 k c. Area Ventilation A Temp - R 1, 2, 3 @g liigh (G31-TS-N602A, B,C, D,E , F) NA H S cD E
*When handling irradiated fuel in the secondary containment.
TABLE 4.3.2-1 (Cbntinued) ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS N C11ANNEL OPERATIONAL E! CIIANNEL FUNCTIONAL CilANNEL CONDITIONS IN WHICll U TRIP FUNCTION AND INSTRUMENT NUMBER CilECK TEST CALIBRATION SURVEILLANCE REQUIRED M
- 3. REACTOR WATER CLEANUP SYSTEM ISOLATI_0N (continued)
Q d. SLCS Initiation (C41A-SI) NA R NA 1,2,3 to
- e. Reactor Vessel Water Level -
Low, Level #2 (B21-LT-N024A-1,B-1 and NA ,) NA R 321-LT-N025A-1,B-1) (B21-LTM-N024A-1,B-1 and D M M 1,2,3 B21-LTM-N025A-1,B-1) t' n h a it a- "n $b Ls, C-.) C N
3 TABLE 4.3.2-1 (bontinued) ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREFENTS $ CIIANNEL OPERATIONAL y CilANNEL FUNCTIONAL CilANNEL CCONDITIONS IN WilICil y TRIP FUNCTION AND INSTRUMENT NUMBER CIIECK TEST CALIBRATION SURVEILLANCE REQUIRED n
' 4. CORE STANDBi cdOLING SYSTEMS ISOLATION E
y a. liigh Pressure Coolant Injection Isolation m
- 1. IIPCI Steamline Flow - liigh (E41-PDT-N004 and E41-PDT-N005) NA("} NA R( l (E41-PDIM-N004-1 and E41-PI7FN-N005-1) D M M 1, 2, 3 (E41-PDrS-N004-2 and E41-PDTS-N005-2) u, 2. IIPCI Steam Supply Pressure -
Low NA M R 1, 2, 3 3: (E41-PSL-N001A,B,C,D) u, 3. IIPCI Steamline Tunnel
- Tempe rature - liigh NA M Q 1, 2, 3
(E4i-TS-3314; E41-TS-3315; E41-TS-3316; E41-TS-3317; E41-TS-3318; E41-TS-3354; E41-TS-3488 and E41-TS-3489)
- 4. Bus Power Monitor NA R NA 1,2,3 (E41-K55 and E41-K56)
- 5. IIPCI Turbine Exhaust Diaphragm Pressure - liigh NA M Q 1, 2, 3
( E41 - PSil-N012 A , B, C , D)
- 6. IIPCI Steam Line Ambient Temp - liigh NA M R 1,2,3 f
R 7. (E51 -TS-N603C , D) IIPCI Steam Line Area
" 1, 2, 3 g A Temp - liigh NA M R g j(( 8.
(E 51 -dTS-N604 C , D) Emergency Area Cooler 2 ty) 0 Temp - High NA M Q 1, 2, 3 c_, (E41-TS-N602A,B) CD CO
r TABLE 4. 3. 2_-1 (Continued) ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS _ % CIIANNEL OPERATIONAL y CllANNEL FUNCTIONAL C5tANNEL CONDITIONS IN WilICH g TRIP FUNCTION AND INSTRUMENT NUMBER CllECK TEST CAL I&'ATION SURVEILLANCE REQUIRED r. 8 b. Reactor Core Isolation g Cooling System Isolation U
- 1. RCIC Steamline Flow - liigh (E51-PDT-N017 and E51-PDT-N018) NA(a) NA R(b)
(E51-PImi-N017A-1 and E51-PDTM-N018A-1) D M M 1. 2, 3 (E51-PDTS-N017A-2 and E51-PDTS-N018A-2)
- 2. RCIC Steam Supply Pressure - Low NA M Q 1, 2, 3
)h (E51-PS-N019A,B,C,D)
- 3. RCIC Steamline Tunnel liigh Temperature NA M R 1,2,3
- (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; E51-TS-3323; os E51-TS-3355 and E51-TS-3487)
- 4. Bus Power Monitor NA R NA 1,2,3 (E51-K42 and E51-K43)
- 5. RCIC Turbine Exhaust Diaphragm Pressure - liigh NA M R 1, 2, 3 (E51-PS-N012A,B,C,D)
- 6. RCIC Steam Line Ambient Temp - liigh NA M R 1, 2, 3 (E51-TS-N603A,B)
- 7. RCIC Steam Line Area
- A Temp - liigh NA M R 1, 2, 3 g 43, (E51-dTS-N604A,B) g 43, 8. RCIC Equipment Room Ambient D Ln Temp - liigh NA M Q 1, 2, 3 ,
(E51-TS-N602A,B) ,o O 9. RCIC Equipment Room A C3 Temp - Iligh NA M Q 1,2,3
'43 (E51-dTS-N601A,B)
i TABLE 4.3.2-1 (Continued) ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS N OPERATIONAL
@ CilANNEL y] CilANNEL FUNCTIONAL C11ANNEL CONDIT'""S IN WilICil y TRIP FUNCTION AND INSTRUMENT NUMBER CllECK TEST CALIBRATION SURVEILLANCE REQUIRED n ' 5. SilUTDOWN COOLING SYSTEM ISOLATION h
y a. Reactor Vessel Water - Low, y Level #1 ( B 21-LT-N017 A-1, B-1, C-1, D-1 ) NA NA R(b) (B21-LTM-N017A-1,B-1,C-1,D-1) D M M 3,4,5
- b. Reactor Steam Dome Pressure
.tigh (B32-PS-N018A,B) NA S/U*, M R 1,2,3 t'
n Y
- If not performed within the previous 31 days.
(a) The transmitter channel check is satisfied by the trip unit channel check. A separate transmitter check is not required. (b) Transmitters are exempted f rom the monthly channel calibration.
- g. _ _ _
8 am, 0 4h> z LJ7 C., a
i TABLE 3.3.3-1 % EMERGENCY CORE COOLING SYSTEM ACHIATION INSTRUMENTATION MINIMUM NUMBER APPLICABLE OPERABLE CllANNELS OPERATIONAL n TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM CONDITIONS 7 E y 1. CORE SPRAY SYSTEM w
- a. Reactor Vessel Water Level - Low, Level #3 (B21-LT-NO31A, B, C, D)
(B21 -LTS-NO31 A-3, B ~ , C-3, D-3 ; B21-LTS-NO31 A-4, 2 1,2,3,4,5 B-4, C-4, D-4 )
- b. React- Steam Dome Pressurc - Lcw (Injection Permissive)
(B21-PT-N021A, B, C, D) (B21-PIM-N021 A-1, B-1, C-1, D-1) 2 1,2,3,4,5 (B21-PTS-NO21A-2, B-2, C-2, D-2) v2 30 c. Drywell Pressure - liigh u> (Ell-PT-N0ll A, B, C, D) da 2 1,2,3 " (E11 -PTM-N011 A- 1,B-2, (E11-PTS-N011A-2, B- 1,C-2, C- 1,D-2 D-1))
- d. Time Delay Relay 1 1,2,3,4,5
- e. 3us Power Monitor #(E21-KIA, B) 1/ bus 1,2,3,4,5
- 2. LPCI MODE OF RilR SYSTEM
__, a . Drywell Pressure - liigh 43, (E11-PT-N011A, B, C, D)
- 43. (E11-PTM-N011A-1, B-1, C-1, D-1) 2 1,2,3 g LJ7 0
0 C_s b. Reactor Vessel Water Level - Low, Level #3 (B21-LT-NO31A, B, C, D) ,5
~~~
(B21-LTS-NO31A-3, B-3, C-3, D-3) 2 1,2,3,4*5* (B21-LTS-NO31A-4, B-3, C-3, D-3)
*Not as.11 cable u 2en two core spray system subsystems are OPERABLE per Speci fication 3.5.3.1.
# Alarm Only. Whci inoperable, verify power availab1!ity to the bus at least once per 12 hours.
F w TABLE 3.3.3-1 (continued) E Z EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUME"TATION g MINIMUM NUMBER APPLICABLE OPERABLE C11ANNELS OPERATIONAL h TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM CONDITIONS H w 2. LPCI MODE OF RilR SYSTEM (continued)
- c. Reactor Vessel Shroud Level (Drywell Spray Permissive)
(B21-LT-NO36 and B21-LT-NO37) (B21-LTM-N036-1 and B21-LTM-N037-1) 1 1, 2, 3, 4*, 5*
- d. Reactor Steam Dome Pressure - Low (Injection Per-missive)
(B21-PT-N021A, B, C, D) (B21-PTM-N021A-1, B-1, C-1, D-1) (B21-PTS-N021A-2, B-2, C-2, D-2) h 1. RilR Pump Start and LPCI Injection Valve Actuation 2 1, 2, 3, 4*, 5* g 2. Recirculation Loop Pump Discharge Valve Actuation 2 1, 2, 3, 4*, 5* O y -'*
- e. RilR Pump Start - Time Delay Relay 1 1, 2, 3, 4*, 5*
4
"* Bus Power Monitor # (Ell-K106A, B)
- p
- f. 1/ bus 1, 2, 3, 4*, 5*
C) s N @ *Not applicable when two core spray system subsystems are OPERABLE per Specification 3.5.3.1. @ #Alann only. When inoperable, verify power availability to the bus at least once per 12 hours. n
TABLE 3.3.3-1 (continued) tzs EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION v 6 MINIMUM NUMITER APPLICABLE p .1 OPERABLE CllANNEL's OPERATIONAL @ TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM CONDITIONS
- 3. IIPCI SYSTEM s
H
- a. Reactor Vessel Water Level - Low, Level #2 (B21-LT-NO31A, B, C, D)
(B21-LTM-NO31A-1, B-1, C-1, D-1; B21-LTS-NO31A-2, 2 1,2,3 l B-2, C-2, D-2) l
- h. Drywell Pressure - liigh (Ell-PT-NollA, B, C, D)
(E11-PIM-N011A-1, B-1, C-1, D-1, E11-PTS-N011A-2, 2 1,2,3 B-2, C-2, D-2) f c. Condensate Storage Tank Level-Low ** (E41-LS-N002, NA* 1,2,3 g E41-LS-N003) di u d. Suppression Chamber Water Level-liigh** (E41-Ld..- , N015A, B) NA* 1,2,3 ,
- c. Bus Power Monitor # (E41-K55 and E41-K56) 1/ bus 1, 2, 3
- 4. ADS
-C::=
- g. Drywell Pressure - liigh, coincident with w (E11-PT-N010A, B, C, D) 2 1,2,3 (E11-PTM-N010A-1, B-1, C-1, D-1)
D -4r. Reactor Vessel Water Level - Low, Level #3 f u (B21-LT-NO31A, B, C, D) 2 1, 2, 3 D, (B21-LTS-NO31A-3, B-3, C-3, D-3; B21-LTS-NO31A-4, B-4, C-4, D-4) z
# Alarm only. When inoperable, verify power availability to the bus at least once per 12 hours.
- When either channel of the automatic transfer logic is in operable, align llPCI pump suction to the suppression pool.
**Provides signa! to llPCI pump suction valves only.
TABLE 3.3.3-1 (continued) $ EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION 2 MINIMUM NUMBER APPLICABLE $ OPEEABLE CilANNELS OPERATIONAL . TRIP FUNCTION AND INSTRUMENT NUMBER PER_ TRIP SYSTEM CONDITIONS E 4. ADS (continued) U N c. ADS Timer (B21-TDPU-KSA, B) 1 1,2,3
- d. Core Spray Pump Discharge Pressure - Iligh (Permissive) 2 1,2,3 (E21-PS-N008A, B and E21-PS-N009A, B)
- e. RllR (LPCI Mode) Pump Discharge Pressure - liigb(Per-missive) 2/ pump 1,2,3 (E11-PS-N016A, B, C, D and E11-PS-N020A, B, C, D)
- f. Bus Power Monitor # (B21-KlA, B) 1/ bus 1, 2, 3 M
v~ y __. U 45= p- as, LT1 Q 42:= k 8 B- -- $ # Alarm only. When inoperable, verify power availability to the bus at least once per 12 hours. f
i TABLE 3.3.3-2 $ DIERCENCY CORE C00LINC SYSTEM ACTUATI , INSTRUMENTATION SETPOINTS E ALLOWABLE h TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE g
- 1. CORE SPRAY SYSTEM E
y a. Reactor Vessel Water Level - Low, Level #3 > -147.5 inches > -147.5 inches N (B21-LTS-NO31A-3, B-3, C-3, D-3; B21-LTS-NO31A-4, B-4, C-4, D-4)
- b. Reactor Steam Dome Pressure - Low (B21-PTS-N021A-2, B-2 , C-2, D-2 ) 410 1 15 psig 410 1 15 psig 1 2 psig i 2 psig
- c. Drywell Pressure - liigh (Ell-PTS-N011 A- 2, B-2, C- 2, D-2)
M c~
- d. Time Delay Relay 14 i t 5 16 secs 14 $ t 5,16 secs u,
l> NA NA
- e. Bus Power Monitor (E21-K1A, B)
D 2. LPCI MODE OF RHR SYSTDI
-P::= 'J'
- a. Drywell Pressure - High i 2 psig i 2 psig c._ ,
(Ell-PIM-N011A-1, B-1, C-1, D-1) Ln > -147. 5 inches
- b. Reactor Vessel Water Level - Low, Level #3 2 -147.5 inches y (B21-LTS-NO31A-3, B-3, C-3, D-3; B21-LTS-NO31A-4, B-4,
@ C-4, D-4)
$ & 39" below TAE* 2 39" below TAF*
g c. Reactor Vessel Shroud Level l
" (B21-LTM-NO36-1 and B21-LTM-NO37-1)
- Top of the active fuel.
/
I TABLE 3.3.3-2 (continued) EMERGENCY CORE C00Lli,0 SYSTEM ACTUATION INSTRUMENTATION SETPOINTS g E ALLOWABLE cq b TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT VALUE R - e d. Reactor Steam Dome Pressure - Low E! y 1. RilR Pump Start and LCPI Injection Valve Actuation (B21-PTS-N021A-2, B-2, C-2, D-2) 410 15 psig 410 1 15 psig l
- 2. Recirc ilation Pump Discharge Valve Actuation (B21-PTM-N021A-1, B-1, C-1, D-1) 310 1 15 psig 310 1 15 psig l
- e. RilR Pump Start - Time Delay Relay 9<t< 11 seconds 9<t< 11 seconds
- f. Bus Power Monitor (E11-K106A, B) NA NA M>
W b
@ 42. @ LJ7 a
n c> x --
. C7s
TABLE 3.3.3-2 (continued) E g EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS
?! ALLOWABLE s
O TRIP FUNCTION AND INSTRUMFNT NUMBER TRIP SETPOINT VALUE g 3. IIPCI SYSTEM s
- a. Reactor Vessel Water Level - Low, Level #2 2 -38 inches 2 -38 incnes (B21-LDi-NO31A-1, B-1, C-1, D-1 and B21-LTS-NO31A-2, B-2, C-2, D-2)
- b. Drywell Pressure - Iligh < 2 psig i 2 psig (E11-PTM-N011A-1, B-1, C-1, D-1 and E11-PTS-N011A-2, B-2, C-2, D-2)
- c. Condensate Storage Tank Level - Low > 23'4"
> 23'4" (E41-LS-N002, E41-LS-N003) $ d. Suppression Chamber Water Level - liigh* < -2 feet < -2 feet ;, (E41-LSil-N015A, B) s.n
- e. Bus Power Monitor (E41-K55 and E41-K56) NA NA
- 4. ADS
- a. Drywell Pressure - liigh 1 2 psig i 2 psig (E11-PDI-U010A-1, B-1, C-1, D-1) !
A Pg b. Reactor Vessel Water Level - Low, Level #3 > -147.5 inches 2 -147.5 inches A (B21-LTS-NO31A-3, B-3, C-3, D-3 and W @g B21-LTS-NO31-A-4, B-4, C-4, D-4) b c. ADS Timer (B21-TDPU-K5A, B) $_ 120 seconds i 120 seconds N 5 *
- d. Core Spray Pump Discharge Pressure - Iligh 2 100 psig 2 100 psig (E21-PS-N008A, B nnd E21-PS-N009A, B)
- e. RllR (LPCI Mode) Pump Discharge Pressure - liigh > 100 psig
> 100 psig
( E il -PS -N016A , B, C, D and Ell-PS-N020A, B, C, D)
- Suppression chamber water level zero is the torus centerline minus 1 inch.
E L BE AU WL OA A LV N L A S T N I O P T E T S N I N O O P I T T E A S A T N N P
) E I d M R e U T.
u R n T i S t N n I o C N ( O I 2 T I - A 3 U T 3 C A 3 f f E E L T B S A Y T S G N I ) L B O O C g B A I E l l K R U - O " 1 C 2 T B Y N ( C E N M r E U o G R t R T i E S n I N o D I ) M d D e r N u e A n w i o N t P O n I o s T c u C ( B N U S E D A f wP,u O & P I R . T 4
,xNhR , hs o t n a> .
ao?P, zO.
i TABLE 4.3.3-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS m CHANNEL OPERATIONAL un CliANNEI, FUNCTIONAL CllANNEL CONDITIONS IN WilICil I! TRIP FUNCTION AND INSTRUMEN1 NUMBER CllECK TEST CALIBRATION SURVEILLANCE REQUIRED R e 1. CORE SPRAY SYSTEM E s a. Reactor Vessel Water Level - Low, ( B21 -LT-N031 A, B , C , D) NA(a) NA R(b) (B21-LTS-N031A-3,B-3,C-3,D-3) D M M 1,2,3,4,5 ( B 21-LTS-NO 31 A-4, B-4, C-4, D-4 ) D M M
- b. Reactor Steam Dome Pressure -
R I} B21-PT-N021A,B,C,D) NA NA w (B21-PTM-N021A-1,B-1,C-1,D-1) D M M 1, 2, 3,4,5 30 (B21-PTS-N021A-2,B-2,C-2,D-2) D M M
- c. Drywell Pressure - Illgh
-a ( E l l - PT-N0l l A , B , C , D) NA ) NA R b)
(Ell-PTM-N0llA-1,B-1,C-1,D-1) D M M 1, 2, 3 (Ell-PTS-N011A-2,B-2,C-2,D-2) D M M
- d. Time Delay Relay NA R R 1,2,3,4,5
- e. Bus Power Monitor (E21-KIA,B) HA R NA 1, 2, 3, 4, 5
- 2. LPCI MOIE OF RilR SYSTEM A @* a. Drywell Pressure - liigh 4"'
@ (Ell-PT-N011A,B,C,D) NA(a) NA R(b)
{ (E 11-PTM-N011 A-1, B-1, C-1, D-1) D M M 1, 2, 3 c>R "z NC) O (a) The transmitter channel check is satisfied by the trip unit channel check. A separate transmitter check is not required. (b) Transmitters are exempted from the monthly channel calibration.
I TABLE 4.3.3.-1 (Continued) EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE RT)UIREMENTS E CilANNEL OPERATIONAL E CllANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICll E TRIP FUNCTION AND INSTRUMENT NUMBER CllECK TEST CALIBRATION SURVEILLANCE REQUIRED 7:
- 2. LPCI MODE OF RHR SYSTEM (Continued)
E y b. Reactor Vessel Water Level - Low, N Level #3 ( B 21 -LT-NO 31 A , B , C , D) NA(a) NA R(b) (B21-LTS-N031A-3,B-3,C-3,D-3) D M M 1, 2, 3, 4* , 5* ( B21 -LTS-N031 A-4, B-4, C-4, D-4) D M M
- c. Reactor Vessel Shroud Level (B21-LT-N036; B21-LT-N037) NA NA R w (B21-LTM-N036-1 a.id D M M 1, 2, 3, 4*, 5*
3 B21-LTM-N037-1) R d. Reactor Steam Dome Pressu re - Low
$ (B21-PT-N021A,B,C,D) NA(a) NA R(b) l
> 1. PHR Pump Start and LPCI Injection Valve Actuation i (B21-PTS-N021A-2,B-2,C-2,D-2) D M M 1, 2, 3, 4*, 5* I
- 2. Recirculatian Loop Pump Discharge Valve Actuation, i (B21-PTM-N021A-1,B-1,C-1,D-1) D M M 1, 2, 3, 4*, 5* I A e. RHR Pump Start-Time Delay Relay NA R R 1, 2, 3, 4*, 5*
Bus Power Monitor (E11-K106A,B) NA R N 1, 2, 3, 4* , 5* g f. 8 C. > " N o N
- Not applicable when two core spray system mubsystems are OPERABLE per Specification 3.5.3.1.
2:
. (a) The transmitter channel check is satisfied by the trip unit channel check.
A separate transmitter check is not required. (b) Transmitters are exempted from the monthly channel calibration.
TABLE 4.3.3.-1 (Continued) EMERGENCY CORE COOLING SYSTEM ACTUATICN INSTRUMENTATION EURVEILLANCE REQUIREMENTS
- n CIIANNEL OPERATIONAL h CIIANNEL FUNCTIONAL CIIANNEL CONDITIONS IN WilICil
]g TRIP FUNCTION AND INSTRUMENT NUMBER CllECK TEST CALIBRATION SURVEILLANCE REQUIRED
- 3. IIPCI SYSTEM E
O a. Reactor Vessel Water Level - Low N Level #2 ( B21-LT-NO 31 A , B , C , D) NA(a) NA R(b) l (B21-LTM-NO31A-1,B-1,C-1,D-1) D M M 1, 2, 3 (B21-LTS-NO31A-2,B-2,C-2,D-2) D M M ,
- b. Drywell Pressure - liigh (E11-PT-N011A,B,C,D) NA(8) NA R(b)
(E11-PTM-N011A-1,B-1,C-1,D-1) D M M 1, 2, 3 p (E11-ITS-N011A-2,B-2,C-2,D-2) D M M y c. Condensate Storage Tank Level Low (E41-LS-N002, E41-LS-N003) M 1, 2, 3 g NA Q
- d. Suppression Chamber Water Level -
liigh (E41-LSil-N015A, B) NA M Q 1, 2, 3
- e. Bus Power Monitor (E41-K55 and NA R NA 1, 2, 3 E41-K56)
- 4. ADS D=f g a. Drywell Pressure - liigh
- p. ( E 11-PT-N010A , B , C , D) NA NA R(b)
(E11-PTM-N010A-1,B-1,C-1,D-1) D M M 1, 2, 3 7 - (a) The transmitter channel check is satisfied by the trip unit channel check. A separate transmitter check is not required. (b) Transmitters are exempted from the monthly channel calibration.
i TABLE 4. 3. 3-1 (Continued)
, EMERGENCY CORE COOLIt'C SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS w
h CllANNEL OPERATIONAL ,
$ CIIANNEL FUNCTIONAL CilANNEL CONDITIONS IN WilICil g TRIP FUNCTION AND INSTRUMENT NUMBER CilECK TEST CALIBRATION SURVEILLANCE REQUIRED '
- 4. ADS (Continued)
E U b. Reactor Vessel Water Level - Low, M Level #3 (B21-LT-NO31A,B,C,D) NA(a) NA R(b) (B21-LTS-NO31A-3,B-3,C-3,D-3) D M M 1,2,3 ( B21 -LTS-NO31 A-4, B-4, C-4, D-4 D M M
- c. ADS Timer (B21-TDPU-KSA,B) NA R R 1,2,3
- d. Core Spray Pump Discharge 3: Pressure - liigh NA M Q 1, 2, 3 (E21-PS-N008A,B and y E21-PS-N009A,B) w
$ e. RilR (LPCI MODE) Pump Discharge Pressure - liigh NA M Q 1, 2, 3 (E11-PS-N016A,B,C, D and E11-PS-N020A,B,C,D)
- f. Bus Power Monitor (B21-K1A,B) NA R NA 1, 2, 3 4:=
y m 42- E. ! LJ7 g a C> ps) y (a) The transmitter channel check is satisfied by the trip unit channel check. rs) - A separate transmitter check la not required. l (b) Transmitters are exempted frota the monthly channel calibration, i
TABLE 3. 3. 5. 3-1 POST-ACCIDENT MONITORING INSTRUMENTATION MINIMUM NO. OF OPERABLE INSTRUMENT INSTRUMENT AND INSTRUMENT NUMBER CHANNELS
- 1. Reactor Vessel Water Level 2 (B21-LITS-N026A,B; B21-LR-615; E21-LI-R604A,B; B21-LT-N037 and B21-LTM-N037-1) l
- 2. Reactor Vessel Pressure 2 (B21-PI-R004A,B; C32-LPR-R608 and C32-PT-N005A,B)
- 3. Containment Pressure 2 (CAC-PI-2599 ; CAC-PT-2599; CAC-PR-1257-1 and CAC-PT-1257-1)
- 4. Containment Pressure 2 (CAC-TR-1258-1 thru 13,22,23,24 and C91-P602)
- 5. Suppression Chamber Atmosphere Temperature 2 (CAC-TR-1258-17 thru 20 and C91-P602)
_ 6. Suppression Chamber Water Level 2 (CAC-LI-2601-3; CAC-LR-2602; CAC-LT-2601; CAC-LT-2602 and CAC-LY-2601-1) ~
- 7. Suppression Chamber Water Temperature 2 (CAC-TR-1258-14, 21 and C91-P602)
- 8. Containment Radiation 2 (CAC-AR-1260; CAC-AQH-1260-1,2,3; CAC-AR-1261; CAC-AQH-1261-1,2,3; CAC-AR-1262 and CAC-AQH-1262-1,2,3)
- 9. Containment Oxygen 2 (CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2 and CAC-AR-1263)
- 10. Containment Hydrogen 2 (CAC-AT-1959-1; CAC-AR-1259; CAC-AT-1263-1 and CAC-AR-1263)
BRUNSWICK - UNIT 2 3/4 3/51 Amendment No. 1445 J23
i r I TABLE 4. 3. 5. 3- 1 , POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS m E CllANNEL CIIANNEL E INSTRUMENT AND INSTRUMENT NUMBER CllECK CALIBRATION 5
- 1. Reactor Vessel Water Level M R (B21-LITS-N026A,B; B21-LR-R615; B21-LI-R604A,B; '
E B21-LT-NO37 and B21-LTM-NO37-1) l s M 2. Reactor Vessel Pressure M R (B21-PI-R004A,B; C32-LPR-R608 and C32-PT-N005A,B) ,
- 3. Containment Pressure M R a (CAC-PI-2599; CAC-PT-2599; CAC-PR-1257-1 and CAC-PI-1257-1)
- 4. Containment Temperature M R (CAC-TR-1258-1 thru 13,22,23,24 and C91-P602)
M e 5. Suppression Chamber Atmosphere Temperature M R
, (CAC-TR-1258-17 thru 20 and C91-P602)
- 6. Suppression Chamber Water Level M R (CAC-LI-2601-3; CAC-LR-2602; CAC-LT-2601; CAC-LT-2602 and CAC-LY-2601-1) ,
- 7. Suppression Chamber Water Temperature M R (CAC-TR-1258-14, 21 and C91-P602)
- 8. Containment Radiation M R (CAC-AR-1260; CAC-AQll-1260-1,2,3; CAC-AR-1261; CAC-AQil-1261-1,2,3; CAC-AR-1262 and CAC-AQll-1262-1,2.3) l fg 9. Containment Oxygen Concentration (CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2 and CAC-AR-1263)
M R R g._,10. Containment Ilydrogen Concentration M R 2 42-(CAC-AT-1259-1; CAC-AR-1259; CAC-AT-1263-1 and CAC-AR-1263)
,o Jd-W C)
IV 4-
i I TABLE 3.3.6.1-1 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION m E5 MINIMUM NUMBER OPERABLE TRIP U TRIP FUNCTION AND INSTRUMENT NUMBER SYSTEMS PER OPERATING PUMP i R n ,
, 1. Reactor Vessel Water Level - 1 Low Low, Level 2 h ( B21-LT-N024 A-1, B-1 and B21-LT-N0 !5 A-1, B-1) i H B21-LTM-N024A-1,B-1 and B21-LTM-UO25A-1,B-1) l N>
- 2. Reactor Vessel Pressure - Low I
( B21-PS-N04 5 A, B ,C , D) M I i g ___ g- a1. g as- " LJ7 v N LJ1
i f~ TABLE 3.3.6.1-2 m ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETPOINTS W E vi TRIP ALLOWABLE TRIP FUNCTION AND INSTRUMENT NUMBER SETPOINT VALUE f3 R ' e 1. Reactor Vessel, Water Level - Low low, Level 2 > -38 inches > -38 inches g (B21-LTM-N024A-1,B-1 and s " B21-LTM-N025A-1,B-1) to
- 2. Reactor Vessel Pressure - Low >1120 psig
> 112 0. psig
( B21 -PS-N045A , B ,C , D) e ? I g. g a>- n 22. g LJ7 C> N ON
I TABLF 4.3.6.1-1 A'IWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS N
@ CilANNEL CIIANNEL FUNCTIONAL CllANNEL E TRIP FUNCTION AND INSTRUMENT NUMBER CIIECK TEST CALIBRATION M
- 1. Peactor Vessel Water Level -
' Low Low, Level 2
@ (B21-LT-N024A-1,B-1; B21-LT-N025A-1,B-1) NAI ") NA R(b)
[i B21-LTM-N024A-1,B-1; B21-LTM-N025A-1,B-1) D M M w
- 2. Reactor Vessel Pressure - Low NA M R
( B21-PS-N04 5 A, B , C , D) ta E i' Ig 4mm a 42= $ (a) The transmitter channel check is satisfied by the trip unit channel check. LJ7 " A separate transmitter check is not required. ! O C1) ' (b) Transmitters are exempted from the monthly channel calibration. N N
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- d. At least once per 18 months, during shutdown, by verifying
. that either:
- 1. The battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for 8 hours when the battery is subjected to a battery service test, or
- 2. The battery capacity is adequate to supply a durmly load of the following profile while maintaining the battery terminal voltage > 105 volts.
a) During the initial 60 seconds of the test; l) Battery 2A-1 > 1056.42 amperes, I
- 2) Battery 2A-2 E 1211.90 amperes,
- 3) Battery 2B-1 > 1089.06 amperes, and
- 4) Battery 28-2E1042.67 amperes. l
')
c During the remainder of the first 30 minutes of the test; l) Battery 2A-1 > 243.19 amperes, _ l
- 2) Battery 2A-2 > 159.10 amperes,
- 3) Battery 23-1 > 176. 79 coeres, and
- 4) Battery 28-2E216.67 amperes. I c) During the remainder of the 8 hour test; l) Battery 2A-1 > 89.52. amperes,
.. I
- 2) Battery 2A-2 > 50.34 amperes, -
- 3) Battery 2B-1 > 53.39 amperes, and
- 4) Battery 28-2 > 75.09 argares.
I
- 3. At the completion of either of the above tests, the battery charger shall be demonstrated capable of recharg-ing its battery at a rate of at least 200 amperes while supplying normal D.C. loads. The battery shall be charged to at least 95% capacit/ in < 24 hours.
- e. At least once per 66 months during shutdown by verifying that the battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test. This performance discharge test shall be performed subsequent to the satisfactory completion of the required battery service test and after normal equalizer charge.
BRUNSWICK - UNIT 2 3/4 8-10 1445 028 imemame c so.}}