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TENNESSEE 37401 5N 157B Lookout Place U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C.20555 Gentlemen: | TENNESSEE 37401 5N 157B Lookout Place U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C.20555 Gentlemen: | ||
In the Matter of Tennessee Valley Authority Docket Nos.50-259 50-260 50-296 BRONNS FERRY NUCLEAR PLANT (BFN)-UNITS 1, 2, AND 3-FINAL SAFETY ANALYSIS REPORT (FSAR)ANNUAL UPDATE-SUPPLEMENT TO AMENDMENT NO.5 In accordance with 10 CFR Part 50.71(e), Amendment No.5 to the BFN FSAR was submitted on July 22, 1987.This letter submits revised pages to Amendment No.5.The instruction sheet for filing Amendment No.5 did not list pages 7.6-1 and-2 which were part of the amendment text.The missing page numbers have been added to the instruction sheet.The revised instruction sheet along with a copy of pages 7.6-1 and-2 are enclosed.The instruction sheet listed tables 7.6-1 and 7.8-1 with sheet numbers to distinguish the order in which the pages were to be placed in the FSAR volumes'~'n the text, however, the tables did not have the appropriate sheet numbers included in the titles.The sheet numbers have been added to the table titles, and copies of the revised tables are enclosed.These changes are submitted only to ensure that the pages associated with Amendment No.5 are properly inserted into the FSAR.Please refer any questions or comments to Nina R.Cosby at (205)729-2676.Enclosures cc: See page 2 8709300170 870925 PDR ADOCK 05000259 PDRJ Very truly yours, TENNESSEE VALLEY AUTHORITY R.idley, D rector Nuclear Lice sing and Regulatory Affairs"I pl,n/qual opportunity Emp~oy<<a55 yt-1 Jl U.S.Nuclear Regulatory Commission cc (Enclosures): | In the Matter of Tennessee Valley Authority Docket Nos.50-259 50-260 50-296 BRONNS FERRY NUCLEAR PLANT (BFN)-UNITS 1, 2, AND 3-FINAL SAFETY ANALYSIS REPORT (FSAR)ANNUAL UPDATE-SUPPLEMENT TO AMENDMENT NO.5 In accordance with 10 CFR Part 50.71(e), Amendment No.5 to the BFN FSAR was submitted on July 22, 1987.This letter submits revised pages to Amendment No.5.The instruction sheet for filing Amendment No.5 did not list pages 7.6-1 and-2 which were part of the amendment text.The missing page numbers have been added to the instruction sheet.The revised instruction sheet along with a copy of pages 7.6-1 and-2 are enclosed.The instruction sheet listed tables 7.6-1 and 7.8-1 with sheet numbers to distinguish the order in which the pages were to be placed in the FSAR volumes'~'n the text, however, the tables did not have the appropriate sheet numbers included in the titles.The sheet numbers have been added to the table titles, and copies of the revised tables are enclosed.These changes are submitted only to ensure that the pages associated with Amendment No.5 are properly inserted into the FSAR.Please refer any questions or comments to Nina R.Cosby at (205)729-2676.Enclosures cc: See page 2 8709300170 870925 PDR ADOCK 05000259 PDRJ Very truly yours, TENNESSEE VALLEY AUTHORITY R.idley, D rector Nuclear Lice sing and Regulatory Affairs"I pl,n/qual opportunity Emp~oy<<a55 yt-1 Jl U.S.Nuclear Regulatory Commission cc (Enclosures): | ||
Mr.G.G.Zech, Assistant Director Regional Inspections Division of TVA Projects Office of Special Projects U.S.Nuclear Regulatory Commission Region II 101 Marietta St., NW, Suite 2900 Atlanta, Georgia 30323 Mr.J.A.Zwolinski, Assistant Director for Projects Division of TVA Projects Office of Special Projects U.S.Nuclear Regulatory Commission 4350 East-West Highway EWW 332 Bethesda, Maryland 20814 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant Route 2, P.O.Box 311 Athens, Alabama 35611 INSTRHCTION SHEET FOR AMENDHENT 5 BROWS FERRY NUCLFAR PLANT Remove Insert EPL-ALL 1.2-3/4 Table 1.3-1 Table 1.3-2 2.2-1/2 Table 2.2-8 2.4-5/6 2.4-7/8 2.4-9/10 (Sheet 13/14)(Sheet 7/8)EPL 1-78 1.2-3/4 Table 1.3-1 Table 1.3-2 2.2-1/2 Table 2.2-8 2.4-5/6 2.4-7/8 2.4-9/10 (Sheet 13/14)(Sheet 7/8)Table 2.4-4 (Sheet 3/4)2.6-1/2 3.2-1/2 3.2-3/4 3.2-5/6 Table 3.2-5 3.3-13/14 3.4-5/6 3.4-7/8 3.4-9/10 3.6-9/10 3.7-1/2 3.7-3/4 3.7-5/6 3.8-7/8 4.1-1/2 4.2-3/4 4.2-5/6 4.4-1/2 4.4-3/4 4.4-11/12 4.9-1/2 5.0-iii/iv 5.2-7/8 5.2-11/12 6.0-iii 6.4-1/2 6.5-13/14 6.5-19/20 7.2-7/8 7.2-19/20 Table 2.4-4 (Sheet 3/4)2.6-1/2 3.2-1/2 3.2-3/4 3.2-5/6 Table 3.2-5 3.3-13/14 3.4-5/6 3.4-7/8 ,3.4-9/10 3.6-9/10 3'-1/2 3.7-3/4 3.7-5/6 3.8-7/8 4.1-1/2 4.2-3/4 4.2-5/6 4.4-1/2 4.4-3/4 4.4-11/12 4.9-1/2 5.0-iii/iv 5.2-7/8 5.2-11/12 6.0-iii 6.4-1/2 6.5-13/14 6.5-19/20 7.2-7/8 7.2-19/20 BFNP-5 7.6 REFUELING INTERLOCKS | Mr.G.G.Zech, Assistant Director Regional Inspections Division of TVA Projects Office of Special Projects U.S.Nuclear Regulatory Commission Region II 101 Marietta St., NW, Suite 2900 Atlanta, Georgia 30323 Mr.J.A.Zwolinski, Assistant Director for Projects Division of TVA Projects Office of Special Projects U.S.Nuclear Regulatory Commission 4350 East-West Highway EWW 332 Bethesda, Maryland 20814 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant Route 2, P.O.Box 311 Athens, Alabama 35611 INSTRHCTION SHEET FOR AMENDHENT 5 BROWS FERRY NUCLFAR PLANT Remove Insert EPL-ALL 1.2-3/4 Table 1.3-1 Table 1.3-2 2.2-1/2 Table 2.2-8 2.4-5/6 2.4-7/8 2.4-9/10 (Sheet 13/14)(Sheet 7/8)EPL 1-78 1.2-3/4 Table 1.3-1 Table 1.3-2 2.2-1/2 Table 2.2-8 2.4-5/6 2.4-7/8 2.4-9/10 (Sheet 13/14)(Sheet 7/8)Table 2.4-4 (Sheet 3/4)2.6-1/2 3.2-1/2 3.2-3/4 3.2-5/6 Table 3.2-5 3.3-13/14 3.4-5/6 3.4-7/8 3.4-9/10 3.6-9/10 3.7-1/2 3.7-3/4 3.7-5/6 3.8-7/8 4.1-1/2 4.2-3/4 4.2-5/6 4.4-1/2 4.4-3/4 4.4-11/12 4.9-1/2 5.0-iii/iv 5.2-7/8 5.2-11/12 6.0-iii 6.4-1/2 6.5-13/14 6.5-19/20 7.2-7/8 7.2-19/20 Table 2.4-4 (Sheet 3/4)2.6-1/2 3.2-1/2 3.2-3/4 3.2-5/6 Table 3.2-5 3.3-13/14 3.4-5/6 3.4-7/8 ,3.4-9/10 3.6-9/10 3'-1/2 3.7-3/4 3.7-5/6 3.8-7/8 4.1-1/2 4.2-3/4 4.2-5/6 4.4-1/2 4.4-3/4 4.4-11/12 4.9-1/2 5.0-iii/iv 5.2-7/8 5.2-11/12 6.0-iii 6.4-1/2 6.5-13/14 6.5-19/20 7.2-7/8 7.2-19/20 BFNP-5 7.6 REFUELING INTERLOCKS 7.6.1 Safet Ob ective The refueling interlocks are designed to back up procedural core reactivity controls during refueling operation; specifically, the interlocks prevent an inadvertent criticality during refueling operations. | ||
Ob ective The refueling interlocks are designed to back up procedural core reactivity controls during refueling operation; specifically, the interlocks prevent an inadvertent criticality during refueling operations. | |||
During a refueling operation, the reactor vessel head is remov d, allowing direct access to the core.Refueling operations in ude the removal of reactor vessel upper internals and the move nt of spent and fresh fuel assemblies between the core and the el storage pool.The service platform, refueling platform and the equipment handling hoists on the platforms are used to accomplish the refueling task.The refueling interlocks reinforce operational procedures that prohibit making the rea tor critical under certain situations encountered during refue ng operations by restricting the movement of control rods and he operation of refueling eguinment. | During a refueling operation, the reactor vessel head is remov d, allowing direct access to the core.Refueling operations in ude the removal of reactor vessel upper internals and the move nt of spent and fresh fuel assemblies between the core and the el storage pool.The service platform, refueling platform and the equipment handling hoists on the platforms are used to accomplish the refueling task.The refueling interlocks reinforce operational procedures that prohibit making the rea tor critical under certain situations encountered during refue ng operations by restricting the movement of control rods and he operation of refueling eguinment. | ||
7.6.2 Safet Desi n Basis 1.During fuel movements in or over the reactor core, all l control rods shall be in their ful inserted positions. | |||
Desi n Basis 1.During fuel movements in or over the reactor core, all l control rods shall be in their ful inserted positions. | |||
2.No more than one control rod sh 1 be withdrawn from its fully inserted position at any ime when the reactor is in the refueling mode.The refueling interlocks in ude circuitry that senses the condition of the refuelin equipment and the control rods.Depending on the sensed ondition, interlocks are actuated, which prevents the movement the refueling equipment or withdrawal of control rods (rod bio).Circuitry is provi ed which senses the following conditions: | 2.No more than one control rod sh 1 be withdrawn from its fully inserted position at any ime when the reactor is in the refueling mode.The refueling interlocks in ude circuitry that senses the condition of the refuelin equipment and the control rods.Depending on the sensed ondition, interlocks are actuated, which prevents the movement the refueling equipment or withdrawal of control rods (rod bio).Circuitry is provi ed which senses the following conditions: | ||
a.All-rods in erted;b.Refuelin platform positioned near or over the core;c.Refue ing platform hoists fuel-loaded (fuel, grapple, frame-mou ed hoist, monorail-mounted hoist);d.F el grapple not full up;and e.Service platform hoist fuel-loaded. | a.All-rods in erted;b.Refuelin platform positioned near or over the core;c.Refue ing platform hoists fuel-loaded (fuel, grapple, frame-mou ed hoist, monorail-mounted hoist);d.F el grapple not full up;and e.Service platform hoist fuel-loaded. | ||
Revision as of 20:51, 5 May 2019
| ML18032A570 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/25/1987 |
| From: | GRIDLEY R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8709300170 | |
| Download: ML18032A570 (16) | |
Text
REGULATORY ORMATION DISTRIBUTION SY M (RIDB)ACCESSION NBR: 870'F300170 DOC.DATE: 87/09/25 NOTARIZED'O FACIL: 50-259 Hrowns Ferry Nuclear Power Stations Unit ii Tennessee 50-260 Hrowns Ferry Nuclear Power Stations Unit 2i Tennessee 50-296 Browns Ferry Nuclear Power Stations Unit 3>Tennessee AUTH.NAME AUTHOR AFFILIATION GRIDLEYs R.Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards revised pages to 870722 Amend 5 to updated FBARi adding page numbers to instru tion sheet 5 sheet numbers to ab es 7.6-J, h 7.8-1.DISTRI I N CO E: A053D C IES R CEIVED: LTR ENCL SIZE: TITLE: OR Submittal:
Updated FSAR (50.71)and Amendments DOCKET 0 05000259 05000260 05000296 NOTES: Zwolinski 3 cg.1 cg ea to: Axelradi Ebneteri S.Richardsoni Liawi G.Zechi Oli OIA.I'wolinski 3 cg.icy ea to: Axelradi Ebneteri S.Richardsons Liaw G.Zech OI>OIA.Zwolinski 3 cg.icy ea to: Axelradi Ebneteri S.Richardson'iawi G.Zechi Oli OIA.05000259 05000260 050002'P6 REC IP I ENT ID CODE/NAME JAMERSONi C GEARS'INTERNAL: ACRS NRR/DEBT/ADS RGN2 EXTERNAL: DMB/DSB LPDR NSIC NOTES: COPIES LTTR ENCL 1 0 1 1 2 2 1 0 1 1 1 1 1 1 1 12 12 REC IP IENT ID CODE/NAME PD BTANGi J A IRH REG F E 01 FRANKLIN NRC PDR COPIES LTTR ENCL 0 1 1 1 1 1 1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 24
TENNESSEE VALLEY AUTHORlTY CHATTANOOGA.
TENNESSEE 37401 5N 157B Lookout Place U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C.20555 Gentlemen:
In the Matter of Tennessee Valley Authority Docket Nos.50-259 50-260 50-296 BRONNS FERRY NUCLEAR PLANT (BFN)-UNITS 1, 2, AND 3-FINAL SAFETY ANALYSIS REPORT (FSAR)ANNUAL UPDATE-SUPPLEMENT TO AMENDMENT NO.5 In accordance with 10 CFR Part 50.71(e), Amendment No.5 to the BFN FSAR was submitted on July 22, 1987.This letter submits revised pages to Amendment No.5.The instruction sheet for filing Amendment No.5 did not list pages 7.6-1 and-2 which were part of the amendment text.The missing page numbers have been added to the instruction sheet.The revised instruction sheet along with a copy of pages 7.6-1 and-2 are enclosed.The instruction sheet listed tables 7.6-1 and 7.8-1 with sheet numbers to distinguish the order in which the pages were to be placed in the FSAR volumes'~'n the text, however, the tables did not have the appropriate sheet numbers included in the titles.The sheet numbers have been added to the table titles, and copies of the revised tables are enclosed.These changes are submitted only to ensure that the pages associated with Amendment No.5 are properly inserted into the FSAR.Please refer any questions or comments to Nina R.Cosby at (205)729-2676.Enclosures cc: See page 2 8709300170 870925 PDR ADOCK 05000259 PDRJ Very truly yours, TENNESSEE VALLEY AUTHORITY R.idley, D rector Nuclear Lice sing and Regulatory Affairs"I pl,n/qual opportunity Emp~oy<<a55 yt-1 Jl U.S.Nuclear Regulatory Commission cc (Enclosures):
Mr.G.G.Zech, Assistant Director Regional Inspections Division of TVA Projects Office of Special Projects U.S.Nuclear Regulatory Commission Region II 101 Marietta St., NW, Suite 2900 Atlanta, Georgia 30323 Mr.J.A.Zwolinski, Assistant Director for Projects Division of TVA Projects Office of Special Projects U.S.Nuclear Regulatory Commission 4350 East-West Highway EWW 332 Bethesda, Maryland 20814 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant Route 2, P.O.Box 311 Athens, Alabama 35611 INSTRHCTION SHEET FOR AMENDHENT 5 BROWS FERRY NUCLFAR PLANT Remove Insert EPL-ALL 1.2-3/4 Table 1.3-1 Table 1.3-2 2.2-1/2 Table 2.2-8 2.4-5/6 2.4-7/8 2.4-9/10 (Sheet 13/14)(Sheet 7/8)EPL 1-78 1.2-3/4 Table 1.3-1 Table 1.3-2 2.2-1/2 Table 2.2-8 2.4-5/6 2.4-7/8 2.4-9/10 (Sheet 13/14)(Sheet 7/8)Table 2.4-4 (Sheet 3/4)2.6-1/2 3.2-1/2 3.2-3/4 3.2-5/6 Table 3.2-5 3.3-13/14 3.4-5/6 3.4-7/8 3.4-9/10 3.6-9/10 3.7-1/2 3.7-3/4 3.7-5/6 3.8-7/8 4.1-1/2 4.2-3/4 4.2-5/6 4.4-1/2 4.4-3/4 4.4-11/12 4.9-1/2 5.0-iii/iv 5.2-7/8 5.2-11/12 6.0-iii 6.4-1/2 6.5-13/14 6.5-19/20 7.2-7/8 7.2-19/20 Table 2.4-4 (Sheet 3/4)2.6-1/2 3.2-1/2 3.2-3/4 3.2-5/6 Table 3.2-5 3.3-13/14 3.4-5/6 3.4-7/8 ,3.4-9/10 3.6-9/10 3'-1/2 3.7-3/4 3.7-5/6 3.8-7/8 4.1-1/2 4.2-3/4 4.2-5/6 4.4-1/2 4.4-3/4 4.4-11/12 4.9-1/2 5.0-iii/iv 5.2-7/8 5.2-11/12 6.0-iii 6.4-1/2 6.5-13/14 6.5-19/20 7.2-7/8 7.2-19/20 BFNP-5 7.6 REFUELING INTERLOCKS 7.6.1 Safet Ob ective The refueling interlocks are designed to back up procedural core reactivity controls during refueling operation; specifically, the interlocks prevent an inadvertent criticality during refueling operations.
During a refueling operation, the reactor vessel head is remov d, allowing direct access to the core.Refueling operations in ude the removal of reactor vessel upper internals and the move nt of spent and fresh fuel assemblies between the core and the el storage pool.The service platform, refueling platform and the equipment handling hoists on the platforms are used to accomplish the refueling task.The refueling interlocks reinforce operational procedures that prohibit making the rea tor critical under certain situations encountered during refue ng operations by restricting the movement of control rods and he operation of refueling eguinment.
7.6.2 Safet Desi n Basis 1.During fuel movements in or over the reactor core, all l control rods shall be in their ful inserted positions.
2.No more than one control rod sh 1 be withdrawn from its fully inserted position at any ime when the reactor is in the refueling mode.The refueling interlocks in ude circuitry that senses the condition of the refuelin equipment and the control rods.Depending on the sensed ondition, interlocks are actuated, which prevents the movement the refueling equipment or withdrawal of control rods (rod bio).Circuitry is provi ed which senses the following conditions:
a.All-rods in erted;b.Refuelin platform positioned near or over the core;c.Refue ing platform hoists fuel-loaded (fuel, grapple, frame-mou ed hoist, monorail-mounted hoist);d.F el grapple not full up;and e.Service platform hoist fuel-loaded.
7.6-1 A two-channel d-c circuit indicates that all rods are in.The rod-in condition for each rod is established by the closure of a magnetically operated reed switch in the rod position indicator probe.The rod-in switch must be closed for each rod before the"all rods in" signal is generated; two channels carry the signal.Both channels must register the"all rods in" signal in order for the refueling interlock circuitry to indicate the"all rods in" condition.
The refueling platform is provided with two mechanical switches attached to the platform which are tripped open by a long, stationary ramp mounted adjacent to the platform rail.The switches open before the platform or any of its hoists are physically located over the reactor vessel, thereby providing indication of the approach of the platform toward the core or its position over the core.The three hoists on the refueling platform and the hoist on the service platform are provided with switches that open when the hoists are fuel-loaded.
The switches are set to open at a load weight that is lighter than the weight of a single fuel assembly, thus providing positive indication whenever fuel is loaded on any hoist.The telescoping fuel grapple hoist is provided with a geared limit switch, which is open any time the grapple has descended more than about four inches from its full up position.This switch is placed in=series with the grapple load switch to ensure interlock operation in the event that the weight of the bottom section of the telescope plus the fuel is less than the preset load.The indicated conditions are combined in logic circuits to satisfy all restrictions on refueling eguipment operation and control rod movement, as described in Figures 7.6-1, 7.6-2, Table 7.6-1 and in the following:
a.Refueling platform travel toward or over the core is stopped when the following three conditions exist concurrently:
l.Any refueling platform hoist is loaded or the fuel grapple is not in its full up position;2.All rods not fully inserted;and 3.Refueling platform position is such that position switch No.1 is open (platform near or over the core).b.With the mode switch in STARTUP, refueling platform travel toward the core is prevented when the refueling platform No.2 position switch is open (platform near or over the core).7.6-2 Bs TABLE 7.6-1 REFUELING INTERLOCK EFFECTIVENESS s Refueling Platform Situation Position Refueling Platform Hoists MMH>>FMH>>FG Service Platform Hoist Mode Control Rods Switch A~ttem t Result Not near core UL>>UL>>UL>>UL>>All rods Refuel fully inserted Move refueling platform over core No restrictions 2.Not near core UL UL UL UL-All rods Refuel fully inserted Withdraw rods Cannot withdram[$more than one rod 3.Not near core UL UL UL UL One rod withdrawn Refuel Move refueling platform over core No restrictions 4.Not near core Any hoist'oaded UL or FG not fully up One rod withdrawn Refuel Move refueling platform over core Platform stopped before over core 5.Not near core UL UL UL UL More than one rod withdrawn Refuel Move refueling platform over core Platform stopped before over core 6.Over core UL UL UL UL-All rods Refuel Withdraw rods fully inserted Cannot withdraw)f~more than one rod 7.Over core Any hoist loaded UL or FG not fully up All rods Refuel Withdraw rods fully inserted Rod block Ba Not near core UL UL UL All rods fully inserted Refuel Withdraw rods Rod block 9.Not near core UL UL UL All rods Refuel fully inserted s Operate service platform hoist No restrictions 10.Not near core UL UL UL One rod withdrawn Refuel Operate service platform hoist Boist operation prevented
BFN-TABLE 7.6-1 (continued)
REFUELING INTERLOCK EFFECTIVENESS Situation Refueling Platform Position Refueling, Platform Hoists NHH+FHH<FG Service Platform Hoist Control Rods Mode Switch A~ttem t Result ll.Not near core UL UL UL 12.Not near core UL UL UL All rods fully inserted Startup I All rods Startup fully inserted Move refueling, platform over core Operate service platform hoist Platform stopped 1 6 No restrictions 14.Not near core UL UL UL 15.Not near core UL UL UL 13.Not near core UL UL UL UL One rod withdrawn All rods fully inserted All rods not fully inserted Startup Startup Withdraw rods Withdraw rods Startup Withdraw rods Startup Operate service platform hoist Boist operations prevented Rod block Rod block No restrictions 16 16.Over core UL UL UL UL All rods fully inserted Startup Withdraw rods Rod block 16 17.Any Any condition Any'ondition Any condition, reactor riot at power Startup Turn mode switch to run Scram<<LEGEND: MMH-Monorail Mounted Hoist FMH-Frame Mounted Hoist FG-Fuel Grapple UL-Unloaded L-Fuel-loaded 0
BFNP-5 TABLE 7.8-1 REACTOR VESSEL INSTRUMENTATION INSTRUMENT SPECIFICATIONS~
Measured Variable Instrument
~18 Normal R~an e A~ccecac Reactor vessel surface temperature Thermocouple 0-600'F ISA C96.1 Reactpr vessel top head Thermocouple surface temperature 0-600 F ISA C96.1 Reactor vessel top head Thermocouple flange surface temperature 0-600'F ISA C96.1 Reactor vessel surface temperature Temperature recorder 0-600'F+lT Reactor vessel water level (temperature compensated) t Reactor vessel water level Level indicator~*
Level indicator""+2%Calibrated jet pump flow Flow transmitter 0-30 psid w 1/2%Jet pump flow rate Flow transmitter 0-30 psid+1/27.
0 BFNP-5 TABLE 7.8-1(continued)
REACTOR VESSEL INSTRUMENTATION INSTRUMENT SPECIFICATIONS*
Measured Variable Ins trumen t TIITl 8 Normal~Ran a R~ecurae Tri Settin Calibrated jet pump flow Flow indicator 0-8 x 106+27.lb/hr Jet pump flow rate Flow indicator 0-80 x 106+2V lb/hr Calibrated jet pump flow Square root extractor+1/27.Recirculation loop flow rate Flow summer+1/27.Recirculation loop flow rate Flow indicator 0-70000 gpm+27.Core total flow Flow summer~1/27.*Other instruments measuring reactor vessel variables are discussed in sections of the Safety Analysis Report where the systems using the instruments are described.
- ~Four types of compensated plus uncompensated level indications having an associated range and corresponding level trip settings.
A