ML20005F775

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Proposed Tech Specs,Changing Main Steam Line Radiation Monitor Setpoint Re Operation of Hydrogen Water Chemistry Sys
ML20005F775
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 01/05/1990
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20005F774 List:
References
NUDOCS 9001170247
Download: ML20005F775 (12)
v • d • e


Text

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TABLE 2.2.1-1 5 E E REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS n ALLOWABLE TRIP SETPOINT VAIRES FUNCTIONAL UNIT E Intermediate Range Monitor, Neutron Flux - High(a) $ 120 divisions of full scale-5 120 divisions y 1. of full scale 2. Average Power Range Monitor Neutron Flux - High, 15%(b) $ 15% of RATED THERMAL POWER $ 15% of RATED a. TBERMAL POWER Flow-Biased Neutron Flux - High(c)(d) $ (0.66 W + 54%) $ (0.66 W + 54%) b. Fixed Neutron Fluu - High(d) < 120% of RATED THERMAL. POWER $ 120% of RATED: c. THERMAL POWER N. 3. Reactor Vessel Steam Dame Pressure - High' $ 1045 psig $:1045 pois - s I8) 3 +162.5 inches 8) E 4. Reactor' Vessel Water' Level - Low, Level 1. 3 +162.5 inches Main Steam Line Isolation Valve - Closure (*)- < 10% closed - -< 10% closed 5. q Main Steam Line Radiation - High(h) $ 3 x full power background f 3.5 x full power h 6. background 7. Dryvell Pressure 'High $ 2 psig ~$ 2 psig 8. . Scram Discharge Volume Water Level - High < 109 gallons 3 109 gallons h 5 II) 9. Turbine Stop Valve - Closure $ 10% tiosed' $ 10% closed -k ?,

10. Turbine Contro11 Valve Fast
osure, Control Oil Pressure - Low 3 500 psig 3 500 psig,

z -.. = -...

-l 0 TABLE 2.2.1-1 (Continued) 9 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS t NOTES -i E (a) The Intermediate Range Monitor scram functions are automatically bypassed when the reactor mode switch is placed in the Run position and the Average Power Range Monitors are on scale. (b) This Average Power Range Monitor scram. function is a fixed point and is-increased when the reactor mode switch is placed'in the Run position. (c) The Average Power Range Monitor scram function is varied, Figure 2.2.1-1, as a function of recirculation loop flow (W). 'The trip settlag of this function must be maintained in accordance with Specification 3.2.2.. (d) The APRM flow-biased high neutron flux. signal is fed throughla time constant circuit of approximately 6 seconds. The APRM fixed high neutron l flux signal does not incorporate the time constant, but responds directly to instantaneous, neutron flux. (e) The Main Steam Line Isolation Valve-Closure scram function is avtomatically bypassed when the reactor mode switch is in other than the Run. position. (f) These scram functions are bypassed when THERMAL FCWER is>1ess than.30% of RATED THERMAL POWER.. (g) Vessel water levels refer to REFERENCE LEVEL ZERO. (h) The Hydrogen Water Chemistry.(HWC) system shall not be placed in; service until reactor power reaches 20% of RATED THERMAL POWER. After reaching. 20% of RATED THERMAL POWER, the-normal-full power background radiation- -[ 1evel and associated trip setpoints may be increased to compensate for ^ increased radiation levels-as a result of full power: operation _with hydrogen injection. Prior to' decreasing power below 20% of. RATED THERMAL POWER and after the HWC system.has been shut off,' the background level and associated setpoint shall be returned to the normal: full power values. Control rod motion shall be suspended, when the reactor power is below 20% of RATED THERMAL POWER, until the necessary adjustment is'made~ (except for. scram or other. emergency action). l BRUNSWICK - UNIT'l-2-5 Amendment No.= 1 1 +. .., _ ~. -, -.. ~

^ 2.2 LIMITING SAFETY SYSTEM SETTINGS BASES (Continued) 3. Reactor Vessel Steam Dome Pressure-Hiah (Continued)- pressure measurement compared to the highest pressure that occurs in the system during a transient. This setpoint is effective at low power / flow conditions when the turbine stop valve closure is bypassed..For a turbine trip under these conditions, the transient analysis-indicates a considerable. margin to the thermal hydraulic limit. 4. Reactor Vessel Water Level-Low.-Level #1 The reactor water level-trip point-was chosen far enough,below the normal operating level to avoid spurious scrams but high enough:above the fuel to assure that there is-adequate water to account for evaporation losses and displacement of cooling following the most severe transients.' This setting, was also used to develop,the thermal-hydraulic limits of power versus flow. 5. Main-Steam Line Isolation Valve-Closure The low pressure-isolation of the main steam line trip was provided:to give protection against rapid depressurization-and resulting cooldown of the reactor vessel. Advantage was taken of the shutdown feature in tha run mode which occurs when the main steam'line isolation valves.are closed, to provide for reactor shutdown so that high power operation at low pressures does not occur. Thus, the combination of the low pressure isolation and isolation valve closure reactor trip with the mode switch in the Run position assures the availability of neutron flux-protection over the entire range of the Safety Limits. In addition, the isolation valve closure trip with the mode switch in the Run position anticipates the pressure and flux transients which occur during normal or inadvertent isolation valve closure. 6. Main Steam Line Radiation - High The Main Steam Line Radiation detectors are'provided to detect a gross-failure of the fuel cladding. When the high radiation is detected,.a scram is initiated to reduce the continued.f ailure of fuel cladding.- At the same time, the Main Steam Line Isolation Valves are closed to limit the release of fission products. The trip settin levels to prevent spurious scrams,g is high enough above background radiation -yet low enough to promptly detect gross. failures in the fuel cladding. The Main Steam Line Radiation detectors setpoints may be ad to placing the hydrogen water chemistry (HWC) system in service. justed prior. 'If the setpoints are adjusted, the HWC system shall be placed in service or the setpoints shall be returned to the normal full power values within 24 hours. If the HWC system is not placed in service and the setpoints are not readjusted within 24-hours, control rod motion shall be suspended (except' for scram.or other emergency action) until the necessary adjustments are made.- Hydrogen injection may cause the radiation levels in the main steam lines to-increase. After shutting off the HWC system or' decreasing power, the' setpoints shall be returned-to the normal full power values. The Technical Specification wording was derived using the EPRI "Guidelinss for Permanent BWR Hydrogen Water Chemistry Installations, 1987 Revision". BRUNSWICK - UNIT 1 B 2-6 Amendment No. i w... -..... ~ -.

~ -- 4 l 'l TABLE 3.3.2-2 lii . y ISOLATION ACTUATION INSTRLMENTATION SETPOINTS E -ALLOWABLE M a . TRIP FUNCTION TRIP SETPOINT VALUE k y 1. PRIMARY CONTAIRBIENT ISOLATION -s.- Beactor Vessel Water Level - 3 + 162.5 inches (a) + 162.5 inches (a) 1. Iow Level 1 2. Imv Level.2 3 + 112 inches (*) 3 + 112 inches (a) 3. Low Level 3 ~ 3 + 2.5 inches (a) > + 2.5 inches *) I .b. ~Drywell Pressure - High $ 2 psig < 2 poig s S Main Stems Line c. $ 3.5 x fu power.. .g 1. Radiation - High 5 3 x full wer background background on 2. Pressure - Low' 3 825 psig _3 825 psig ' 3. Flow - High < 140% of rated flow $ 140% of rated flow de Main Steam Line Tunnel Temperature - High 5.200*F $ 200*F e. - Condenser Vacuum -"i.ow 3 7 inches Hg vacuum.. 3 7 inches Hg vacuum ' g.

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Turbine Building Area Temp - High < 200*F < 200*F Main Stack Radiation - High (b) (b) g -g. a

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9 E. ~;-' 1. e TABLE 2.2.1-1 E j-y RJACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS

  • n ALIDMABLE M

8 FUNCTIONAL UNIT TRIP SETPOINT VAIRES Intermediate Range Monitor, Neutron Flux - High(a) $ 120 divisions of full scale $ 120 divisions 1. of full scale-N j 2. Average Power Range Monitor Neutron Flux - High, 15%(b) $ 15% of RATED THERMAL POWER 5 15% of RATED s. i THERNAL POWER Flow Biased Neutron Flux - High(c)(d) (0.66 W + 54%) .5 (0.66 W + 542)' ~ b. Id) c. Fixed Neutron Flux - High $ 120% of RATED THERMAL POWER < 120% of RATED-THERNAL POWER T 3. Reactor' Vessel -Steam Dome Pr essure - High. $ 1045 psig < 1045.peig. I I 4. Reactor Vessel Water Leve'l . Low, 14 vel 1 > +162.5 inches 8) > +162.5 inches 8I Main Steam Line'Isolatior: Valve - Closure *) $ 10% closed $.10% closed I 5. Ih) 6. Main Steam Line Radiation - High $ 3 x full power background 5 3.5 x. full power l' background 7. Drywell Pressure'- High' $ 2 psig $.2 psig 8. Scram Discharge Volume Water Le el - High $ 709. gallons .$ 109 gallons (' n D ( .9. Turbine Stop Valve - Closure 2 10% closed $ 10% closed n

10. Turbine Cc.atrol Valve Fast

.r e, ,o Control Oil Pressure - Low > 509 ps g > 500 psig r - u----

TABLE 2.2.1-1-(Continued) REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS NOTES (a) The Intermediate Range Monitor' scram functions'are automatically bypassed when the reactor mode switch is placed in the Run position and the Average Power Range Monitors are on scale. .(b) This Average Power Range Monitor scram function'is a fixed point and is increased when the reactor mode switch is placed in the Run position. (c) The Average Power Rang'e Monitor scram function is varied, Figure 2.2.1-1,< as a function ~of recirculation loop flow (W).. The trip setting of thisl function must be~ maintained-in accordance with Specification 3.2.2. (d) The iPRM flow-biased high neutron flux signal is-fed through a time ] constant circuit of approximately 6 seconds. The:APRM fixed high neutron ] flux signal does not incorporate the time constant, but responds directly' to instantaneous neutron flux. (e) The Main Steam Line Isolation Valve-Closure scram function is j automatically bypassed when the reactor mode switch.is in other than'the 4 Run position. j (f) These scram functione are bypassed when THERMAL-PCdER is less than 30% of j RATED THERMAL POWER. 1 i (g) Vessel water levels refer to REFERENCE LEVEL ZERO. (h) The Hydrogen Water Chemistry (HWC) system shall not be placed in service until reactor power reaches 20% of RATED THERMAL POWER. ;After reaching-20% of RATED THERMAL POWER, the normal; full poaer background radiation -i level and associated trip setpoints may be increased to compensate for i increased radiation levels as a result of full; power operation with hydrogen injection. Prior to decreasing power below 20% of-RATED THERMAL . POWER and after the HWC system has'been shut off, the background level-and associated-setpoint shall be returned to the normal full power values. Control rod motion ~shall be suspended,Lwhen-the reactor power is below 20% of RATED THERMAL POWER,;until the necessary adjustment is-made (except-for scram or other emergency action).- i i i BRUNSWICK - UNIT 2-2 Amendment No.

I

v 2e2 ! LIMITING SAFETY SYSTEM SETTINCS GASES (Continued) q 3. Reactor Vessel Steam Dome Pressure-High (Continued) ( c pressure measurement compared to the highest pressure that occurs in the i system during a transient. This.setpoint is effective at low power / flow conditions when the turbine stop valve closure is bypassed. For a turbine trip under these conditions, the transient. analysis indicates a considerable margin to the thermal hydraulic-limit. 4. Reactor Vessel' Water-Level-Low, Level #1 The reactor water level trip' point was chosen far enough below the normal operating level to avoid spurious scrams but high enough above the fuel to. assure that there is adequate water to account for evaporation-losses and displacement of cooling following,the most severe transients. This setting was also used to develop the thermal-hydraulic limits of power versus flow. 5. Main Steam Line Isolation Valve-Closure The low pressure isolation of'the main steam line trip was provided co give protection against rapid depressurization and resulting cooldown of the reactor vessel.' Advantage was taken of the shutdcwn feature in the run mode which occurs'when the main steam line isolation valves are closed,'to_provido' 4 l for reactor shutdown'so that high power operation at low pressures does not-I occur. Thus, the combination of the, low pr' essure isolation and isolation l valve closure reactor trip with the mode switch in the-Run position assuresi i the availability of neutron flux protection over the entire range of the. Safety Limits. In addition, the isolation valve closure trip wtth the mode switch ir the Run position anticipates the pressure ant flux transients which occur during normal or inadvertent isolation valve ~ closure. 6. .Mrdn Steam Line Radiation - High The Main Steam Line Radiation detector.s are provided:to detect a gross failure of the~ fuel cladding. When the high' radiation is detected, a scram.is; initiated to reduce the.centinued failure of fuel cladding. At-the same time, the Main Steam Line' Isolation-Valves are closed to limit the' release of I fission products. The trip settin levels to prevent spurious scrams,g is high enough above background-radiation - yet low enough to promptly detect. gross failures in the fuel cladding. ~ The Main Steam Line Radiation detectors setpoints may be ad to placing the hydrogen water chemistry-(HWC)i system in service. justed prior -If the setpoints are adjusted, the HWC system shall be placed in' service or the setpoints shall be returned to the~ normal full power values within: 24 hours. i If,the NWC system is not placed in service and the setpoints are not ~ readjusted within 24 hours, control rod'estion shall be suspended (except for i scram or other emergency-action) until the necessary adjustments are made.- Hydrogen injection n',y cause the radiation levels;in the main steam lines to increase. !After shutting off the HWC system or decreasing power, the setpoints shall be returned to the normal full ;ower values. 1 The Technical Specification wording was derived using' the EPRI l "Cuidelines for Permanent BWR Hydrogen Water Chemistry Installations, H 1987 Revision". i I o BRUNSWICK - UNIT 2 B 2-6 Amendment No. 1 h M

~- ... _ _... ~. TABLE 3.3.2-2 g-y ISOLATION ACTUATION INSTRtMENTATION SETPOINTS n ALLOWABLE ? a ' TRIP FUNCTION TRIP SETPOINT VALUE l ' y 1. PRIMARY CONTAIBMENT ' ISOLATION l w a. Reactor Vessel Water Level -- j' 1. Iow, Level 1 3 + 162.5 inches *) 3-+ 162.5 inches *I I I .2. Low, Level 2 . 3 +-112 inches *) 3 + 112 inches *) ~ I I l 3. Low, Level 3 3 + 2.5 inches *} 3 + 2.5 inches *) I I b. Drywell Pressure - High $ 2 psig $ 2 psig 4 w N -] c. Main Steam Line y 1. Radiation.- High 53xfuligwer 53.5xfugpower J g background back tound 4 4 2. Pressure - Low 3 825 psig 3 825 peig 3. . Flow - High < 140%~of rated flow $ 140% of rated flow - i - 4. - Flow High 5 40%.of rated flow $ 40% ::' rated flow - l d. Main. Steam Line Tunnel Temperature - High 3 200*F $ 200*F.' e.; Condenser Vacuum Low . 3 7' inches.Hg vacuum' 3 7 inches Hg vacuum

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f. -Turbine BuiNing Area ~ Temp - High'-

5'200*F $ 200*F a o

g. ' Main Stack Radiation - High.

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i? . *1co TABLE 3.3.2-2 (Continued) ISOLATION ACTUATION INSTT@fENTATION SETPOINTS' ALLOWABLE c: 'lltIP SETFOINT VALUE S TRIP FUNCTION e N 5. SHUTDOWN COOLING SYSTEM ISOLATION Reactor Vessel Water Level - Low Level 1 > 162.5' inches '} > 162.5. inches *) I I a. b. Reactor Steam Domi-Pressure - High 5 140 psig $ 140 psig u N w E N N I (a) Vessel water levels refer to REFERENCE LEVEL'ZERO. (b) Establi'sh alare/ trip setpoints per the methodology contained in the OFFSITE DOS 6 CALCULATION MANUAL (ODCM). (c) The Hydrogen Water Chemistry (HWC) system shall'not be placed in service until reactor. power reaches 20% of-RATED THERMAL F0h'ER. 'After reaching 20% of RATED THERMAL POWER, the normal full power background radiation l level'and associated' trip setpoints=may be increated to compensate for. increased radiation' levels as a' result ~ of full power operation with hydrogen injection.- Prior to_ decreasing 4 power below 20% of RATED THERMAL ~ POWER-D s' and'after the HWC system has been shut off, the background level and associated setpoint shall be returned to-the normal full power values. ' Control rod' motion'shall..bel suspended, when the-reactor power is below 20% of'- ^ RATED THERMAL POWER, until.-the necessary adjustment is made (except"for scram or other emergency action). z ^O -A -.o .r=ae-m_.ma sa ..m A^w.,.Aaasu---.z.-h.ae-.- '---n'aws .m. -}}

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