ML19325D618

Proposed Tech Specs Re Main Steam Line Radiation Monitor Setpoint Change Hydrogen Water Chemistry

ML19325D618
Person / Time
Site:	Brunswick
Issue date:	10/19/1989
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML19325D616	List: ML19325D615 ML19325D618
References
NUDOCS 8910250149
Download: ML19325D618 (15)

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ENCLOSURE 3 l

BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50-325 & 50-324 i

OPERATING LICENSES DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT r

NAIN STEAM LINE RADIATION MONITOR SETPOINT CHANGE

-l HYDROCEN WATER CHEMISTRY INSTRUCTIONS FOR INCORPORATION The proposed changes to the Technical Specifications (Appendix A to Operating.

Licenses DPR-71 and DPR-62) would be incorporated as follows:

1 UNIT 1 l

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ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PLANT, UNITS'l AND 2 J

w/

NRC DOCKETS 50-325 & 50-324

)

OPERATING LICENSES DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT:

5 MAIN STEAM LINE RADIt. TION MONITOR SETPOINT CHANGE

.i HYDROCEN WATER CHEMISTRY j

4

SUMMARY

LIST OF REVISIONS i

o UNIT 1

+

Pages Daaf:riotion of Cliannes 2-4 Add footnote application to Item 6 in g

table 2.2.1-1.

2-5

' Add footnote to explain MSLRN setpoint c.,-

adjustment when NWCS is in service.

1 i

B 2-6 Add discussion regarding MSLRN setpoint aojustment during use of HWC' system.

3/4 3-18 Add footnote appli ation to Item 1.c.1 in h

Table 3.3.2-2.

i 3/4 3-22 Add footnote to explain NSLRN setpoint I

adjustment when HWCS is in service.

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i L

UNIT 2 1'

Tdges Descriotion of Channes h

2-4 Add footnote application to Item 6 in table 2.2.1-1.

2-5 Add footncte to explain MSLRN setpoint adjustment when HWCS is in service.

7,

B 2-6 Add discussion regarding MSLRM setpoint adjustment dt' ring use of HWC system.

Ine i

3/4 3-18 Add footnote application to Item 1.c.1 in Table 3.3.2-2.

3/4 3-22 Add footnote to explain MSLRH sc.tpoint adjustment vien HVCS is in service.

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BRUNSWICK STEAM ELECTRIC PL\\NT, UNITS 1 AND 2 c

NRC DOCKETS 50-325 & 50-324 OPERATIhc TICENSES DPR 'll & DPR-62 l

REQUEST /Ok LICENSE AN2NDMENT

- MAIN STEAM LINE RADIATION MONITOR SETPOINT CHANCE p

11YDROCEN WATER CHEMISTRY

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TECHNICAL SPECIFICATION PAGES - UNIT 1

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-. REACTOR PROTECTION SYSTtM INSTRUMENTATION SCTPOIFTS f3 ^

()

-ALIDWABLE x.

FUNCTIONAL UNIT

-. TRIP SETPOIKT.

VALUES =

c*-y 1.

Intermediate Range Monitor, Neutron Flux High(a

~< 120' divisions'of fu11' scale

< 120 divisions of full scale 2.

Average Power Range Monitor Neutron Flux - High, 15%(b)

$ 15% of MATED THERMAL POWER

$ 15% of RATED a.

. THERMAL 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

. THERMAL POWER u

E 3.

Reactor Vessel Steam Dome Pressure - High 5 1045 psig 5 1045 psig Reactor Vessel Water Level - Low, 14 vel 1

-> +162.5 inches E)

-> +162.5 inches 8)

- 4 I

I 4.

I 5.

Main Steam Line Isolation Valve - Closure *)

$ 10% closed 5 10% closed 6.

Mair. Steam Line Radiation - High(h)

$ 3 x full power background

- < 3.5 x full power' l

. backg ound.

7.

Drywett Pressure - High

< 2 psig

$ 2 psig k

8.

Scram Discharge Volume Water Level -- High

= < 109 gallons

< 109 gallons a

l' 3"

9.

Turbine stop Valve - Closure (f)

< 10% closed

-5 10% closed 5

l

10. Turbine Control Valve Fast

osure, z

Control 6il Pressure - Low t 500 m tg

. 3 500 p ig i

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TABLE 2.2.1-1 (Continued)

+

REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS NOTES e.

(a) The Intermediate Range Monitor teram functions are automatically bypassed when the reactor mode switch is placed in the Run positior and the Average Power Range %Netors are on scale.

(b) This Average Power Range Monitor scram function is a fixed point and is ir ilased when the' reactor mode switch is placed in the Run position.

(c) The Average Power Range Monitor scram function is varicd, Figure 2.2.1-1, as a function of recirculation loop fles'(W). The trip setting of this function must be maintained in accordance with Specification 3.2.2.

(d) The APRM flow-biased high neutron flux signal is fed through-a time o...

constant circuit of approximately 6 seconds. The APRM fixed high neutron flux s'gr21 does not incorporate the time. constant, but responds directly to instantaneous neutron fluF.

(e) The Main Steam Line Isolation. Valve-Closure scram function is automatically bypassed when the reactor mode switch it in~other than the Run position.

(f) These scram functions are bypassed when THERMAL POWER is lesa than 30% of RATED THERMAL POWER.

-(g) Veesel water levels refer to REFERENCE LCVEL ZERC.

(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 i

level end associated trip setpoints may be increased to compensate for L

increased radiation levels as a result of full power. operation with l

hydrogen. injection. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after decreasing below 20% of RATED THERMAL ~ POWER or the HWC system has been shut of f, the be.ckground levet and associated setpoint shall be returned to the normal full power values.

If a power reduction event occurs so that the reactor power is below 20% of RATED THERMAL POWER for longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> without the required sitpoint change, aontrol rod motion shell be suspended (except for scram or other emergency action) until the necessary adjustment is made.

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BRUNSWICK - UNIT 1 2-5 Amendment No.

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-2.2 LIMITING SAFETY SYSTEM SETTINCS i

BASES (Continued) 3.

Reactor Vessel Steam Dome Pressure-High (Continued) cressure measurement compared to the highest pressure that occurs in the system during a transient.

This setpoint is effective at low peo<r/ flow conditions when the turbine stop valve closure is bypassed.

Fot a turbine

-trip under these concations, the transient analysis indicates a considerable

l margin to the thermal hydrat:lic limit.

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4.

Reactor Vessel Water Level-Low, Level #1 The' reactor water level trip point was chosen far ernugh belew the normal operating level to avoid sparlous scrams but high enough a.>ove the fuel to assure that there is adequate water to account for evaporation tr.ses 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 Isolatton valve-Closure e

The low pressure isolation of the main steam line trip was provided to give protection against rapid deptessurization and resulting cooldoen of the reactor vessel. Advantage was taken of the shutdown feature in the 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 itolation and isolation valve closure reactor trip with the mode switch in the Run position assure 3 the availability of neutron flux proteccion over the entire range of the

'Safecy Limits.

In addition, the isolation valve closure trip with the mode i

cwitch in the Run por.ition anticipates the pressure and flux transients whis:h occur during normal or inadvertent isolation valve closure.

6.

Main Steam Line Raaiation - High' I

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 failure of fuel cladding. At the same time, the Main Steam Line Isolation Valves are closed to limit the relecsc of spurious scrams,g,is high enough above background radiation The trip settin fission products.

levels to prevent yet low enough to promptly detect gross j

failures in the fuel cladding.

The Main Steam Line Radietion detectors setpoints may be adjusted price to placing the hydrogen water chemistry (HWC) system in service.

If the setpoints are adjusted. the HWC system shall be placed in service or the

.setpcints shall b; returned to the normal full power values within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

If the HWC system is not placud in service and the setpoints are not readjusted within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 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, che setpoints shall be returned to the normal full power values.

The Technical Specification wording was derived using the EPRI

" Guidelines for Permanent BWR Hydrogen Water Cheaistry Installations, 1987 Revision".

P BRUNSWICK - UNIT 1 B 2-6 An.e ndment No.

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y' 1 SOLATION ACTUATION INSTRtNENTATION SETPOINTS-n

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TRIP SETPOINT VALUE f1 TRIP FUNCTION y

1.

PRIMARY CONTAINMENT ISOLATION

~ - -

a.

Reactor Vessel Water Level -

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3 + 162.5 inches *)

3 + 162.5 inches *)

1.

Low Level 1

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'3 + 112 inches *)

3 + 112 inches *)

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Low Level 2 L Low Leval 3

> + 2.5 inches (a)

+ 2.5 inches (a)~

b.

Drywell Pressure - High

. < 2 psig

< 2 ' psi ^g g

c.

Main Steam Line y

1.

Radiation - High

<3xfuligver

<3.5xfugpower' l

g backgroun6 background 2.

Pressure - Low 3 825 prig 3.825 psig 3.

Flow - High

< 140% of rated flow

< 140% of retad flow

_'200*F

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_ 200*F d.

Main Steam Line Tunnel Temperature - High e.

Condenser Vacuum - Low-

,3 ~!_ inches Hg vacuum 3 7 inches Hg vacuum g

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Turbine Building Area Temp - High

< 200*F

< 200*P.

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Main Stack Radiation - High

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=TABt.E 3.3.2-2 (Continued)'

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E ISOLATION ACTUATION INSTRUMENTATION SETPOINTS c1 M

ALLOWABLE 3

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8 TRIP FUNCTICH ZIP SETPOlWT

'VALUE-e 2:

y 5.

SHUTDOWN COOLING SYSTEM ISOLATI3N s.

Reactor Vessel Water Level - Low ',evel 1

' 3 162.5 inches (a) 162.5 inches ")

I b.

Keactor Steam Dome Pressure - High d140psig-

< 140 psig 1

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(a) Vessel water levels refer to REFERENCE LEVEL ZERO.

(b) Establish alarm / trip setpoints per the methodology contained in the~OFFSITE DOSE CALCdLATION MAN"AL (CDCM).

(c) The hydrogen water chemistry (HWC) system shall not be placed in service until reactor power reaches 20% of-i l

k RATED THERMAL POWER. After reaching 20% of RATED THERMAL.POWEE, the normal full power background radiation g,

level and associated trip;setpoints may be increased to compensate for _ increased radiation levels as~ a result 4

g of full power operation with hydrogen injection. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after decreasing below 2,0%-~of. RATED THERMAL E

POWER or the HWC system has been shut off, the background level and associated setpoint shall-be rett.rned to the normal full power values. If a power reduction event occurs so that the reactor power,is below 20% of z

l

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RATED THERMAL POWER for longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> without the required setpoint change, control rod motion shall be saspended (except for scram or other emergency action) until the necessary adjustment is made.

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j ENCLOSURE 6-i L

BRUNSWICK STEAM ELECTRIC PIANT, UNITS 1 AND 2 D

NRC DOCEETS 50-325 & 50-324 l

OPERATING LICENSES DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT-MAIN STEAM LINE RADIATION MONITOR SETPOINT CHANGE

' HYDROGEN WATER CHEMISTRY t

IJ&HNICAL SPECIFICATION PAGES - UNIT 2 T

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TABLE'2'2.1-1

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- G rREACTUR PROTECTION SYSTEN' INSTRUMENTATION SETPOINTS-

-4 ALLOWABLE.

8 FUNCTIONAL UNIT TRIP SETPOINT VALUES' C

h 1.

Intermediate Range Mcnitor, Neutron Flux - High(a)

< 120 divisions of full scale

< 120 divisions

~

of full scale' 2.

Average Power Range Monitor Neutron Flux - High, 15%(b).

1 15% of RATED THERMAL POWER

$ 15% of RATED a.

~ THERMAL POWER f

Flow Biased Neutron Flux - High(c)(d)

< (0.66 W + 54%)

,$,(0.66 W + 54%)

i b.

Fixed Neutron Flux - High(d)

< 120% of RATED THERMAL POWER

-$.120% of RATED.

c.

THERMAL POWER t

b 3.

Reactor Vessel Steam Dome Pressure - High

< 1045 psig

.< 1045 psig I

I 4.

Reactor Vessel Water Level - Low, level-1

> +162.5 inches 8}

3 +162.5 inches 83 2

5 l

5.

Main Steam Line Isolation Valve - Closure 'I^

_ 10% closed

._ 10% closed 6.

Main Eteam Line Radiatior. - High(h) 5 3 x full power backgroune'

< 3.5 x full power-

-l.

background.

l 7.

Drywell Pressure - High

$ 2 psig

< 2 psig f

8.

Scram Discharge Volume Water Level - High 3 109 gallons

-$ 109 gallons o

i 3

9.

Turbine Stor Valve - Closure (f)

< 10% closed-

< 10% closed oe l

10. Turbine control Valve Fast

osure, z

l

,o control Oil-Pressure - Low

- 3 500 psig

~3 500 psig-l l

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REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS s

s p

k-NOTESc

(

(a)- The; Intermediate Range Monitor scram functions are automatically bypassed when,the reactor mode switch is placed in the Run position and the k

Average Power Range. Monitors are on scale.

i (b) This Average Power Range Monitor scram function is a fixed point and is h

increased when the reactor mode switch is placed in the Run posttion..

4 (c) The Average Power Range. Monitor scram function is' varied, Figure 2.2.1-1, 4

i as'a function of recirculation loop flow (W). The trip setting of this i

function must.be maintained in accordance with Specification 3.2.2.

(d) The APRM' 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 responcis directly to instantaneous neutron flux.

(e). The Main Steam Line Isolation Valve-Closure scram function is automatically bypassed when the' reactor mode switch is in other than the Run position.

(f) 'shese scram functions are bypassed when THERMAL POWER is.less than 30% of

[

RATED THERMAL POWER.

(g) Vessel water levels refer to REFERENCE LEVEL ZERO.

(h) The hydrogen water chemistty (HWC) system shall not be placed in service j

until reactor power reaches 20% of RATED THERMAL POWER. After ceaching-

.20% of RATED THERMAL POWER, the normal full power background radiation V

' level end' associated trip setpoints may be increased to compensate for

-increased radiation levels as a result of full power operation with i

hydrogen' injection. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after decreasing'below 20% of RATED THERMAL POWER or the HWC system has been shut off, the background leval and a:sociated setpoint shall be returned to the normal full pawer values.

If a power reduction event occurs no that the reactor power is belo'w 20% of RATED THERMAL POWER for longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> witLout the required setpoint change, control rod motion shall be suspended (except for scram or other emergency action) until the necessary adjustment is made.

BRUNSWICK - JNIT 2 2-5 Amendment No.

a.

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f. L LIMITING SAFETY SYSTEM SETTINGS.

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BASES (Continued) 6,

3.

Reactor Vessel Steam Dome Pressure-High (Continued) t pressure measurement compared to the highest pressure that occurs in the system during a transient. This setpoint is effective at low power / flow F

conditions when the turbine stop valve closure is bypassed.

For a turbine p

trip under these conditions, the transient analysis indicates a considerable marfin to the thermal hydtaulic 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 displactment 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 t

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 the 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 pr' essure 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 tsolation valve closure trip with the mode r

switch in the Run position anticipates the pressure and flux transients which occur _during normal or inadvertent isolation valve closure.

l 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 failure of fuel cladding. At the same time, the Main Steam Line Isolation Valves are closed to limit the release of fission products. The trip setting is high enough above background radiation levels to prevent spurious scratis, yet low enough to promptly detect gross failures in'the fuel cladding.

The Main Steam Line Radiation detectors setpoints may be aojusted prior to placing the hydrogen weter chemistry (HWC) system in service.

If the setpcints are adjusted, the HWC system shall be placed in service or the setpoints shall be returned to the normal full power values within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

If the HWC system is not placed in service and the setpoints are not readjusted within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 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 r

setpoints shall be returned to the normal full power values.

The Technical Specification wording was derived using the EPRI

" Guidelines for Permanent BWR Hydrogen Water Chemistry Installations, 1987 Revision".

',i

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BRUNSWICK - UNIT 2 B 2-6 Amend.nent No.

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ISOLATION ACTUATION INSTRIMENTATION SETPOINTS n

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x ALLOWABLE TRIP FUNCTION TRIP SETPOINT

'VALUE-e z

3 1..

PRIMARY CONTAINMENT ISOLATION u

a.

Reactor Vessel Water Level--

1.

Low, Level 1 3 + 162.5. inches *}

3 + 162.5 inches (a)

I 3 + 112 inches (a)

+ 112 inches (a)~

2.

Low, Level 2 3.

Iow, Level 3 ~

3 + 2.5 in::hes *I 3 + 2.5 inches (a)-

I h.

Drywell Pressure - High 5 2 psig

$ 2 psig U

c.

Main Steam Line y

1.

Radiation - High'

$3xfullguer 53.5xfugpower l

backgrour'd background l

2.

Pressure - Low 3 825 psig 3 825 psig.

3.

Flow - High 3 140% of rated flow

$ 140% of rated flow

~

4.

Flow - High

-< 40% of rated flow

-< 40% of rated-flow d.

Main Steam Line Tunnel Temperature - High 5 200*F

$ 200*F

~

g e.

Condenser Vacuum - Low 3 7 inches Hg vacuum 3 7 inches Hg vacuum

$g f.

Turbine Building Area Temp - High

$ 200*F

< 200*F en 3

g.

Main Stack Radiation - High (b)

(o) 3 N

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. TABLE 3.3.2-2=(Continued)

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C-E E

ISOIATION ACTUATION -INS 11tUMENTATION SETPOINTS E

' ALLOWABLE ~

TRIP FUNCTION TRIP SETPOINT VALUE C

. z 4

5.

SHUTDOWW COOLING SYSTEM ISOLATION

~

3 162.5 inches (a) 162.5-inches (a) a.

Reactor Vessel Water Level - Low Level 1 b.

Reactor Steam Dome Pressure - High

< 140 psig 140 psig u5 M

j (a) Vessel water levels refer to REFERENCE LEVEL ZERO.

(b) Establish alarm / trip setpoints per the a:ethodology contained in the OFFSITE DOSE CALCUIATION MANUAL (ODCM).

3 (c) The hydrogen water chemistry (HWC) systern.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 i

level and associated trip setpoints may be increased to compensate for increased radiation levels as a result 4

of full power operation with hydrogen injection ~.. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter decreasing below 20%- of RATED THERMAL -

f, POWER or the HWC system has been shut off, the background level and assoi.inted setpoint shall be returned to the normal full power values. If a power reduction event occurs so that the reactor power is below 20% of 2o RATED THERMAL POWER for longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> without the required setpoint change, control rod motion shall be suspended (except for scram or other emergency action) until the necessary adjustment ~is made.

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