Text

Proposed Tech Specs Re RCS Conductivity
	ML20094A086
Person / Time
Site:	Brunswick
Issue date:	10/23/1995
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20094A077	List: BSEP-95-0383, Application for Amends to Licenses DPR-71 & DPR-62,revising Action B of TS 3.4.4 to Allow for Chemical Decontamination of RCS During Refueling Outages; ML20094A086;
References
	NUDOCS 9510300164
	Download: ML20094A086 (25)
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I ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS. 50-325 AND 50-324 OPERATING LICENSE NOS. DPR 71 AND DPR-62 REQUEST FOR-LICENSE AMENDMENTS l

REACTOR COOLANT SYSTEM CONDUCTIVITY i

PAGE CHANGE INSTRUCTIONS UNIT 1 Removed page Inserted page

-3/4 4 3/4 4-7 3/4 4-9 3/4 4-9 8 3/4 4-3 B 3/4 4-3 8 3/4 4-4 B 3/4 4-4 PAGE CHANGE INSTRUCTIONS UNIT 2 Removed page Inserted page 3/44-7 3/4 4 3/4 4-9 3/4 4-9 8 3/4 4-3 B 3/4 4-3 B 3/4 4-4 B 3/4 4-4 9510300164 951023

.PDR -ADOCK 05000324

-L P_-

.PDR i

' ;b.-

y.

ENCLOSURE 5 i-BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 l

NRC DOCKET NOS. 50-325 AND 50-324 OPERATING LICENSE NOS. DPR 71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS REACTOR COOLANT SYSTEM CONDUCTIVITY MARKED-UP TECHNICAL SPECIFICATION PAGES - UNIT 1 4

W i-i ij l'

f,-

}

i I

REACTOR COOLANT SYSTEM j

3/4.4.4 CHEMISTRY LIMITING CONDITION FOR OPERATION 3.4.4 The chemistry of the reactor coolant system shall be maintained within the limits specified in Table 3.4.4-1.

.APPLICABILITYt. " ; :.11

'.n :.

4 MERMIONAL CONDITIONS {,f.,3,4 and 5 3

1

- ACTION:

a.

In' OPERATIONAL CONDITION 1, 2, and 32 1.

With the conductivity or chloride concentration exceeding the limits specified in Table 3.4.4-1, but less than 10 umho/cm at 25'c and less than 0.5 ppm, respectively, operation may continue for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and this condition need not be reported to i

the commission provided that o'peration under these conditions shall not exceed 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year. The provisiens of j

Specification 3.0.4 are not applicable.

2.

With the conductivity or chloride concentration exceeding the limits specified in Table 3.4.4-1 for more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during one continuous time interval or with the conductivity exceeding j

10 pmho/cm at 25'c or chloride exceeding 0.5 ppm, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

In OPERATioNM. C09DITIMS 4 and 5*

!! ^"-

"i-^gith the conductivity and/or chloride b.

^tconcentration of the reactor coolant in excess of the limit specified in Table 3.4.4-1, restore the conductivity and/or chloride concentration to within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

.h 6

Excep cluring(planned chemical decontamin klon a.eWiWs{wMh4he re.aa+ c ve d.hetd).

BRUNSWICK - UNIT 1 3/4 4-7 Amendment No. S!P*

i Fog Ir4FORMAThoN ONLY REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.4 The reactor coolant shall be determined to be within the specified chemistry limit by:

Analyzing a sample of the reactor coolant for conductivity and a.

chlorides at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and b.

Continously recording the conductivity of the reactor coolant, or Analyzing a sample of the reactor coolant for conductivity at least c.

once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when all of the continuous recording conductivity-monitors are inoperable.

\\.

M i

n 4

..s RETY?ED TECH. SPECS.-

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{.

f e

I i

i TABLE 3.4.4-1 as Ez REACTOR COOLANT SYSTEM CHEMISTRY LIMITS E

s OPERATIONAL CONDITION CHLORIDES CONDUCTIVITY (ushos/cm 025 C)

I C:

1

< 0.5 ppe

< 2.0 3

H e

2

< 0.2 ppe

< 2.0 At 211 ::Ezr tin _

3,4 and 5

< 0.2 ppm (10.0 3

L u

L i

e 6

i k

p a :

3 r

LU Except duri planned chemical decent =m'in.Uon acwisesf uub h reade-vessel dauded).

., q i

J31

! ;!!p

. m

!~

'<.L, FOR INFORMATiopd ONLY r

k REACTOR COOLANT SYSTEM

~

j BASES

~

These specifications are based on the guidance of General Electric SIL f380, Rev. 1, 2-10-84.

3 3/4.42 ' SAFETY / RELIEF VALVES

)

The reactor coolant system safety valve function of the safety-relief valves operate to prevent the system from being pressurized above the Safety.

Limit of 1325 psig. The system is designed to meet the requirements 'of the 4

ASME Boiler and Pressure Vessel Code Section III for the pressure vessel and 4

ANSI B31.1, 1975, Code for the reactor coolant system piping.

3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE

}'

'3/4.4.3.1-LEAKACE DETECTION SYSTEMS i

The RCS leakage detection systems required by this specification are'

' provided to monitor and detect. leakage f rom the Reactor Coolant Pressure.

j Boundary. These detection systems are consistent with the recommendations of Regulatory Culde 1.45, " Reactor Coolant Pressure Boundary Leakage Detection l

Systems."

3/4.4.3.2 OPERATIONAL LEAKACE The allowable leakage rates of coolant from the reactor coolant system

],

have been based on the predicted and experimentally observed behavior of cracks in pipes. The normally expected background leakage due to equipment design and the detection capability of the instrumentation for determining s

i system leakage was also considered. The evidence obtained from experiments l

suggests that for leakage somewhat greater than that specified for unidentified leakage, the probability is small that the imperfection or crack associated with such leakage would grow rapidly. However, in all cases, if the leakage race.s exceed the values specified or the leakage is located and l:

known to be PRESSURE BOUNDARY LEAKACE, the reactor will be shut down to allow further investigation and corrective action. Monitoring leakage at eight hour intervals is in conformance with the 12/21/89 NRC SER for CL 88-01.

i 3/4.4.4 CHEMISTRY 5

I The reactor water chemistry limits are established to prevent damage to the reactor materials in contact with the coolant. Chloride limits are specified to prevent stress corrosion cracking of.the stainless steel. The

'effect'of chloride is not as' great when the oxygen concentration in the coolant is low; thus, the higher limit on chlorides is permitted during full power operation. During shutdown and refueling operations, the temperature

necessary for stress corrosion to occur is not present.

Conductivity measurements are required on a continuous basis since changes in this parameter are an indication of abnormal conditions. When the conductivity is within limits, the pH, chlorides, and other impurities

.affecting conductivity must also be within their acceptable limits. With the 5

)

conductivity outside the limits, additional samples must be examined to ensure that.the chlorides are not exceeding the limits.

BRUNSWICK - UNIT 1-B 3/4 4-2 Amendment No. M 4

REACTOR COOLANT SYSTEM h

BASES u

The surveillance requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.

---* INSCRT PARAGEAPH CATTACNEED) 3/4.4.5 SPECIFIC ACTIVITY l

i The limitations on the specific activity of the primary coolant ensure that the 2-hour thyroid and whole body doses resulting from a main steam line failure outside the containment during steady state operation will not exceed small fractions of the dose guidelines of 10 CFR 100. Permitting operation to continue for limited time periods with higher specific activity levels.

accommodates short-term lodine spikes which may be associated with power level changes, and is based on the fact that a steam line failure during these short

~

time periods is considerably less likely. Operation at the higher activity

' levels, therefore, is restricted to a small. fraction of the unit's total operating time. The upper limit of coolant iodine concentration during short-term iodine spikes ensures that the thyroid dose from a steam line failure will not exceed 10 CFR Part 100 dose guidelines.

Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency of isotopic analysis following power changes may be permissible if justified by the data obtained.

Closing the main steam line isolation valves prevents the release of activity to the environs should the steam line rupture occur. The surveillance requirements pro.ide adequate assurance tha't excessive specific v

activity levels in the reactor coolant will be detected in sufficient time to take corrective action.

1 3/4.4.6 PRESSURE / TEMPERATURE LIMITS All components in the Reactor Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pressure changes. These cyclic loads are introduced by normal load transients, reactor trips, and start-up and shutdown operations. The various categories of load cycles used for design purposes are provided in Section 4.2 of the FSAR.

During start-up and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic operation.

l During heatup, the thermal gradients in the reactor vessel wall produce j

thermal stresses which vary from compressive at the inner wall to tensile at the outer wall. Thermal-induced compressive stresses tend to alleviate the tensile stresses induced by the internal pressure. During cooldown, thermal gradients to be accounted for are tensile at the inner wall and compressive at 1

the outer wall.

1 BRITNSWICK - IJNIT 1 B 3/4 4-3 Amendment No. M i

I

INSERT PARAGRAPH:

In order to reduce personnel radiation exposure, chemical decontamination of portions of the reactor coolant system may be performed during shutdown. During the chemical decontamination process, the injection of chemical solvents may cause the reactor coolant system conductivity and chloride measurements to increase above the limits. The solvents that are selected for use in performing the chemical decontamination process are selected and evaluated to ensure their chemical reactivity will not adversely impact components or the structuralintegrity of the reactor coolant system. Because decontamination activities are performed at temperatures significantly less than normal operating temperatures, the chemical reactivity of these solvents will not increase the likelihood of stress corrosion occurring nor affect those stress corrosion cracks that may already be present.

e ENCLOSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS. 50-325 AND 50-324 OPERATING LICENSE NOS. DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS REACTOR COOLANT SYSTEM CONDUCTIVITY i

MARKED-UP TECHNICAL SPECIFICATION PAGES - UNIT 2

)

i i

?

, - =

e.,e,

REACTOR COOLANT SYSTEM 3/4.4.4 CHEMISTRY LIMITING CONDITION FOR OPERATION L3.4.4. The chemistry of the reactor coolant system shall be maintained within the limits specified in Table 3.4.4-1.

APPLICABILITY:. OPERATIONAL CONDITtoNS 1,2 3 % 4, and 5.s a

..f ACTION In OPERATIONAL CONDITION 1, 2, and 38 a.

1.

With the conductivity or chloride concentration exceeding the

-limits specified in Table 3.4.4-1, but less than 10 umho/cm at 25'c and less than 0.5 ppe, respectively, operation may continue for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and this condition need not be reported to the Commission provided that operation under these conditions shall not exceed 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year. The provisions of Specification 3.0.4 are not applicable.

2.

With the conductivity or chloride concentration exceeding.the limits specified in Table 3.4.4-1 for more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during one continuous time interval or with the conductivity exceeding 10 paho/cm at 25'C or chlo'ide exceeding 0.5 ppe, be in at least r

HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN

~

within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

in Off. RATIONAL CbHDmoNS 4 and 5*

b.

": :__ :th:: tir::gwith the conductivity and/or chloride concentration of the reactor coolant in excess of the limit specified in Table 3.4.4-1, restore the conductivity and/or chloride concentration to within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

i 4

)

i i

Escapt during p)anneJ chemieal deconhnin.En acHvi+ies(wnh the f1Ackr vetStk defueled),

i BRUNSWICK - UNIT 2 3/4 4-7 Amendment No. 449-3:

. ~.

FOR INFORPAA'TtoN ONLY REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.4 The reactor coolant shall be determined to be within the specified chemistry limit by Analysing a sample of the reactor coolant for conductivity and a.

chloride at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and

b..

Continuously recording the conductivity of the reactor coolant, or Analyzing a sample of the reactor coolant for conductivity at c.

least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when all of the continuous recording conductivity monitors are inoperable.

O G

4 b

a i

9 4

RETYPED TECH. SPECS.

"~ * ~ ~ ~ ' ~ ~

j _.

TABLE 3.4.4-1 g

-E REACTOR COOLANT SYSTEM CHEMISTRY LIMITS CONDUCTIVITY (pahos/cm 825 C) 0 Q

OPERATIONAL CONDITIONS CHLORIDES 1

< 0.5 ppe

< 2.0 l

I

,g 2

< 0.2 ppe

< 2.0 l

d

.n 3, 4, and 5"

< 0.2 ppe

<10.0 A 211 :" r t*---

i e

l l

t

,o i

L a i

it ll lL f

Except durig planned chemic.4 deconbninchen odivMes(uilh he renckor vassd debeled).

i.

iL r

p.

e.

~

Fog IsrogMATioN ONLY l

REACTOR COOLANT SYSTEM g:

g BASES-These. specifications are based on the guidance of General Electric SIL #380, Rev. 1, 2-10-84.

1 3/4.4.2 SAFETY / RELIEF VALVES The reactor coolant system' safety valve function of the safety-relief valves operate to prevent the system from being pressurized above the Safety Limit of 1325 psig. The system is designed to meet the requirements of the-ASME' Boiler,and Pressure Vessel Code Section III for the pressure vessel and ANSI B31.1, 1967, code for the reactor coolant system piping.

I' 3/4.4.3-REACTOR COOLANT SYSTEM LEAXACE 3/4.4.3.1 LEAKAGE DETECTION SYSTEMS i

The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundary. These detection systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection 4

Systems."

i 3/4.4.3.2 OPERATIONAL LEAKACE i

The allowable leakage rates of coolant from the reactor coolant system have been based on the predicted and experimentally observed behavior of 4

cracks in pipes. The normally expected background leakage due to equipment design and the detection capability of the instrumentation for determining

[

system leakage was also considered. The evidence obtained from experiments

~

suggests that for leakage somewhat greater than that specified for unideritified leakage, the probability is small that the imperfection or crack 4

associated with such leakage would grow rapidly. However, in all cases, if the leakage rates exceed the values specified or the leakage is located and known to be PRESSURE BOUNDARY LEAXAGE, the reactor will be shut down to allow further investigation and corrective action. Monitoring leakage at eight hour intervals is in conformance with the 12/21/89 NRC SER for CL 88-01.

i 3/4.4.4 CHEMISTRY The reactor water chemistry limits are established to prevent damage to the reactor materials in contact with the coolant. Chloride limits are specified to prevent stress corrosion cracking of the stainless steel. The effect of chloride is not as great when the oxygen concentration in the coolant is lowl thus, the higher limit on chlorides is permitted during full i

power operation. During shutdown and refueling operations, the temperature necesssey for stress corrosion to occur is not present.

Conductivity measurements are required on a continuous basis since changes in this parameter are an indication of abnormal conditions. When the conductivity is within limits, the pH, chlorides, and other impurities affecting conductivity must also be within their acceptable limits. With the

,]

conductivity outside the limits, additional samples must be examined to ensure

./ -

that the chlorides are not exceeding the limits.

i BRUNSWICK - UNIT 2 B 3/4 4-2 Amendment No.

a

~

1 1---

9 4

m

m..

m

.c REACTOR COOLANT SYSTEM BASES The surveillance. requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.

% INGERT PARAGRAPH (ATTACHED) 3/4.4.5 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the 2-hour thyroid and whole body doses resulting from a main steam line failure outside the containment during steady state operation will not exceed small fractions of the dose guidelines in 10CFR 100. Permitting operation to continue for limited time periods with higher specific activity' levels accommodates short-term iodine spikes which may be associated with power level changes, and is based on the fact that a steam line failure during these short

. time periods is considerably less likely. Operation at the higher activity levels, therefore, is restricted to a small fraction of the unit's total operating time. The upper limit of coolant iodine concentration during short-term lodine spikes ensures that the thyriod dose from a steam line failure will not exceed 10 CFR Part 100 dose guidelines.

Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency of isotopic analysis following power changes may be permissible, if justified by

~

.)

the data obtained.

Closing the main steam line isolation valves prevents the release of activity to the. environs should the steam line rupture occur. The surveillance requirements provide adequate assurance that excessive specific activity levels in the reactor coolant will be detected in sufficient time to take corrective action.

3/4.4.6 PRESSURE / TEMPERATURE LIMITS All components in the Reactor Coolant System are designed to withstand the These ef fects of cyclic loads due to system temperature and pressure changes.

cyclic loads are introduced by normal load transients, reactor trips, and start-up and shutdown operations. The various categories of load cycles used for design. purposes are provided in Section 4.2 of the FSAR.

During start-up and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic operation.

During heatup, the thermal gradients in the reactor vessel wall produce thermal stresses which vary from compressive at the inner wall to tensile at the outer wall. Thermally induced compressive stresses tend to alleviate the tensile' stresses induced by the internal pressure. During cooldown, thermal gradients to be accounted for are tensile at the inner wall and compressive at the outer wall.

8 BRUNSWICK - UNIT 2 B 3/4 4-3 Amendment No. JJF "-

INSERT PARAGRAPH:

In order to reduce personnel radiation exposure, chemical decontamination of portions of the reactor coolant system may be performed during shutdown. During the chemical' decontamination process, the injection of chemical solvents may cause the reactor coolant system conductivity and chloride measurements to increase above the limits. The solvents that are selected for use in performing the chemical decontamination process are selected and evaluated to ensure their chemical reactivity will not adversely impact components or the structuralintegrity of the reactor coolant system. Because decontamination activities are performed at temperatures significantly less than normal operating temperatures, the chemical reactivity of these solvents will not increase the likelihood of stress corrosion occurring nor affect those stress corrosion cracks that may already be present.

3 ENCLOSURE 7

- BP.UNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS 50-325 AND 50-324 OPERATING LICENSE NOS, DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS 1

REACTOR COOLANT SYSTEM CONDUCTIVITY 1

TYPED TECHNICAL SPECIFICATION PAGES - UNIT 1 P

,r-*

w'w-e T

r

- =

u =---

--m

-

r-=4

, -- - =

w

REACTOR COOLANT SYSTEM 3/4.4.4 CHEMISTRY LIMITING CONDITION FOR OPERATION 3.4.4 The chemistry of the reactor coolant system shall be maintained within the limits specified in Table 3.4.4-1.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2. 3. 4. and 5*.

I ACTION:

a.

In OPERATIONAL CONDITIONS 1, 2. and 3:

1 1.

With the conductivity of chloride concentration exceeding the limits specified in Table 3.4.4-1 but less than 10 ymbo/cm at 25*C and less than 0.5 ppm. respectively operation may continue for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and this condition need not be reported to the Commission provided that operation under these conditions shall not exceed 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year. The provisions of Specification 3.0.4 are not applicable.

2.

With the conductivity or chloride concentration exceeding the limits specified in Table 3.4.4-1 for more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during one continuous time interval or with the conductivity exceeding 10 pmho/cm at 25'C or chloride exceeding 0.5 ppm.

be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b, In OPERATION CONDITIONS 4 and 5* with the conductivity and/or i

chloride concentration of the reactor coolant in excess of the i

limit specified in Table 3.4.4-1 restore the conductivity and/or chloride concentration to within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ,

. Except during lanned chemical decontamination activities (with the reactor vessel defueled.

BRUNSWICK - UNIT 1 3/4 4-7 Amendment No.

l

i e

TABLE 3.4.4-1 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS OPERATIONAL CONDITION CHLORIDES CONDUCTIVITY Onhos/cm 0 25 C) 1

< 0.5 ppm

< 2.0 2

< 0.2 ppm

< 2.0 3, 4. and 5*

< 0.2 ppm

<10.0 l

Except during planned chemical decontamination activities (with the reactor vessel defueled).

BRUNSWICK - UNIT 1 3/4 4-9 Amendment No.

I

e REACTOR' COOLANT SYSTEM BASES The surveillance requirements provide adecuate assurance that concentrations in excess of the limits will be cetected in sufficient time to take corrective action.

In order to reduce personnel radiation exposure, chemical decontamination of portions of the reactor coolant system may be performed during shutdown. During the chemical decontamination process, the injection i

of chemical solvents may cause the reactor coolant system conductivity and i

chloride measurements to increase above the limits. The solvents that are selected for use in performing the chemical decontamination process are selected and evaluated to ensure their chemical reactivity will not adversely impact components or the structural integrity of the reactor coolant system.

Because decontamination activities are performed at temperatures significantly less than normal operating temperatures. the chemical reactivity of these solvents will not increase the likelihood of stress corrosion occurring nor affect those stress corrosion cracks that may already be present.

3/4.4.5 SPECIFIC ACTIVITY l

The limitations on the specific activity of the primary coolant ensure that the 2-hour thyroid and whole body doses resulting from a main steam line failure outside the containment during steady state operation will not exceed small fractions of the dose guidelines in 10CFR 100.

Permitting operation to i

continue for limited time periods with higher specific activity levels accommodates short-term iodine spikes which may be associated with power level changes, and is based on the fact that a steam line failure during these short time periods is considerably less likely. Operation at the higher activity levels, therefore, is restricted to a small fraction of the unit's total operating time. The upper limit of coolant iodine concentration during short-term iodine spikes ensures that the thyroid dose from a steam line failure will not exceed 10 CFR Part 100 dose guidelines.

Information obtained on iodine spiking will be used to assess the parameters associated with spiking )henomena. A reduction in frequency of isotopic analysis following power c1anges may be permissible, if justified by the data obtained.

Closing the main steam line isolation valves prevents the release of activity to the environs should the steam line rupture occur. The surveillance requirements provide adequate assurance that excessive specific activity levels in the reactor coolant will be detected in sufficient time to take corrective action.

r

.3/4.4.6 -PRESSORE/ TEMPERATURE LIMITS All components in the Reactor Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pressure changes.

These cyclic loads are introduced by normal load transients, reactor trips, and start up and shutdown operations. The various categories of load cycles used for design purposes are provided in Section 4.2 of the FSAR.

During B 3/4 4-3 Amendment No.

I BRUNSWICK-- UNIT 1

., o REACTOR COOLANT SYSTEM BASES PRESSURE /TEMPERAT1JRE LIMITS (Continued) start-up and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic operation.

During heatu), the thermal gradients in the reactor vessel wall produce thermal stresses w11ch vary from compressive at the inner wall to tensile at the outer wall. Thermal-induced compressive stresses tend to alleviate the tensile stresses induced by the internal pressure.

During cooldown, thermal gradients to be accounted for are tensile at the inner wall and compressive at the outer wall.

The reactor vessel materials have beeri tested to determine their initial RTm.

The results of these tests are shown in GE NED0 24161.

Reactor operation and resultant fast neutron. E>l Mev, fluence will cause an increase in the RTm.

Therefore, an adjusted reference temperature, based upon the fluence, can be predicted using the proper, revision of Regulatory Guide 1.99.

The pressure-temperature limit curve Figures 3.4.6.1-1, 3.4.6.1-2, and 3.4.6.1-3a through 3.4.6.1-3c include predicted adjustments for this shift in RTm at the end of indicated EFPY, as well as adjustments to account for the location of the pressure sensing instruments.

The actual shift in RTm of the vessel material will be checked periodically during operation by removing and evaluating, in accordance with ASTM E185-82, reactor vessel material irradiation surveillance specimens installed near the inside wall of the reactor vessel in the core area.

Since the neutron spectra at the irradiation samples and vessel inside radius vary little, the measured transition shift for a sample can be adjusted with confidence to the adjacent section of the reactor vessel.

The pressure-temperature limit lines shown in Figures 3.4.6.1-1, 3.4.6.1-2 and 3.4.6.1-3a through 3.4.6.1-3c have been provided to assure compliance with the minimum temperature requirements of the 1983 revision to Appendix G of 10CFR50. The conservative method of the Standard Review Plan has been used for heatup and cooldown.

The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided in Table 4.4.6.1.3-1 to assure compliance with the requirements of ASTM E185-82.

BRUNSWICK - UNIT 1 B 3/4 4-4 Amendment No, I

.,, sa ENCLOSURE 8' 1

BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS. 50 325 AND 50-324

-OPERATING LICENSE NOS. DPR 71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS REACTOR COOLANT SYSTEM CONDUCTIVITY TYPED TECHNICAL SPECIFICATION PAGES UNIT 2 i

j l

9 I

I 4

3 l

.g.

3"

4 y

REACTOR COOLANT SYSTEM

.3/4.4.4 CHEMISTRY LIMITING CONDITION FOR OPERATION.

3.4.4 The chemistry of the reactor coolant system shall be maintained within the limits specified in Table 3.4.4-1.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2. 3, 4, and 5*.

I ACTION:

a.

In OPERATIONAL CONDITIONS 1, 2. and 3:

1 1.

With the conductivity of chloride concentration exceeding the limits specified in Table 3.4.4-1, but less than 10 mho/cm at 25 C and less than 0.5 ppm respectively, operation may continue for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and this condition need not be reported to the Commission provided that operation under these conditions shall not exceed 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year. The provisions of Specification 3.0.4 are not

' applicable.

2.

With the conductivity or chloride concentration exceeding the limits specified in Table 3.4.4-1 for more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during one continuous time interval or with the conductivity exceeding 10 gmho/cm at 25 C or chloride exceeding 0.5 ppm, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in 4

COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

j b.

In OPERATIONAL CONDITIONS 4 and 5* with the conductivity and/or I

chloride concentration of the reactor coolant in excess of the limit specified in Table 3.4.4-1. restore the conductivity and/or chloride concentration to within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

i l

i

)

Except during planned chemical decontamination activities (with the reactor vessel defueled).

BRUNSWICK - UNIT 2 3/4 4-7 Amendment No.

I 4

c...

t. *

I TABLE 3.4.4-l' REACTOR COOLANT SYSTEM CHEMISTRY LIMITS i

OPERATIONAL CONDITION CHLORIDES CONDUCTIVITY (umhos/cm @ 25*C) 1-'

< 0.5 ppm

< 2.0 2

< 0.2 ppm

< 2.0

3. 4, and 5*-

< 0.2 ppm

<10.0 l

\\

)

Except during lanned chemical decontamination activities (with the reactor

-vessel-defueled.

BRUNSWICK - UNIT 2 3/4 4-9

-Amendment No.

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7, m -

REACTOR COOLANT SYSTEM

' BASES The surveillance requirements provide adecuate assurance that concentrations in excess of the limits will be cetected in sufficient time to take corrective action.

In order to reduce personnel radiation exposure, chemical decontamination of portions of the reactor coolant system may be performed during shutdown.

During the chemical decontamination process, the injection of chemical solvents may cause the reactor coolant system conductivity and chloride measurements to increase above the limits. The solvents that are selected for use in performing the chemical decontamination process are selected and evaluated to ensure their chemical reactivity will not adversely impact components or the structural integrity of the reactor coolant system.

Because decontamination activities are performed at temperatures significantly less than normal operating temperatures, the chemical reactivity of these solvents will not increase the likelihood of stress corrosion occurring nor affect those stress corrosion cracks that may already be present.

3/4.4.5 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the 2-hour thyroid and whole body doses resulting from a main steam line failure outside the containment during steady state operation will not exceed small fractions of the dose guidelines in 10CFR 100.

Permitting operation to continue for limited time periods witn higher specific activity levels accommodates short-term iodine spikes which may be associated with power level changes, and is based on the fact that a steam line failure during these short time periods is considerably less likely. Operation at the higher activity levels, therefore, is restricted to a small' fraction of the unit's total

)

term iodine spikes ensures that the thyriod dose from a steam line faig short operating time.

The upper limit of coolant iodine concentration durin

ure will not exceed 10 CFR Part 100 dose guidelines.

1 Information obtained on iodine spiking will be used to assess the parameters associated with spiking )henomena. A reduction in frequency of isotopic analysis following power clanges may be permissible, if justified by the data obtained.

Closing the main steam line isolation valves prevents the release of activity to the enviros should the steam line rupture occur. The surveillance requirements provide adequate assurance that excessive specific j

activity levels in the reactor coolant will be detected in sufficient time to take corrective action.

3/4.4.6 PRESSURE / TEMPERATURE LIMITS All components in the Reactor Coolant System are designed to withstand the effects of cycl!c loads due to system temperature and pressure changes.

i These cyclic loads are introduced by normal load transients, reactor trips, and start-up and shutdown operations. The various categories of load cycles used for design purposes are provided in Section 4.2 of the FSAR.

During

' BRUNSWICK - UNIT 2 B 3/4 63 Amendment No.

l l

3

C (ao n

REACTOR COOLANT SYSTEM BASES

. PRESSURE / TEMPERATURE LIMITS (Continued) start-up and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic operation.

During heatu), the thermal gradients in the reactor vessel wall produce thermal stresses w11ch vary from compressive at the inner wall to tensile at the outer wall. Thermally induced compressive stresses tend to alleviate the tensile stresses induced by the internal pressure.

During cooldown, thermal gradients to be accounted for are tensile at the inner wall and compressive at the outer wall.

The reactor vessel materials have been tested to determine their initial RTer. The results of these tests are shown in GE NEDO 24161. Reactor operation and resultant fast neutron, E>l Mev, fluence will cause an increase in the RTor.

Therefore, an adjusted reference temperature, based upon the i

fluence, can be predicted using the proper revisia of Regulatory Guide 1.99.

The pressure / temperature limit curves Figures 3.4.6.1-1, 3.4.6.1-2, and 3.4.6.1-3a through 3.4.6.1-3c include predicted adjustments for this shift in RTor at the end of indicated EFPY, as well as adjustments to account for the location of the pressure-sensing instruments.

The actual shift in RTor of the vessel material will be checked periodically during operation by removing and evaluating, in accordance with ASTM E185-82, reactor vessel material irradiation surveillance specimens installed near the inside wall of the reactor vessel in the core area.

Since the neutron spectra at the irradiation samples and vessel inside radius vaty little, the measured transition shift for a sample can be adjusted with confidence to the adjacent section of the reactor vessel.

The pressure / tem)erature limit lines shown in Figures 3.4.6.1-1, 3.4.6.1-2, and 3.4.6.1-3a t1 rough 3.4.6.1-3c have been provided to assure compliance with the minimum temperature requirements of the 1983 revision to A)pendix G of 10CFR50. The conservative method of the Standard Review Plan las been used for heatup and cooldown.

The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided in Table 4.4.6.1.3-1 to assure compliance with the requirements of ASTM E185-82.

BRUNSWICK - UNIT 2 B 3/4 4-4 Amendment No.

I

ML20094A086

Text

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