ML20249C637

Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05

ML20249C637
Person / Time
Site:	Sequoyah
Issue date:	06/26/1998
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20249C633	List: ML20249C632 ML20249C637
References
GL-95-05, GL-95-5, NUDOCS 9806300465
Download: ML20249C637 (22)

Text

. _ _ _ _ _ _ _ _ _ - _ - _ _

ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY l

SEQUOYAH PLANT (SQN)

UNITS 1 and 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-98-02 MARKED PAGES I.

AFFECTED PAGE LIST Unit 1 l

3/4 4-19 3/4 4-21 3/4 4-22 B3/4 4-4a B3/4 4-5 Unit 2 3/4 4-24 3/4 4-26 3/4 4-27 B3/4 4-4 B3/4 4-5 II.

MARKED PAGES See attached.

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9806300465 980626 i

PDR ADOCK 05000327 P

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REACTOR COOLANT SYSTEM

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3/4.4.8 SPECIFIC.. ACTIVITY LIMITING CONDITION FOR OPERATION i

I 3.4.8 The specific activity of the primary coolant shall be limited to:

{

Less than or equal to g microcuries/ gram DOSE EQUIVALENT I-131, a.

and

{4{St}

b.

Less than or equal to 100/E microcuries/ gram.

APPLICABILITY:

MODES 1, 2, 3, 4 and 5 ACTION:

1 MODES 1, 2 and 3*

R121 With the specific activity of the primary coolant greater than a.

• g

,,let microcuries/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with T less than 500 F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, avg b.

With the specific activity of the primary coolant greater than 100/E R121

(

microcuries/ gram, be in at least HOT STANOBY with T less than 500 F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

avg MODES 1, 2', 3, 4 and 5 With the specific activity of the primary coolant greater than a.

e*gf p microcuries/ gram DOSE EQUIVALENT I-131 or greater than 100/E l

microcuries/ gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits.

~,

R121 "With T greater than or equal 500*F.

avg SEQUOYAH - UNIT 1 3/4 4-19 Amendment No. 36, 117 June 19, 1989

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DOSE EQUIVALENT l-131 Primary Coolant Specific Activity Limit Versus f

Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity >.Mfuci/ gram Dose Equivalent 1131 Yo.55 l

3 SEQUOYAH - UNIT 1 3/4 4-22 9

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._ ____._ ____.___ _ __._ _ _ _ _ s

3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE

, - ~

[ T j 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS 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 Systems," May 1973.

3/4.4.6.2 OPERATIONAL LEAKAGE i

Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 GPM.

This threshold value is sufficiently low to ensure early detection of additional leakage.

The surveillance requirements for RCS Pressure Isolation Valves provide I

added assurances of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA.

Leakage from the RCS isolation valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.

The 10 GPM IDENTIFIED LEAKAGE limitation provides allowance for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.

TheCONTROLLEDLEAKAGElimitationrestrictsoperationwhenthetotaldlow supplied to the reactor coolant pump seals exceeds 40 GPM with the modulating valve in the supply line fully open at a nominal RCS pressure of 2235 psig.

This limitation ensures that in the event of a LOCA, the safety injection flow will not be less than assumed in the accident analy g

q gg,gg The total steam generator tube leakage lim of 600 g ons per day for I

all steam generators and 150 gallons per day f any o.te eam generator will minimize the potential for a significant leak' age even uring steam line break.

Based on the NDE uncertainties, bobbin coi voltag distribution and crack to growth rate frous the previous inspection, he e cted leak rate following R226 steam line rapture 19 limited to below gpm in the faulted whi will limte the calculated offsite doses to within 10 percent of the FR 100 l

l guidelines.

If the ;,rojected and cycle distribution of crack cations gpm in the faulted results in primary-to-secondary leakage greater than X,Qnal tubes must be loop during a postulated steam line break event, additi removed from service in order to reduce the postulated primary-to-secondary steam'line break leaEE"g'e to belo gpm. -

" ~ ~ ' ~ ~ ~ ~

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PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.

l Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN.

( The ha(,agc yM lso s

n standard operatin/ incorporated into SR).4.6.are acre restrictive than limilg leakage limitJ and.s k intended to provide an additional margin to accommodate a crack which alght grow at a greater than expected rate or unexpectedly extend outside the thickness of the tube support plate.

Hence, the reduced leakage limit, when combined with an effective leak rate 1

\\ nonitoring program, provides additional assurance that>d the plant shut down should a significant R226 leak be experienced & ::r M El it will be detected, an g n a t.faely manner.

i April 9, 1997 SEQUOYAH - UNIT 1 B 3/4 4-4a Amend:nent No. 36, 189, 214, 222 l

l L__ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

REACTOR COOLANT SYSTEM BASES

%e 5"M" The surveillance requirements provide adequate assurance that concentra-tions in excess of the limits will be detected in sufficient time to take corrective action.

3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure

'that the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> doses at the site boundary will not exceed an appro-priately small fraction of Part 100 limits following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM.

The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC of typical site locations.

These values are conservative in that specific site parameters of the Sequoyah Nuclear Plant site, such as site boundary loca

• a and - teorological conditions, were not considered in this evaluation.

,3f he ACTION state. nt permitting POWER OPERATION to continue for limited time p ods with the p imary coolant's specific activity greater than-se)-

equa 1c6'microcuries ram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4 1 accommodates possible iodine spiking phenomenon which may occur following ianges in THERMAL POWER.

Operation with specific activity levels exceeding )<3.4-1 should be limited to no more than 800 hour0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />sc'microcu the limits shown on Figure per year since the activity levels. allowed by Figure 3.4-1 increase the 2-hour i

thyroid dose at the site boundary by a factor of up to 20 following a postulated R121 steam generator tube rupture.

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Reducing T to less-than 500 F prevents the release of activity should 3yg

.a steam generator tube rupture since the saturation pressure of the primary coolant is below the lift pressure of the atmospheric steam relief valves.

The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action.

Information obtained on iodine spiking will be used to assess the parameters a'ssociated with spiking phenomena.

A reduction in

' frequency of isotopic analyses following power changes may be permissible if justified by the data obtained.

i l

l SEQUOYAH - UNIT 1 B 3/4 4-5 Amendment No. 117 June 19, 1989

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REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVITY'

- s LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

Less than or equal to Fdf microcurie per gram DOSE EQUIVALENT I-131, a.

and b.

Less than or equal to 100/E microcuries per gram.

APPLICABILITY:

MODES 1, 2, 3, 4 and 5 ACTION:

MODES 1, 2 and 3*:

R107 a.'

With the specific activity of the primary coolant greater than

,1<0' microcurie per gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 0.35 during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with T less than 500 F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

avg b.

With the specific activity of the primary coolant greater than 100/E R107 i

microcurie per gram,'be 'in at least HOT STANDBY with T less than 500 F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

avg

. MODES 1, 2, 3, 4 and 5:

a.

With the specific activity of the primary coolant greater than microcurie per gram DOSE EQUIVALENT I-131 or greater than 0 3C 100/E microcuries per gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits.

R107

• With T greater than or equal to 500 F.

avg SEQUOYAH - UNIT 2 3/4 4-24 Amendment No. 28,107 June 19, 1989 l

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g 40 50 60 70 80 90 100 20 30 PERCENT OF RATED THERMAL POWER FIGURE 3.41 DOSE EQUIVALENT l-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity >. uCi/ gram Dose Equivalent I 131 f

b SEQUOYAH - UNIT 2 3/4 4-27

t REACTOR COOLANT SYSTEM

• BASES 8

opee 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS 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 i

Rsgulatory Guide 1.45, " Reactor. Coolant Pressure Boundary Leakage Detection Systems," May 1973.

3/4.4.6.2 OPERATIONAL LEAKAGE Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 GPM.

This threshold value is sufficiently low to ensure early detection of additional leakage.

The surveillance requirements for RCS Pressure Isolation Valves provide cdded assurances of valve-integrity thereby reducing the probability of gross volve failure and consequent intersystem LOCA.

Leakage from the RCS isolation valves is IDENTIFIED LEAKAGE and.ill be considered as a portion of the allo,wed limit.

The 10 GPM IDENTIFIED LEAKAGE litnitation provides allowance for a limited r

Emount of leakage from known sources whose presence will not interfere with the

.dstection of UNIDENTIFIED LEAKAGE by the leakage detection systems.

The. CONTROLLED LEAKAGE limitation restricts operation when the total flow supplied to the reactor coolant pump seals exceeds 40 GPM with the modulating valve in the supply line fully open at a nr.7inal RCS pressure of 2235 psig.

This limitation ensures that in the event of e LOCA, *he safety injection flow will not be less than assumed in the accident analyses.

gQ 4ep

^

The total steam generator tube leakage limit 60 ns per day for all steam generators and 150 gallons per day fo'r any one'0 gsteam generator will leakage eve uf during steam line break.

minimize the potential for a significant bobbin coil' voltage'; distribution and crack Bssed on the NDE uncertainties, stosin r:.t'r frcm the previous inspection,/the exp'ected leak rate following. a '

13 steam line rupture is limited to below 3-:-f gpmhn the faulted loop, which will limit the calculated offsite doses to within 10 percent of the 10 CFR 100 guidelines.

If the projected and cycle distribution of crack indications results in primary-to-secondary leakage greater than.3-pgpm in the f aulted loop during a postulated steam line break event, additt nal tubes must be removed from service in order to reduce the postulated rimary-to-secondary team line break leakage to below m.

p PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.

Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN.

A i

( The leakage lialtf incorporated into SR.4.4.6. art more restrictive than the f"Tt5dard operating leakage limitj and.dk intended to provide an additional

\\ nargin to accommodate a crack which night grow at a greater than expected rate f1 or unexpectedly extend outside the thickness of the tube support plate.

g213 Hence, the reduced leakage limit, when combined with an effective leak rate f*O

.aonitoring program, provides additional assurance that,d the plant shut down should a significant leak be experienced -l: scry!cc3 it will be detected, an

\\ in a t APfil 9' 1997 SEQUOYAB imely manner.

B 3/4 4-4 Amendment No. 211, 213 UNrr 2 L_______________.

l' l.

i 1

l REACTOR COOLANT SYSTEM

+

(yig BASES

)

3/4.4.7 CHEMISTRY The limitations on Reactor Coolant System chemistry ensure that corrosion i

of the Reactor Coolant System is minimized and reduces the potential for Reactor Coolant System leakage or failure due to stress corrosion.

Maintaining 1

the chemistry within the Steady State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant.

The associated effects of exceeding the oxygen, chloride and fluoride limits are time and temperature dependent.

Corrosion studies show that operation may be continued with contaminant concentration 4

l levels in excess of the Steady State Limits, up to the Transient Limits, for I

the specified limited time intervals without having a significant effect on the structural integrity of the Reactor Coolant System.

The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concen-trations to within the Steady State Limits.

The surveillance requirements provide adequate assurance that concentrations

]

in excess of the limits will be detected in sufficient time to take corrective action.

j 1

(

3/4.4.8 SPECIFIC ACTIVITY l '

The 1, imitations on the specific activity of the primary coolant ensure that the resulting 2-hour doses at the site boundary will not exceed an appropriately small fraction of Part 100 limits following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM.

The values for the limits on specific activity represent limits based upon a parametric evaluation by the NRC of typical site locations.

These values are conservative in that specific site parameters of the bequoyah site,7 uch e site boundary location 1

and meteorological conditions, kere not considered in this evaluation.

1 The ACTION statement permitting POWER OPERATICN to continue for limited time periods with the primary' coolant's specific ac?.ivity greater than dw O.3f microcuries/ gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER Operation with specific activity levels exceedingFt1 microcuries/ gram DOSE EQUIVALENT I 131 but within the limits shown on Fidure 3.4-1 should be limited to no more than 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> per i '

year since the act-vity levels allowed by Figure 3.4-1 increase the 2-hour R107 thyroid dose at thp site boundary by a factor of up to 20 following a postulated steam nerator tube rupture.

(

SEQUOYAH - UNIT 2 8 3/4 4-5 Amendment No.107 June 19, 1989

i ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (SQN)

UNITS 1 and 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-98-02 REVISED PAGES I.

AFFECTED PAGE LIST Unit 1 3/4 4-19 3/4 4-21 3/4 4-22 B3/4 4-4a B3/4 4-5 Unit 2 3/4 4-24 3/4 4-26 3/4 4-27 B3/4 4-4 B3/4 4-5 II.

REVISED PAGES See attached.

l E3-1

6 REACTOR COOLANT SYSTEM 3/4.4.0 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specif' activity of the primary coolant shall be limited to:

Less than or equal to 0.35 microcuries/ gram DOSE EQUIVALENT I-131, l

a.

and b.

Less than or equal to 100/5 microcuries/ gram.

APPLICABILITY: MODES 1, 2,

3, 4 and 5 ACTIQM:

MODES 1, 2 and 3*

With the specific activity of the primary coolant greater than R121 a.

0.35 microcuries/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> l

during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at lecst HOT STANDBY with T less than 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

avg b.

With the specific activity of the primary coolant greater than 100/5 lR121 microcuries/ gram, be in at least HOT STANDBY with T less than 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

avg MODES 1, 2,

3, 4 and 5 With the specif.c activity of the primary coolant greater than a.

0.35 microcuries/ gram DOSE EQUIVALENT I-131 or greater than 1007E l

microcuries/ gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits.

R121

• With T greater than or equal 500*F.

SEQUOYAH - UNIT 1 3/4 4-19 Amendment No. 36, 117,

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20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.4-1 DOSE EQUlVALENT l 131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity > 0.35 Cl/ gram Dose Equivaient 1131 SEQUOYAH - UNIT 1 3/4 4-22

3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS 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 Systems," May 1973.

3/4.4,6.2 OPERATIONAL LEAKAGE Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 GPM.

This threshold value is sufficiently low to ensure early detection of additional leakage.

The surveillance requirements for RCS Pressure Isolation Valves provide added assurances of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA.

Leakage from the RCS isolation valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.

The 10 GPM IDENTIFIED LEAKAGE limitation provides allowance for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.

The CONTROLLED LEAKAGE limitation restricts operation when the total flow supplied to the reactor coolant pump seals exceeds 40 GPM with the modulating valve in the supply line fully open at a nominal RCS pressure of 2235 psig.

This limitation ensures that in the event of a LOCA, the safety injection flow will not be less than assumed in the accident analyses.

The total steam generator tube leakage limit of 600 gallons per day for all steam generators and 150 gallons per day for any one steam generator will R226 minimize the potential for a significant leakage event during steam line break.

Based on the NDE uncertainties, bobbin coil voltage distribution and crack growth rate from the previous inspection, the expected leak rate following a steam line rupture is limited to below 8.21 gpm at atmospheric conditions and 70*F in the faulted loop, which will limit the calculated offsite doses to within 10 percent of the 10 CFR 100 guidelines.

If the projected and cycle distribution of crack indications results in primary-to-secondary leakage greater than 8.21 gpm in the faulted loop during a postulated steam line break event, additional tubes must be removed from service in order to reduce the postulated primary-to-secondary steam line break leakage to below 8.21 gpm.

The 150-gallons per day limit incorporated into SR 4.4.6 is more restrictive than the standard operating leakage limit and is intended to provide an additional margin to accommodate a crack which might grow at a greater than expected rate or unexpectedly extend outside the thickness of the tube support plate. Hence, the reduced leakage limit, when combined with an effective leak rate monitoring program, provides additional assurance that, should a significant leak be experienced, it will be detected, and the plant shut down in a timely manner.

PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.

Thereforo, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN.

R226 SEQUOYAH - UNIT 1 B 3/4 4-4a Amendment No. 36, 189, 214, 222,

REACTOR COOLANT SYSTEM BfiES The surveillance requirements provide adequate assurance that concentra-tions in excess of the limits will be detected in sufficient time to take corrective action.

3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> doses at the site boundary will not exceed an appro-priately small fraction of Part 100 limits following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM.

The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC of typical site locations. These values are conservative in that specific site parameters of the Sequoyah Nuclear Plant site, such as site boundary location and meteorological conditions, were not considered in this evaluation.

The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity greater than or equal to 0.35 microcuries/ gram DOSE EQUIVALENT I-131, but within the allowable limit I

shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER. Operation with specific activity levels exceeding 0.35 microcuries/ gram DOSE EQUIVALENT I-131 but within the limits shown on Figure 3.4-1 should be limited to no more than 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> per year since the activity levels allowed by Figure 3.4-1 increase the 2-hour thyroid dose at the site boundary by a factor of up to 20 following a R121 postulated steam generator tube rupture.

Reducing T to less than 500 F prevents the release of activity should a steam generator tube rupture since the saturation pressure of the primary coolant is below the lift pressure of the atmospheric steam relief valves.

The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action.

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

SEQUOYAH - UNIT 1 B 3/4 4-5 Amendment No. 117,

EEACTOR COOLANT SYSTEM l

3/4.4.8 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a.

Less than or equal to 0.35 microcurie per gram DOSE EQUIVALENT I-131, l

and b.

Less than or equal to 100/5 microcuries per gram.

l APPLICABILITY: MODES 1, 2,

3, 4 and 5 ACTION:

MODES 1, 2 and 3*:

lR107 a.

With the specific activity of the primary coolant greater than 0.35 microcurie per gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> l

during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with T., less than 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

With the specific activity of the primary coolant greater than 100/5 lR107 microcurie per gram, be in at least HOT STANDBY with T., less than 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

MODES 1, 2,

3, 4 and 5 :

a.

With the specific activity of the primary coolant greater than 0.35 l

microcurie per gram DOSE EQUIVALENT I-131 or greater than 100/E microcuries per gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits.

R107

• With T, greater than or equal to 500*F.

SEQUOYAH - UNIT 2 3/4 4-24 Amendment No. 28, 107, 1

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0 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER I

I 4

I FIGURE 3.4-1 DOSE EQUIVALENT l-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity > 0.35 Cilgram Dose Equivalent 1-131 SEQUOYAH - UNIT 2 3/4 4-27

Tl REACTOR COOLANT SYSTEM

BASES, I

3 /4. 4. 6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are l

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 Systems," May 1973.

3/4.4.6.2 OPERATIONAL LEAKAGE Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 GPM.

This threshold value is sufficiently low to ensure early detection of additional leakage.

The surveillance requirements for RCS Pressure Isolation Valves provide l

added assurances of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA.

Leakage from the RCS. isolation valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.

l l

The 10 GPM IDENTIFIED LEAKAGE limitation provides allowance for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.

l The CONTROLLED LEAKAGE limitation restricts operation when the total flow supplied to the reactor coolant pump seals exceeds 40 GPM with the modulating valve in the supply line fully open at a nominal RCS pressure of 2235 psig.

This limitation ensures that in the event of a LOCA, the safety injection flow will not be less than assumed in the accident analyses.

The total steam generator tube leakage limit of 600 gallons per day for R213 all steam generators and 150 gallons per day for any one steam generator will minimize the potential for a significant leakage event during steam line break.

Based on the NDE uncertainties, bobbin coil voltage distribution and crack growth rate from the previous inspection, the expected leak rate following a steam line rupture is limited to below 8.21 gpm at atmospheric conditions and 70 *F in the faulted loop, which will limit the calculated offsite doses to within 10 percent of the 10 CFR 100 guidelines.

If the projected and cycle l

distribution of crack indications results in primary-to-secondary leakage l

greater than 8.21 gpm in the faulted loop during a postulated steam line break event, additional tubes must be removed from service in order to reduce the l

postulated primary-to-secondary steam line break leakage to below 8.21 gpm.

The 150-gallons per day limit incorporated into SR 4.4.6 is more restrictive than the standard operating leakage limit and is intended to provide an additional margin to accommodate a crack which might grow at a greater than expected rate or unexpectedly extend outside the thickness of the tube support plate. Hence, the reduced leakage limit, when combined with an I

effective leak rate' monitoring program, provides additional assurance that, l

should a significant leak be experienced, it will be detected, and the plant I

shut down in a timely manner, j

PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.

Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN.

lR213 SEQUOYAH - UNIT 2 B 3/4 4-4 Amendment No. 211, 213,

o l

REACTOR COOLANT SYSTEM

BASES, f

3/4.4.7 CHEMISTRY q

i The limitations on Reactor Coolant System chemistry ensure that corrosion i

of the Reactor Coolant System is minimized and reduces the potential for i

Reactor Coolant System leakage or failure due to stress corrosion. Maintaining the chemistry within the Steady State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The associated effects of exceeding the oxygen, j

chloride and fluoride limits are time and temperature dependent.

Corrosion studies show that operation may be continued with contaminant concentration levels in excess of the Steady State. Limits, up to the Transient Limits, for the specified limited time intervals without having a significant effect on the structural integrity of the Reactor Coolant System. The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concen-trations to within the Steady State Limits.

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

3/4.4.8 SPECIFIC ACTIVITY 1

The limitations on the specific activity of the primary coolant ensure l

that the resulting 2-hour doses at the site boundary will not exceed an appropriately small fraction of Part 100 limits following a steam generator 1

tube rupture accident in conjunction with an assumed steady state primary-to-I secondary steam generator leakage rate of 1.0 GPM.

The values for the limits on specific activity represent limits based upon a parametric evaluation by the NRC of typical site locations.

These values are conservative in that specific site parameters of the Sequoyah site, such as site boundary location and meteorological conditions, were not considered in this evaluation.

The ACTION statement permitting POWER OPERATION to continue for limited 4

time periods with the primary coolant's specific activity greater than 0.35 l

microcuries/ gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER. Operation with specific activity levels exceeding 0.35 microcuries/ gram DOSE EQUIVALENT I-131 but within the limits l

shown on Figure 3.4-1 should be limited to no more than 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> per year since the activity levels allowed by Figure 3.4-1 increase the 2-hour thyroid R107 dose at the site boundary by a factor of up to 20 following a postulated steam generator tube rupture.

SEQUOYAH - UNIT 2 B 3/4 4-5 Amendment No. 107 e__-___--______