Text

Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core
	ML20195E984
Person / Time
Site:	Sequoyah
Issue date:	06/07/1999
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
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ML20195E969	List: ML20195E966; ML20195E984;
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ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY SEQUOYAH PLANT (SQN)

UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE MARKED PAGES I. AFFECTED PAGE LIST Unit 2 3/4 4-24 3/4 4-26 3/4 4-27a (new page)

B 3/4 4-4 B 3/4 4-5 II. MARKED PAGES See attached.

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t REACTOR COOLANT SYSTEM 3/4.4.0 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 0.3! microcurie per gram DOSE EQUIVALENT lR227 I-131, and

b. Less than or equal to 100/E microcuries pe _ *am.

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

MODES 1, 2 and 3*:

a. Wi '

r e ecific activity of the rimary coolant greater than 07 0, i+

microcurie per gram DOS QUIVALENT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one cont. s time interval or exceeding the 1 mit lR227 line shown on Figure 3.4 ' be in at least HOT STANDBY with T,,, ess than 5000F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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

MODES 1, 2, 3, 4 and 5:

a. With the specific activity of the primary coolant greater than .3 i**

microcurie per gram DOSE EQUIVALENT I-131 or greater than """

lR227 100/E microcuries per gram, perform the sampling and analysis requirements of item da of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits.

R107 INSERT i

With T., greater than or equal to 5000F, l 1

- For Unit 2 Cycle 10 operation, a DOSE EQUIVALENT I-131 less than or equal to 1.0 microcurie per gram shall be maintained.

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' For Unit 2 Cycle 10 operation, refer to Figure 3.4-la, j I

SEQUOYAH - UNIT 2 3/4 4-24 Amendment No. 28,107,227, I

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SEQUOYAH - UNIT 2 3/4 4-27a

REACTOR COOLANT SYSTEM BASES 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 laakage.

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 tot-flow supplied to the reactor coolant pump seals exceeds 40 GPM with t FP4SIIIt1' modulating valve in the supply line fully open at a nominal RCS prer oure f 2235 psig. This limitation ensures that in the event of a LOCA, ee et injection flow will not be less than assumed in the accident lye . .

The total steam generator tube leakage limit of 600 al ns p day for R213 all steam generators and 150 gallons per day for any o s 2un g rator wil minimize the potential for a significant leakage eve ing e eam line break. Based on the NDE uncertainties, bobbin co v tage stribution an crack growth rate from the previous inspection, n e> pec -

leak rate following a steam line rupture is limited to e 8.; 1** gpm at atmospher'c conditions and 70 oF in the faulted loop, i will ltmt; the calculated offsite doses to within 10 percent of tl CFR 100 guidelines. If the R227 projected and cycle distribution on-e indications results in primary to-secondary leakage greater than 8.2:/d m in the faulted loop during a postulated steam line break even , additional tubes must be removed fro service in order to reduce ostulated primary-to-secondary steam 1 ie break leakage to below 8.2 ** gpm.

The 150-gallons per day limit incorporated into SR 4.4.6 is mor restrictive than the standard operating leakage limit and is intende to provide an additional margin to accommodate a crack which might gro at a greater than expected rate or unexpectedly extend outside the thick ess of the R227 tube support plate. Hence, the reduced leakage limit, when combin d with an effective leak rate monitoring program, provides additional assur rce that, should a significant leak be experienced, it will be detected, an the plant shut down in a timely manner.

PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptabl since it may be indicative of an irapending gross failure of the pressure bo rdary.

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

lR213

" For Unit 2 Cycle 10 operation, the limiting leakage in the faulted loop following a main steam line break is 2.7 gpm.

November l7.1998 SEQUOYAH UNIT 2 B 3/4 4-4 Amendment No. 211,213,227

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EEACTOR COOLANT SYSTEM l

1 BASES l 3/4,4.7 CHEMISTRY The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduces the potential for Reactor Coolant System leakage or failur e 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 j oxygen, chloride and fluoride limits are time and temperature dependent. 1 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 2cestrictions of the Transient Limits provides time for taking correctiv" a;tions to restore the contaminant concentrations 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.

INSERT l

3/4.4.8 SPECIFIC ACTIVITY {

The limitations on the specific activity of ep ma co la t ens, re that the resulting 2-hour doses at the site bo ary' 11 tot e cet an i appropriately small fraction of Part 100 li s to owi ; a st am eneratc r j tube rupture accident in conjunction wit eady at te rimary- :o-n ass' sed secondary steam generator leakage rate f 1.0 M. ihe value fo the lim _ts j on specific activity represent lim , based on parametri eva uation b:

the NRC of typical site locatio . These alue are conservstive in that i specific site parameters of t . Sequoya site such as site boun'ary locat' n j and meteorological conditi s, were con dered in this valu tion.

l The ACTION sta ment permi ing P ER OPERATION to ontin e for limi ;eo I time periods w(37 e primary olant' - specific activit great r than 0.31**. lR227 microcuries/gr tm DOSE EQUIV ENT I ' 1, but within the aulowabl limit shown on Figure 3.4- C. accommo es pos 1ble iodine spiking enomen n which may occur following char._ n THERF POWER. Operation w' h spec fic activity levels exceeding ~0.3 ** mic'ms ries / gram DOSE EQUIVALE JT I-131 but within the

' lR227 limits shown on Figure 3.4- should be limited to n re tha 900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months per year since the activity lev nm allowed by Figure 3.4 incre su .he 2-hour

R107 thyroid dose at the site boundary by a factor of up to 0 foi owing a postttiated steam generator tube rupture.

l ** For Unit 2 Cycle 10 operation, a DOSE EQUIVALENT I-131 less than or equal

! to 1.0 microcurie per gram shall be maintained.

For Unit 2 Cycle 10 operation, refer to Figure 3.4-la.

November l7,1998 SEQUOYAH - UNIT 2 B 3/4 4-5 Amendment No. 107,227

ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (SQN)

UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE REVISED PAGES I. AFFECTED PAGE LIST Unit 2 3/4 4-24 )

3/4 4-26 3/4 4-27a 3 B 3/4 4-4 i B 3/4 4-5 II. REVISED PAGES See attached.

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. i REACTOR COOLAfrP SYSTEM '

I: '3/4.4.8 SPECIFIC ACTIVITY l

. 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, and l

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

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

MODES 1, 2 and 3* j lR107 !

a. With the specific activity of the primary coolant greater than 0.35** microcurie per gram DOSE EQUIVALENT I-131 for more-than l 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval'or exceeding the limit line shown on Figure 3.4-l', be in at least HOT STANDBY with T., less j

than'5000F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With the specific. activity;of the primary coolant greater than 100/E lR107 microcurie per gram, be in at least HOT STANDBY with T , less than

.500 F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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

a. With the specific activity of the primary coolant greater than ,35**

l l microcurie per gram DOSE EQUIVALENT I-131 or greater than

~100/E microcuries per gram, perform the sampling and analysis requirements of item da 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.

- For Unit.2 Cycle 10 operation, a DOSE EQUIVALENT I-131 less than or equal to 1.0 microcurie per gram shall be maintained.

For Unit'2 Cycle 10 operation, refer to Figure 3,4-la.

SEQUOYAll- UNIT 2 3/4 4-24 Amendment No. 28,107,227, i

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FIGURE 3.4-1 a DOSE EQUIVALENT l-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific l Activity > 1.0 pCilgram Dose Equivalent 1-131 for Cycle 10 Operation SEQUOYAH - UNIT 2 3/4 4 27a

REACTOR COOLANT SYSTEM BASES 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE l

3/4.4.6.1 LEAKAGE DETECTION SYSTEMS l

Thb RCS leakage detection systems required by this specification are I

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 Prersure Boundary Leakage Detection Systems," May 1973.

1/_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 wnose 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 R213 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 l conditions and 70 oF 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- R227 secondary leakage greater than 8.21** gpm in the faulted loop during a !

postulated steLm line break event, additional tubes must be removed from R227 service in order to reduce the postulated primary-to-secondary steam line break leakage to below 8.21** gpm.

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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 i provide an additional margin to accommodate a crack which might grow at a I greater than expected rate or unexpectedly extend outside the thickness of the '

tube support plate. Hence, the reduced leakage limit, when combined with an R227 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.

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

R213

" For Unit 2 Cycle 10 operation, the limiting leakage in the faulted loop following a main steam line break is 2.7 gpm..

SEQUOYAll - UNIT 2 83/44-4 Amendment No. 211,213,227

o REACTOR COOLANT SYSTEM BASES

- 3/4.4.7 CHEMISTRY The limitations on Reactor Coolant System chemistry ensure that s corrosion of the' Reactor Coolant System is minimized and reduces the potential

!for Reactor Coolant System leakage or failur e 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,. 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 i 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 concentrations 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.

3/4.4.8 SPECIFIC ACTIVITY The limitations 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 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 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 lR227 on Figure 3. 4-l', accommodates possible iodine spiking phenomenon which may l

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

- For Unit 2 Cycle 10 operation, a DOSE EQUIVALENT I-131 less than or equal to 1.0 microcurie per gram shall be maintained.

',For Unit _2 Cycle 10 operation, refer to Figure 3.4-la.

SEQUOYAH - UNIT 2 ' B 3/4 4-5 Amendment No. 107,227-

ML20195E984

Text

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