Text

Proposed Tech Specs,Reducing Allowable Unit 1 RCS Dose Equivalent I-131 from 0.35 Uci/Gram to 0.20 Uci/Gram for Remainder of Cycle 8
	ML20137C638
Person / Time
Site:	Byron
Issue date:	03/14/1997
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20137C602	List: ML20137C599; ML20137C638;
References
	NUDOCS 9703250067
	Download: ML20137C638 (8)
	v • d • e

- - - - . _ .

, REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the reactor coolant shall be limited to:

a. Less than or equal to 1 miECurie per gram DOSE EQUIVALENT I-131**,

and

b. Less than or equal to 100/l microcur~ies per gram of gross radioactivity.

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

ACTION:

MODES 1, 2 and 3*:

a. With the specific activity of the reactor coolant greater than 1 microcurie per gram DOSE EQUIVALENT I-131** for more than 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 3.4-1, 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 ; and

b. With the specific activity of the reactor coolant greater than 100/E microcuries 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 .

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With T , greater than_ot_ equal _to 500*F.

- For Unit I cr col SE EQUIVALENT I-131 will be linited to M microCuries per gram.

Sip BYRON - UN'ITS 1 & 2 3/4 4-27 AMENDMENT NO. 77 9703250067 970314' PDR ADOCK 05000454 ,

P PDR -

, REACTOR COOLANT SYSTEM JIMITING CONDITION FOR OPERATION ACTION (Continued)

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

With the specific activity of the reactor coolant greater than _,

I microcurie per gram DOSE EQUIVALENT I-131* or greater than 100/E l microcuries per gram, perform the sampling and analysis requirements of Item 4.a) of Table 4.4-4 until the specific activ'ity of the reactor !

coolant is restored to within its limits. l l

l SURVEILLANCE RE0VIREMENTS )

1 4.4.8 The specific activity of'the reactor coolant shall be determined to be '

within the limits by performance of the sampling and analysis program of Table 4.4-4.

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For Unit I? reactor coolant DOSE EQUIVALENT I-131 will be limited to microcuries per gram.

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BYRON - URITS -l & 2 3/4 4-28 AMENDMENT NO. 77 M =* e -

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DOSE EQUIVALENT I-131 REACTOR COOLANT SPECIFIC ACTIVITY !

LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE REACTOR COOLANT SPECIFIC ACTIVITY >lpCI/GRAN DOSE EQUIVALENT I-131*

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' *For Unit 1* ReactsFToolant Specific Activity >0M pCi/ Gram DOSE EQUIVALENT I-131 4

BYRON - UNITS 1 & 2, 3/4 4-29 b)

69. AMENDMENT NO. 77

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OPERATION 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.4-1 '

DOSE EQUlVALENT l-131 REACTOR COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE REACTOR COOLANT SPECIFIC ACTIVITY > 1pCl/ GRAM DOSE EQUfVALENT l-131*

For Unit 1 through Cycle 8 Reactor Coolant Specific Activity > 0.2 Cl/ Gram DOSE EQUIVALENT l-131.

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TABLE 4.4-4 i 4

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REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE i AND ANALYSIS PROGRAM [

i l' TYPE OF MEASUREMENT SAMPLE AND ANALYSIS MODES IN WHICH SAMPLE .

AND ANALYSIS FREQUENCY AND ANALYSIS REQUIRED 1 1. Gross Radioactivity At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 1, 2, 3, 4 ,

, Determination ** i i

! 2. Isotopic Analysis for DOSE EQUIVA- Once per 14 days ~

1 I

LENT I-131 Concentration

3. Radiochemical for i Determination *** Once per 6 months

1 i 4. Isotopic Analysis for Iodine a) Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , If,2#,3#,4#,5#

. Including I-131, I-133, and I-135 whenever the specific '

! activity exceeds 1

- pC1/ gram DOSE l EQUIVALENT I-131**** I .

or 100/E pCi/ gram of gross radioactivity, and I l

. b) One sample between 2 1,2,3 ,

and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following a THERMAL POWER change exceeding 15 percent

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POWER within a 1-hour 2 period. ,

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TABLE 4.4-4 (Continued)

TABLE NOTATIONS

Until the specific activity of the Reactor Coolant System is restored )

within its limits. q l

Sample to be taken after a minimum of 2 EFPD and 20 days of POWER j OPERATION have elapsed since reactor was last subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or longer.

- A gross radioactivity analysis shall consist of the quantitative measurement of the total specific activity of the reactor coolant except for radionuclides with half-lives less than 10 minutes and all radioiodines. The total specific activity shall be the sum of the !

degassed beta-gamma activity and the total of all identified gaseous .

activities in the sample within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after the sample is taken and i extrapolated back to when the sample was taken. Determination of the contributors to the gross specific activity shall be based upon those energy peaks identifiable with a 95 percent confidence level. The latest '

available data may be used for pure beta-emitting radionuclides.

- - A radiochemical analysis for E shall consist of the quantitative measurement of the specific activity for each radionuclide, except for radionuclides with half-lives less than 10 minutes and all radiciodines, ,

l which is identified in the reactor coolant. The specific activities for 4 these individual radionuclides shall be used in the determination of E for the reactor coolant sample. Determination of the contributors to E shall be based upon these energy peaks identifiable with a 95 percent confidence level. - i

- - - For Unit I co n D E EQUIVALENT I-131 will be limited to-445-microcuries per gram.

O. M e

3/4 4-31 AMENDMENT NO. 77 BYRON-UEITS1&2

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REACTOR COOLANT SYSTEM 4

BASES OPERATIONAL LEAKAGE (Continued)

. The Surveillance Requirements for RCS pressure isolation valves provide j added assurance of valve integrity thereby reducing the probability of gross 1 valve failure and consequent intersystem LOCA. Leakage from the RCS pressure i isolation valves is IDENTIFIED LEAKAGE and will be considered as a portion of (

the allowed limit. ;

1 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 l

! 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 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 I 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.

3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the reactor coolant ensure that the resulting 2-hour doses at the SITE BOUNDARY will not exceed an l appropriately small fraction of 10 CFR Part 100 dose guideline values following a steam generator tube rupture accident in conjunction with an assumed steady-

. state reactor-to-secondaar steam generator leakage rate of 1 gpm.9 The values for the limits on specific activity represent limits based upon a parametric evaluation by the NRC of typical site locations. These values a e conservative '

in that specific site parameters of the Byron Station, such as S E BOUNDARY location and meteorological conditions, were not considered in ti is evaluation.

i BYRON - UNIT,5 1,& 2 B 3/4 4-5 AMENDMENT NO. 21 ;

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For Unit 1 through Cycle 8, the limitations on the specific activity of the reactor coolant

' ensure that the resulting 2-hour off-site doses will not exceed an appropriately small fraction of the 10 CFR Part 100 dose guideline values following a Main Steam Line Break i

accident in conjunction with an assumed steady-state primary-to-secondary steam l

generator leakage rate of 150 gpd from each unfaulted steam generator and maximum site I

} allowable primary-to-secondary leakage from the faulted steam generator.

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ML20137C638

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