Text

STS for C-E Reactors,Rcs,Including Provisions for Iodine Spiking & Limits & Sampling Requirements for Primary & Secondary Coolants
	ML19327A388
Person / Time
Site:	Fort Calhoun
Issue date:	07/02/1980
From:	; ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	;
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ML19327A387	List: ML19327A386; ML19327A388;
References
	NUDOCS 8008060130
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REACTOR COOLANT SYSTEM 3/4.4.9 SPECIFIC ACTIVITY l

LIMITING CONDITION FOR OPERATION 3.4.9 The specific activity of the primary coolant shall be limited to:

a.

Less than oc equal to 1.0 microcurie / gram DOSE EQUIVALENT I-131, and b.

Less than or equal to 1004 microcuries/ gram.

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

ACTION:

MODES 1, 2 and 3*:

a.

'With the specific activity of the primary coolant greater than 1.0 microcurie / gram DOSE EQUIVALENT I-131 but within the allowable limit 4

(below and to the left of the line) shown on Figure 3.4-1, operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months provided that the cumulative operat-ing time under these circumstances does not exceed 800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months in any consecutive 12 month period. With the total cumulative operating time at a primary coolant specific activity greater than 1.0 micro-curie / gram DOSE EQUIVALENT I-131 exceeding 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months in any consecutive 6 month period, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days indi-cating the number of hours above this limit.

The provisions of Specification 3.0.4 are not applicable.

b.

With the specific activity of the primary coolant greater than 1.0 microcurie / 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 .

avg c.

With the specific activity of the primary coolant greater than 100 4 microcuries/ 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 .

avg A

Witt T,yg greater than or equal to 500*F.

CE-STS 3/4 4-22 JUL 0 2_1980 l

REACTOR COOLANT SYSTEM ACTION:

(Continued)

MODES 1, 2, 3, 4 and 5:

d.

With the specific activity of the primary coolant greater than 1.0 microcurie / gram DOSE EQUIVALENT I-131 or greater than 100/E micro-curies / gram, perform the sampling and analysis requirements of item 4 a) of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits. A REPORTABLE OCCURRENCE shall be prepared and submitted to the Commission pursuant to Specification 6.9.1.

This report shall contain tha results of the specific activity analyses together with the following information:

1.

Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, 2.

Fuel burnup by core region, 3.

Clean-up flow history starting 48 nours prior to the first sample in which the limit was exceeded, 4.

History of de gassing operation, if any, sta: ting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, and 5.

The time duration when the specific activity of the primary coolant exceeded 1.0 microcurie / gram DOSE EQUIVALENT I-131.

SURVEILLANCE REQUIREMENTS 4.4.9 The specific activity of the primary coolant shall be determined to be I

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

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CE-STS 3/4 4-23 Ji1L 0 21980 l

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TABLE 4.4 n b[

PRIMARY COOLANT SPECIFIC ACTIVITY' SAMPLE u

AND ANALYSIS PROGRAM TYPE OF MEASUREMENT SAMPLE AND ANALYSIS MODES IN WHICH SAMPLE AND ANALYSIS FREQUENCY AND ANALYSIS REQUIRED 1.

Gross Activity Determination At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 1, 2, 3, 4 2.

Isotopic Analysis for DOSE 1 per 14 days 1

EQUIVALENT I-131 Concentration 3.

Radiochemical for E Determination 1 per 6 months

1 4.

Isotopic Analysis for Iodine a)

Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , l#, 2#, 3#, 4#, 5#

Including I-131, I-133, and I-135 whenever the specific activity exceeds 1.0 mci / gram, DOSE EQUIVALENT I-131 u,);

or 100/E mci / gram, and I'

b)

One sample between 1, 2, 3 23 2 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 of the RATED THERMAL POWER within a one hour period.

Until the specific activity of the primary coolant system is restored within its limits.

Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor

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was last subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or longer, r-o 54 O

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20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER 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 >1.0gCi/ gram Dose Equivalent 1-131 l

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CE-STS 3/4 4-25 JUI. 0 21980 I

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e PLANT SYSTEMS ACTIVITY LIMITING CONDITION FOR OPERATION

3. 7. '1. 4 The specific activity of the secondary coolant system shall be less than or equal to 0.10 microcuries/ gram DOSE EQUIVALENT I-131.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the specific activity of the secondary coolant system greater than 0.10 microcuries/ gram DOSE EQUIVALENT I-131, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.1.4 The specific activity of the secondary coolant system shall be determined to be within the limit by performance of the sampling and analysis program of Table 4.7-1.

CE-STS 3/4 7-8 AUG 15 1979 l

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o TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM TYPE OF MEASUREMENT SAMPLE AND ANALYSIS AND ANALYSIS FREQUENCY 1.

Gross Activity Determination At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 2.

Isotopic Analysis for DOSE a) 1 per 31 days, whenever EQUIVALENT I-131 Concentration the gross activity determina-tion indicates iodine con-centrations greater than 10%

of the allowable limit.

l b) 1 per 6 months, whenever the j

gross activity determination indicates iodine concentra-tions below 10% of the allowable limit.

J CE-STS 3/4 7-9 AUG 15 1979

REACTOR COOLANT SYSTEM BASES CHEMISTRY (Continued) 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 fluoridh 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.

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

3/4.4.9 SPECIFIC ACTIVITY

{

The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 and a concurrent loss of offsite electrical power.

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 (

) 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 1.0 microcurie / gram DOSE EQUIVALENT I-131, t,ut 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 1.0 microcurie / gram DOSE EQUIVALENT I-131 but within the limits shown on Figure 3.4-1 must be restricted to no more than 800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months per year (approximately 10 percent of the unit's yearly operating time) since the activity levels allowed by Figure 3.4-1 increase the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thyroid dose at the site boundary by a factor of up to 20 following a postulated steam generator tube rupture.

The reporting of cumulative opera: bg U me over 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months in any 6 month consecutive period with greater than 1.0 microcurie / gram DOSE EQUIVALENT I-131 will allow sufficient time for Commission evaluation of the circumstances prior to reaching the 800 hour0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months limit.

CE-STS B 3/4 4-5 JUL 0 21980

REACTOR COOLANT SYSTEM BASES SPECIFIC ACTIVITY (Continued)

Reducing T to less than 500*F prevents the release of activity should asteamgenerat@9 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.

3/4.4.10 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 startup and shutdown operations.

The various categories of load cycles used for design purposes are provided in Section (

) of the FSAR.

During startup 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.

These thermal induced compressive stresses tend to alleviate the tensile stresses induced by the internal pressure.

Therefore, a pressure-temperature curve based on steady state conditions (i.e., no thermal stresses) represents a lower bound of all similar curves for finite heatup rates when the inner nll of the vessel is treated as the governing location.

The heatup analysis also covers the determination of pressure-temperature limitations for the case in which the outer wall of tne vessel becomes the controlling location.

The thermal gradients established during heatup produce tensile stresses at the outer wall of the vessel.

These stresses are additive to the pressure induced tensile stresses which are already present.

The thermal induced stresses at the outer wall of the vessel are tensile and are l

dependent on both the rate of heatup and the time along the heatup ramp; l

therefore, a lower bound curve similar to that described for the heatup of the inner wall cannot be defined.

Consequently, for the cases in which the outer 1

wall of the vessel becomes the stress controlling location, e.;.ch heatup rate of interest must be analyzed on an individual basis.

CE-STS B 3/4 4-6 JUL 0 21980 L

PLANT SYSTEMS BASES 3/4.7.1.4 ACTIVITY

.The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture.

This dose also includes the effects of a coincident 1.0 GPM primary to secondary tube leak in the steam generator of the affected steam line and a concurrent loss of offsite electrical power. These values are consistent with the assumptions used in the accident analyses.

3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVE The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture. This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, i

and 2) limit the pressure rise within containment in the event the steam line l

rupture occurs within containment. The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses.

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations to (90)*F and f (30)*F and are sufficient (275) psig are based on a steam generator RTNDT to prevent brittle fracture.

3/4,7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions.

The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.

3/4.7.4 SERVICE WATER SYSTEM The OPERABILITY of the service water system ensures that sufficient cooling capacity is available for continued operation of equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.

CE-STS B 3/4 7-3 AUG 151979

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ML19327A388

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