ML19317G548

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Proposed Text for Tech Specs Re Calculated Activity Limits on Primary & Secondary Coolant for Facility
ML19317G548
Person / Time
Site: Crystal River 
Issue date: 01/29/1972
From: Fontecilla H
US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML19317G547 List:
References
NUDOCS 8003180855
Download: ML19317G548 (5)


Text

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.,a CRYSTAL RIVER NUCLEAR GENERATING PLA';T UNIT 3

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' TECICTICAL SPECIFICATIONS

- The Technical 1 Specification. activity limits on the primary'and secondary coolantifor the Crystal River Nuclear Generating Plant Unit 3-have.been

. calculated _by the Accident Analysis Branch. The primary coolant noble gas and: iodine' activities'are set by n' postulated tube rupture accident.

andethe' secondary iodine activity by a steam'line break accident. A loss of offsite : power is ' assumed to occur a*: th'e same time.

The Technical Specifications should read as follows:

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Maximum Reactor Coolant Activity Specification The s ecific activity of the reactor coolant due to dose equivalent

- I-131_/ shall not exceed 2.0 uCi/ gram during equilibrium conditions or-prior to'startup.. The iodine activity will be allowed to exceed the equilibrium limit but shall not exceed the maximum values in-dicated 'in Figure 1 during 48-hour periods during icdine transients.

Operation with a. primary coolant activity higher than the equilibrium value, however, shall not exceed 5% of the plant total yearly

. operating time. The total specific activity of the reector coolant

~.due to all nuclides, excluding tritium, with half-lives of = ore than 20 minutes:shall not exceed 225/E uCi/ gram.

If:the limits specified above are not satisfied, shutdown procedures

- shall be initiated immediately and the reactor shall be cooled to

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500*F or less.within eight hours af ter detection.

If the iodine

- activity exceeds the indicated maximum value the equilibrius' iodine

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activity limit trust be lowered by an amounc proportionate to the

- amount.by which the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limit was exceeded.

Sampling Frequency Whenever the reactor is critical, the sampling frequencies given in

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Table 4.2.1'.shall be :used to-determine primary and secondary coolant 4

~1/ Dos'e LequivalentI-131 concentration is defined as that concentration -

~of I-131' which alone would produce the same dose as the quantity and isotopic mixture actually present.

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'". activity levels, jIn addition,' the sampling program described in Table 4.2.2-shall be. initiated,z.

(a)

' following a change in power exceeding 15 percent of rated power which occurs within ene hour period;-

(b) during the first 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> following-a partial or complete depressurization of the reactor coolant system; and

(c).

whenever the primary or secondary coolant activity exceeds the equilibrium limits specified above.

These bests shall be recorded together with the following information:

(a)-

~ reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prier to the first. sample, (b) fuel burnup.by core region,

- (c) clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the-first sample, and (d).

history of. de-gassing operatiens if any.

Reporting Recuirenents -

--The above 'information shall be included in the semi-annual operating

-report.. If the limits' of the specification'are exceeded, a report

. shall be made to the Directorate of Licensing within 30 days.

TABLE 4.2.2 Sample' Measurements

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. Iodine activity,. isotopic analysis Every 4Lhours*~

. liquid sample including at least I-131, I-133,

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The basis' for the primaryLecolant iodine' activity limit is a computed dose

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- to'the. thyroid at the site boundary of 1.5' rem during the-2-hour period-following.a steam generator tube' rupture accident and a primary to secondary

. steam: generator: leakage-of 1.0 spm.

  • In-.all cases, the : minimum _ number of samples shall not be less -than-three for'each' transient.

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FRACTION (F) 0F DOSE' EQUIVALENT I-131

. PRIMARY C00LMT SPECIFIC - ACTIVITY EQUILIBRIUM LIMITS FOLLOilI:iG POWER TRMSIENTS FOR THE CRYSTAL RIVER NUCLEAR GENERATING PLA' T UNIT 3

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The. Nsis ifor'. the totaA activity limit is a. computed whole body dose at Lthe L site boundary of 0.5 rem during the-2-hour period following a steam -

generator: tube. rupture accident.. Twenty minutes is the average time it

takes the released eases.co're'ach'the site boundary under. adverse meteorological conditions and E is the average energy of betas and ga= mas

- per'~ disintegration.

The~ allowance to exceed. iodine equilibrium activity limits during the

specified 48-hour. periods ' following initiation of shutdown or a power transient.is made in' order to account,for,possible iodine spiking

. phenomenai= The basis for the allowable maximum values.is a resulting dose to'the thyroidfat theLsite' boundary of 30 rem during the 2-hour p'eriod following 2.' steam generator' tube frupturs accident.

In calculatiing the limits-specified above a X/0 value of 2.0 x 104 sec/m -

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'andian' iodine decontamination factor of 10 between the' steam and water

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2. [Secondarv System Activity Specifications The ' specific activity.of-the secondary coolant due to dose equiva-

-lent I-131 ~shall not exceed 0.05 uCi/ gram.

If the linits specified above'are not satisfied. shutdown procedures shall be initiated

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within;four' hours and' the reactor shall be cooled to 500*F or less within'eight hours after detection.

Basis The basis for.this specified' limit'is a computed dose to'the thyroid ct the site boundary of 1.5 rem'during the 2-hour' period

,following a main. steam line break accident.. This is also based on 'a primary to secondary steam generator leakage of 1.0 gpm.

Noispecifications' are made in regard to; noble gas activity

. because: these gasesL are a' aumid' to be continuously re=oved through;the condenser.

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)In' calculating the limits.specified.above a X/Q.value-of 2.0 x~-'10 %-sec/m3 and an--iodine' decontamination 1 factor of'10

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between the steam and. water phases in the unaffected steam

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- ITEM 1 of TABLE 4.2-1~

. FREQUENCIES FOR SAMPLING-TESTS Maximum Time

.Between Check Frequency Tests

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'Re' actor Coolant

-Gross Activity-3 Times / Week ( )

4 Days Liquid Samples i

Isotopic-analysis to determine-equivalent I-131 concentration Bi-weekly.

15. Days

@ diochemical for E Deternination Semi-annual (2) 7 Months Tritium Activity Weekly 10 Days 2

(1)When radioactivity level exceeds-25 percent of limits.in specificatiens

3.1.D, the sampling frequency shall.be increased to.a minimum of~once each day.

(2) Redetermined if: the primary ' coolant radioactivity changes by more than 10 pci/cc 'in accordance with specification 3.1.D.

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