ML20210A099

Proposed Tech Spec Pages 4-106,4-107 & 4-109 Re Radioactive Gaseous Waste Sampling & Analysis Program

ML20210A099
Person / Time
Site:	Crane
Issue date:	02/03/1987
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20209J549	List: ML20209J541 ML20210A068 ML20210A099
References
NUDOCS 8702060408
Download: ML20210A099 (3)

Text

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TABLE 4.22-2 m

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM E

E I

I I

l l

Sampling l

Minimum l

l Lower Limit y

Gaseous Release Type i

Frequency I

Analysis Type of Activity I

of Detection l

l Frequency i

Analysis I

(LLD) l I

l l

(uCi/mila I

I I

i l

i I

I I

P I

P I

l A.

Waste Gas l

Each Tank l

Each Tank l Principal Gamma i 1 x 10-4 Storage Tank l

Grab l

l Emitters 9 I

I Sample i

i i

l I

I i

l I

I i

B.

Containment l

P i

P l H-3 1 1 x 10-6 Purge i

Each Purge b i

Each Purge b l Principal Gamma l 1 x 10-4 i

Grab I

I Emitters 9 I

I Sample l

l l

I I

I I

2.

I I

I I

g C.

Auxiliary and l

l l H-3 l 1 x 10-6 Fuel Handling l

Mc e i

M l Principal Gaeuna i 1 x 10-4 Building Air l

Grib l

Emitters 9 i

Treatment System l

Sample I

I I

I I

I I

I I

I D.

Fuel Handling Building i

M (during i

i H-3 1 1 x 10-6 ESF Air Treatment Systes I system opera-l M (during i Principal Gamma l 1 x 10-4 I

tion)

I system I Emitters 9 l

1 Grab Sample I

operation) l l

l 1

I I

I I

I I

E.

Condenser Vacuum l

Mh l

I H-3 l 1 x 10-6 y

h l

Grab Sample l

Mh i Principal Gamma l 1 x 10-4 Pumps Exhaust l

l l Emitters 9 l

1 I

I I

G702060408 8702O3 PDR ADOCK 05000289 P

PDR

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E.

TABLE 4.22-2 (Continued)

R A

RADICACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGPR4 5

'a l

I I

I l

Sampling i

Minimum l

l Lower Limit g

Gaseous Release Type l

Frequency i

Analysis l

Type of Activity I

of Detection l

l Frequency I

Analysis I

(LLD) m l

l l

l (uCi/mila l

I I

I I

I I

I F.

All Release Types as l

l Wd l

I-1 31 1 1 x 10-12 Listed Above in A, B, C l

Continuous f -

l Charcoal i

I-133 1 1 x 10-10 and D (during System l

l Sample i

1 Operation)

I i

l l

1 1

I I

I I

I I

I Continuous f I

Wd i Principle Gacma l 1 x 10-11 l

l Particulate l Emitters 9 I

l l

l (I-131, Others) l I

I I

i 1

I I

I 1

I l

l O

l Continuous f.i l

Q l

Gross Alpha i 1 x 10-11 l

l Composite l

l l

l Particulate i

l l

i Sample I

l l

l i

I I

I I

I l

Continuous f i l

Q l

Sr-89, Sr-90 l 1 x 10-11 l

l Composite l

l l

l Particulate i

I l

l Sample i

I I

I I

I I

I I

I G.

Condenser Vent Stack i

Continuous k l

yd l

I-131 1 1 x 10-12 Continuous Iodine l

I Charcoal l

l SamplerJ l

l Sample l

l l

l 1

1 1

I I

I t

r TABLE 4.22-2 (Continued) d.

Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter changing (or af ter removal from sampler).

e.

Tritium grab samples shall be taken weekly from the ventilation exhaust from the spent fuel pool area whenever spent fuel is in the spent fuel pool.

f.

The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.22.2.1, 3.22.2.2, and 3.22.2.3.

g.

The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87. Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emmissions and Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported.

Other peaks which are measureable and identifiable, together with the above nuclides, shall also be identified and reported.

Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD, and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations, h.

Applicable only when condenser vacuum is established.

Sampling and analyses shall be performed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following each shutdown, startup or thermal power level change exceeding 15% of Rated Thermal Power in one hour.

i.

Gross Alpha, Sr-89, and Sr-90 analyses do not apply to the Fuel Handling Building ESF Air Treatment System.

j.

If the Condenser Vent Stack Continuous Iodine Sampler is unavailable, then alternate sampling equipment will be placed in service within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

k.

Applicable only when condenser vacuum is established.

4-109 AmendmentNo.//,122