Text

Revised Pages to Proposed Radiological Effluent Tech Specs, Per 841002 Application for Amends to Licenses DPR-77 & DPR-79
	ML20140H223
Person / Time
Site:	Sequoyah
Issue date:	09/27/1985
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20140H220	List: ML20140H215; ML20140H223;
References
	NUDOCS 8510090134
	Download: ML20140H223 (39)
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INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION e

3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels sbown in table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm /

trip setpoints of these channels shall be determined in accordance with the methodology and the parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: During releases via these pathways.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, without delay, suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE take the ACTION shown in table 3.3-12. Exert best effort to return the instruments to Sem,i -

OPERABLE status within 30 days and, if unsuccessful, explain in tne next9 Annual Radioactive Effluent Release Report why the inoper- N ability could not be corrected within 30 days.

c. The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13.b are not applicable.

SURVEILLANCE REQUIREMENTS - 4.3.3.9 Each radioactive liquid effluent monitoring instru=entation channel shall be demonstrated OPERABLE by perfor=ance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in table 4.3-8.

8510090134 850927 PDR ADOCK 05000327 P PDR

SEQUOYAH - UNIT 1 3/4 3-69

e TABLE 3.3-12 (Continued)

TABLE NOTATION ACTION 30 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:

a.

At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and

b. At least two technically qualified members of the Facility Staff independently verify the release rate

. calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 31 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are ana-lyzed for gross radioactivity gamma at a limit of detection of at least 10 7 microcuries/ gram:

a.

ytdtf At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is -&eee than or equal to 0.01 g microcuries/ gram DOSE EQUIVALENT I-131.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/ gram DOSE EQUIVALENT I-131.

ACTION 32 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases vi_ this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for gro9s 10 radioactivity gamma at a limit of detection of at least microcuries'/ml.

ACTION 33 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is esti-mated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump curves may be used to estimate flow.

ACTION 34 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue provided the tank liquid level is estimated during all liquid additions to the tank.

SEQUOYAH - UNIT 1 3/4 3-71

O a '

INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRU?ENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 3.3-13 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservativ'e than required by the above Specification, without delay suspend the release of radio-active gaseous effluents monitored by the affected channel, declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Exert best efforts to return the dem,: instrument to OPERABLE status with 30 days and, if unsuccessful, explain in the next' Annual Radioactive Effluent Release Report ll why the operability could not be corrected within 30 days.

c. The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13.b are not applicable.

SUPNEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-9. ,

i 4

i t

SEQUOYAH - UNIT 1 3/4 3-74 o

l l

l 1

5 TABLE 3.3-13 (Continued)

TABLE NOTATION At all times.

During waste gas disposal system operation.

- - During shield building exhaust system operation.

ACTION 40 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 41 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 42 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may co inue provided grab samples are taken at least once per hours and these samples are analyzed for noble gas ross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . ~g It ACTION 43 -

With the number of channels OPERABLE less than' required by the Minimum Channels OPERABLE requirement, operation of these waste gas disposal system may continue 4^- "r t^ l ':

-4mps provided grab samples are taken and analyzed either l (1) every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during degassing operations of the reactor coolant system, or (2) daily during other operations.

ACTION 44 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the channel has been declared inoperable samples <

are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.

SEQUOYAH - UNIT 1 3/4 3-77

TABLE 4.11-1 (Coninued) '

2.22x108 is the number of disintegrations per minute per microcurie, Y is'.the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide, and ,

At from plant effluents is the elapsed time between midpoint of sample collection and time of counting UNDP4WT)

It should be recogni::ed that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particu-late measurement, b.

A composite sample is one which the quantity of liquid sampled is proportional to the quantity of liquid waste discharfed and in which the method of sampling employed results in a specimen which is representative of the liquids released.

c. Prior to analyses, all samples taken for the composite shall be throughly mixed in order for the composite sample to be represen-tative of the effluent release,

d. A batch release is the discharge of liquid wastes of a discrete volume.

' Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in the ODCM, to assure representative sampling.

e. A continuous release is the discharge of liquid wastes of a non-discrete volume; e.g., from a volume of system that has an input flow during the continuous release.

3ggy gg gg p,3 e @

f.

The principal gamma emitters for which the LLD speci icatio applies exclusively are the following radionuclides: Hn-54, Fe-5 , Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, )m# Ce-144 does not mean that only these 'nuclides are to be detected and reported.

This list l

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

g.

' Relesses from these tanks are continuously composited during releases.

With the composite sampler or the sampler flow monitor inoperable, the sampling frequency shall be changed to require representative batch samples from each tank to be released to be taken prior to release and manually composite for these analyses.

h. Applicable only during periods of primary to secondary leakage or the release of radioactivity as detected by the effluent provided the radiation monitor setpoint radiatiog monitor and allowing for background radiation during periods when primary toisl at a secondary leakage is not occurring.

SEQUOYAH - UNIT 1 3/4 11-4 1

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RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT l

I LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be used to reduce the radiotetive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent to unrestricted areas (see Figure 5;i-1) would exceed 0.06 mrem to the total body

or 0.2 mrem to any orgao* in a 31-day period.

t APPLICABILITY: At all times. I ACTION:

i

a. With radioactive liquid waste being discharged without

{ treatment '^r r::: i:2 21 f 2 and in excess of the above h limits, in lieu of an LER, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a t

Special Report which includes the following information:

i

1. Identification of the inoperable equipment or subsystems i

and the reason for inoperability,

2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and 4

3. Summary description of action (s) taken to prevent a recurrence.

, b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

i SURVEILLANCE REQUIREMENTS l

4.11.1.3.1 Doses due to lig.id releases shall be projected at least i

once per 31 days, in accordance with the methodology and parameters in the ODCM.

Per reactor unit f

i SEQUOYAH - UNIT 1 3/4 11-6 i

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RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE LIMITINGCONDITIdNFOROPERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents to areas at or beyond the site boundary (unrestricted-area)

(see Figure 5.1-1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and '

.Tosae133 N

b. For Iodine 131,djhsf" Tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

APPLICABILITY: At all times.

ACTION:

With the dose rate (s) exceeding the above limits, without delay restore the release rate to within the above limit (s).

SURVEILL/SCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.

z-m II 4.11.2.1.2 The dose rate due to I-131,/ T ritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.

l l

l SEQUOYAH - UNIT 1 3/4 11-8 i ,

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flinimum .

Sampling Analysis I.ower Limi t of '

Caseous Release Type Frequency Type of Detection (LLD)

Frequency Activity Analysis P P (pCi/ml)"

A. Waste Gas Storage Tank Each Tank Each Tank Ptsneyej6eyefa.'#er "2' _4

...>c.

h Grah Anna,m1Aa- - F-Mr I x to B. Containment ll

! Pi Di "d!E "- 8 ~0

1. Purge Each Purge 1x 10 ~0

,?, Each Purge 11 - 3 g Grah Sample 1 x 10

2. Vent Dj DJ Princo*f^6e===*

'l _ . ~8 E"#*t1 x 10 4 Each Day Each Day Grah Sample 11- 3 Prontopsl benene Ernitter 1 x to -6

{ C. Noble Gases and y Tritium il 11 " L;/ Goou. "

l x 10 "

- k, Grab ll m p

.g 1. Condensgr Vacu'um Sample q Exhaust 11 - 3 1 x 10 -6

' $N

g. K" 2.AuxiliagBuilding Exhaust pg p " e, g n

3. Service Building g g g.

Exhaust '

- Agy

4. Shield guilgling

'C gg, Exhaust D. $ , ~*

Iodine and Parti- Continuous f. W d N *~

g culates I-131 1 x 10 -12 **'

Sampler Charcoal yg"

1. Auxiliary Build-j ;- ing Exhaust Sample y.;

e g gg Continuous W Principal Gamma _33 "p i 2. Shield Building Sampler' Parti',ulate c

I x 10 g3 Exhaust Emitter 8 (I-131, Others)

-1 g Samole p Continuous il "

Cross Alpha 1 x 10 _33 Composite 3 Sampler

[

Particulate Sample j Continutous g

_gg O Sr-89, Sr-90 g

Compo ite 1 x 10 F

- Sampler Particulate Sampic E. Noble Cases all Continuous 7 1 x 10 -6 Noble Gas Noble Cases Releases types !!oni t o r !!oni tor as listed in C Gross lieta or Gamma

I TABLE 4.11-2 (Continued)

TABLE NOTATION

a. The LLD is defined, for the purposes of these specifications, as the I smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with only a 5% probability of falsely concluding that a blank observation represents a "real" signal.

1 e

for a particular measurement system (which may include radiochemical separation):

4 8 LLD = b E . V . 2.22x108 . Y , exp (A.at)

Where

l

', LLD is the "a priori" lower limit of detection as defined above in t microcurie per unit mass or volume.

I s b is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency as counts per disintegration,

) V is the sample size in units of mass or volume, 2.22x108 is the number of disintegrations per minute per microcurie,

(

1 Y is the fractional radiochemical yield (when applicable),

A and is the radioactive decay constant for the particular radionuclide, at for plant effluents is the elapsed time between midpoint of sample j collection and time of counting (midpoint).

It should be noted that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and 1

not as an a posteriori (after the fact) limit for a particular measurement.

i b' .

Sampling and analysis shall also be performed following shutdown, startup, or a thermal power change. exceeding 15% of rated thermal power within 1 bour unless (1) analysis shows that the dose equivalent I-131 con-centration in the primary coolant has not increased more than a factor of 3 and (2) the noble gas activity monitor shows that the effluent

activity has not increased by more than a factor of 3...J L .L1

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,.t_

_, ogen,

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. .. .-~+,

_ _ . - ~ - _ , . , _ , , , _ - - . ., _ - . , _ _ _ _ _ _ . . , . - . ,_.-__,..--__-,___-._.. _.

.- T*"LZ s.14 .: (

tinued)

TABLE NOTATION c.

Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded, d.

Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 2 days following each shutdown from 415% RATED THERMAL POWER, startup of 415% RATED THERMAL POWER or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in one hour and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLD's may be increased by a factor of 10.

e.

Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fule 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 calcula-tion made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3. .

g.

The principal ga.nma emitters for which the I.LD specification applies exclusive.y are the following radionuclides: Kr-87, Kr-SS, Xe-133, 1

Xe-133m, Xe-135, and Xe-138 for noble gases and Ma-54, Fe-59, I-131, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate principal gamma emitters. This list does not mean that only these nuclides are to be detected and reported. Other gamma peaks that are measureable and identifiable, together with the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.12.

h. During releases via this exhaust system, i.

Purging - Applicable in MODES 1, 2, 3, and 4, the upper and lower com-partment.; of the containment shall be sampled prior to PURGING. Prior to breaking containment integrety in MODE 5 or 6, the upper and lower compartments of the containment shall be sampled. The incore instrument room purge sample shall be obtained at the shield building exhaust between 20and 25 minutes following initiation of the incore instrument room purge.

J. Venting - Applicable in Modes 1, 2, 3, and 4; the containment will be vented to the containment annulus and then to the auxilary building via containment annulus fans. The lower containment compartment shall be sampled daily when venting is to occur to account for the radioactivity j being discharged from the venting process.

SEQUOYAH - UNIT 1 3/4 11-11

4 RADIOACTIVE EFFLUENTS DOSE - I-131., TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM

(

Q> - 133 LIMITING CONDITION FOR OPERATION-3.11.2.3

r-is3, 11 The dose to a MEMBER OF THE PUBLIC from I-131,ITritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at or beyond the site beundary (see Figure 5.1-1) shall be limited to the following from each reactor unit.

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,

b. During any calendar year:

organ. Less than or equal to 15 mrems to any APPLICABILITY: At all times.

ACTION:

.T- 133, g a.

With the calculated dose from the release of I-131, tritium, and all radionuclides in pa rticulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of an LER, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits,

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS AN 4.11.2.3 Cumulative dose contributi< f o

ns for the current calendar quarter y and current calendar year for I-131," tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

SEQUOYAH - UNIT 1 3/4 11-13 I

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TABLE 3.12-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES E

Reporting Levels c

3. ~ Water Airborne Particulate Fish Milk Analysis (pCf/1) or Gases (pCf/m3) Food Products

{ (pCi/Kg, wet) (pCi/1) (pC1/Kg, wet)

N-3 2 x 10 4( } NA NA NA NA 3

Mn-54 1 x 10 NA 3 x 10 4 NA NA 2

Fe-59 4 x 10 NA 1 x 10 4

NA NA Co-58 3 1 x 10 NA 3 x 10 4 NA NA 2

Co-60 3 x 10 NA 1 x 10 4 NA NA 2

Zn-65 3 x 10 NA 2 x 10 4 NA NA FP Zr-Nb-95 2 4 x 10 NA NA NA NA I-131 '2 0. 9 NA 3 1 x 10 2 {

Cs-134 30 10 3 1 x 10 60 1 x 10 3 Cs-137 50 20 3 2 x 10 70 2 x 10 3 2

Ba-La-140 2 x 10 NA NA 3 x 10 2 NA us (a) For drinking water samples.

@ a value et 30,000 yGA may be ved.This is 40 CFR Part 141 value. .'If no delskin 3

(b) Il no drinkly v4ter potkwmy ensh, a volane of 20 i C.) may b e ved.

R y v J d

__ _ _ _ . 1- -

O O n TABLE 4.12-1 S MAXIMUMVALUESFORTHELOWERLIMITSOFDETECTION(LLD)ah y i l

4 O

Z Airborne Particulate j '

Water orGag Fish Milk food Products Sediment ;

5 Analysis (pCi/1) (pCi/m ) (pCi/kg, wet) (pCI/1) (pCi/kg, wet) (pCi/kg, dry) -

Q gross beta 4 1 X 10

-2 NA NA NA NA H-3 2000 N NA NA NA NA NA Mn-54 15 NA 130 NA NA NA Fe-59 30 NA 260 NA NA NA Co-58,60 15 NA 130 NA NA NA m FP 2 Zn-65 30 NA 260 NA NA NA y

~

Zr-95 30 NA NA NA NA NA Nb-95 15 NA NA NA NA NA I-131 [)* 7 X 10'2 NA 1 60 NA 11 Cs-134 15 5 X 10-2 130 15 60 150 l 1 Cs-137 18 6 X 10 -2 150 18 80 180 en Q Ba-140 60 NA NA 60 NA NA 4 La-140 15 NA NA 15 NA NA E

s 14 no dM;,4 w.fre paway utsts, a v41.e a4 3000 pCi/l may be used.

49.TF no dM;y mier p6msy exists, a value *! 15 f li ll may be "SCO- \

)

i

TABLE 4.12-1 (Continued)

TABLE NOTATION

( t.

Th; ','_" #e :n:!,;i; c'__dr'.-t'n;

_m _3

...-a ws y,. . - . - -

m..

g y_

_7----

t:r :nd ;., f;;; -eter :; ;!r:

7, .,

_____._...t 771 -,, _ _ , i. c . c r i .~v 7, v r

-I' !:;;! ;- r*-- t' - !E ;C!/a :r id:-t!'i;d i, ;..-fe;; ;t:r 1.--i., a m. . . ....- <___ tt; _j;;;, ;7 ja ;g; ,,,,,; ;; ;; _;;;;;;j-

- 1 c' I '2!, d ...L;,,9 ets. .. g. . . ' ' , L; ;. ,;1, : . .

P=+=d t' . o 1,n .e , n _e - - - ---

r-- 8 v' ' 'J3*

b,1(. Other peaks which are measurable and identifiable, together with the y radionuclides in Table 4.12-1, shall be identified and reported.

5 i

l

. SEQUOYAH - UNIT 1 3/4 12-9

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- - " ' ~ ~ ~ - * '

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l RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A Land Use Census shall be conducted and shall identify within a dis-tance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest gardena of greater than 50 m 2 (500 fta) producing fresh leafy vegetation.

APPLICABILITY: At all times.

ACTION:

a. With a' Land Use Census identifying a location (s) that yields a calculated dose or dose commitment 20% greater than the values currently being calculated in Specification 4.11.2.3, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.

b. With a Land Use Census identifying a location (s) that yields a calculated c'1se or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) within 30 days to the Radiological Environmental Moni-toring Program given in the 00CM, if samples are available. The sampling location (s), excleding the control station location, having the lowest calculated dose or dose commitment (s), via the same

[( exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted.

Pursuant to Specification 6.14, submit in the next Semiannual Radio-active Effluent Release Report documentation for a change in the 00CM including a revised figure (s) and table (s) for the 00CM reflecting the new location (s) with information supporting the change in sampling locations.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-cocr survey, mail survey, telephone survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environ-mental Operating Report pursuant to Specification 6.9.1.6.

" Broad leaf vegetation sampling cf 4t least three dif ferent kinds af vegetation

,may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garder, census. Specifications for broad leaf vegetation sampling ;n Table 3.12-1.4c. shall be fcilowed, including analysis of control samples.

.sfadfM- %

=TT" ? - UNIT 1 .

3/4 12-10 J

/_

RADI0 ACTIVE EFFLUENTS BASES This specifi-cation applies to the release of gaseous effluents from all reactors at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

3/4.11.2.2 DOSE, NOBLE GASES This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable". The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MIMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision I, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at the site boundary are based upon the historical average atmospheric conditions.

.TODINE 133, 3/4.11.2.3 DOSE - IODINE 131,4 TRITIUM, AND RADIONUCLIDES y

This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the sa=e time implement the guides set forth in Sectica IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calcula-tional procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be sub-stantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodologies provided in NUREG/CR-1004, " A Statistical Ananlysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Rndionuclides", October, 1979 and Regulatory Guide 1.109, " Calculation of ~

SEQUOYAH - UNIT 1 B 3/4 11-3

RADIOACTIVE EFFLUENTS BASES Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average ,

atmospheric conditions. The release rate specifications for I-131, UE- lJ3 lJ Tritium, and Radionuclides in particulate form with half-lives greater than 8 days are dependent on the existing radionuclide pathways to man, beyond the site boundary. The pathways which were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.

3/4.11.2.4 CASEOUS RADWASTE TREATMENT The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given ic Section II,b of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portion:

of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I,10 CFR Part 50, for gaseous effluents.

3/4.11.2.5 -EXPLOSIVE GAS MIXTURE s This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen.

Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

SEQUOYAH - UNIT 1 B 3/4 11-4

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ADMINISTRATIVE CONTROLS The annual radiological environmental operating reports sh- 1 nclude summarized

~

and tabulated results in the format of Reculatory Guide 4.8, lecember 1975 of all radiological environmental samples taken during the report pe.'oc. In the event that some results are not available for inclusion with the rep (. t, the recort shall be submitted noting and explaining the reasons for the mis 'ng results.

The missing data shall be submitted as socn as possible in a supp mentary recort.

The reports shall also include the following: a summary description 'f the radiological environmental monitoring program; a map of all sampling 'ca-fons keyed to a table giving distances and di'rections from one reactor; and 5e results of licensee participaticn in the Interlaboratory Comparison Prog. m, required by Specification 3.12.3.

SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORTE 6.9.1.8 The semiannual radioactive effluent release report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year. The period of the first recort shall begin with the date of initial criticality.

6.9.1.9 semiannual radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste releasea frem the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reportina Radioactivity in Solid Wastes and Releases of Radio- -

active Materials in Liquid and Gaseous Effluents from Lignt-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix 8 thereof.

The annual radioactive effluent release report (Radiological Impact) to be submitted 60 days af ter January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.5 This s pe report shall include an assessment of the radiation 0 cases dut to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from' radioactive liquid and gaseous effluents to members of the puolic due to their activities inside the site boundary (Figure 5.1-1) during the report perioc. All assumotiens used in making these assessments (i.e. , specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accorcance with the OFFSITE DOSE CALCULATICN MANUAL (00CM).

1/ A singia.suomittal may be made for a multiple u.'it station. The submittal should ccmcine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall spegif7 the releases of radioactive m terial from each unit.. ' '

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ADMINISTRATIVE CONTROLS

b. a determination that the change did not reduce the overall con-formance of the solidified waste product to existing criteria for solid wastes; and

c. documentation of the fact that the change has been reviewed and found acceptable by the PORC.

2. Shall become effective upon review and acceptance by the PORC.

6.14 0FFSITE 00SE CALCULATION MANUAL (0DCM) 6.14.1 The ODCM shall be anproved by the Commission prior to implementation.

6.14.2 Licensee initiated changes to the ODCM: ,

semi-1.

Shall be submitted to the Commission in the next%annual radioactive 8 4MY h

release report pursuant to specification 6.9.1.9. This submittal shall contain:

a. sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information. Information submitted should consistent of a package of those pages of the 00CM to be changes with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s); ~

b.

a determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and

c. documentation of the fact that the change has been reviewed and found acceptable by the RARC.

2. Shall become effective upon review and acceptance by the RARC.

6.15 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous and Solid) 6.15.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid): W g g gg p

1. Shall be reported to the Commission in the "n.O b ^ .J,o, 7-*

for the period in which the evaluation was reviewd by the PORC. The ll discussion of each change shall contain:

a. A summary of the evaluation that led to the determiration that the change could be made in accordance with 10 CFR 50.59; e s.,bal et klmtim regared by this sec% may be made as feet dthe anne.sl FSAR update SEQUOYAH - UNIT 1 6-25

INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in table 3.3-12 shall be OPERABLE with their alam/ trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alam/

trip setpoints of these channels shall be detemined in accordance with the methodology and the parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

^

APPLICABILITY: .

'During releases'via these pathways.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, without delay, suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE take the ACTION shown ,

in table 3.3-12. Exert best effort to return the instruments to Sem,i-OPERABLE status within 30 days and, if unsuccessful, explain in i r.ne nexp Annual Radioactive Effluent Release Report why the inoper- !!

ability could not be corrected within 30 days.

c. The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13.b are not applicable.

SURVEILLANCE REQUIREMENTS .

4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by perfomance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in table 4.3-8.

SEQUOYAH - UNIT 2 3/4 3-68 e

.= - .- .- - - .- - = . - _ . . - - . - - __

i INSTRUMENTATION 1 i

, RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION k.

i LIMITING CONDITION FOR OPERATION i

1 -

j 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels l shown in table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to I ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm / ,

j trip setpoints of these channels shall be determined in accordance with the i ODCM.

APPLICABILITY: As shown in table 3.3-13 4

4 ACTION:

j a. With a radioactive gaseous effluent monitoring instrumentation j

channel alarm / trip setpoint less conservative than required by the j above specification, without delay, suspend the release of radioactive

gaseous effluent monitored by the affected channel or decl'are the j

channel inoperable, or change the setpoint so it is acceptably t

conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in table 3.3-13. Exert best efforts to return the instrument to -

f fees- OPERABLE status within 30 days and, if unsuccessful, explain in the nex6 Annual Radioactive Effluent Release Report why the operability N 4

could not be corrected within 30 days.

i' c. The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13.b are not applicable.

i 4

SURVEILLANCE REQUIREMENTS

)

4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel i

shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE

CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in table 4.3-9.

4 4

4 i

SEQUOYAH - UNIT 2 3/4 3-76 i

i i

[

TABLE 3.3-13 (Continued)

TABLE NOTATION

At all times.

During waste gas disposal system operation.

- - During shield build,ing exhaust system operation.

ACTION 40 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and

b. At least two technically qualified members of the Facility Staff independently verify the release rate, calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 41 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least'once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . --

ACTION 42 -

With the number of channels OPERABLE l'ess than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the grab samples are taken at least once per hours and these samples are analyzed for noble gas gross a vity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , ll ACTION 43 -

l2 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of this waste gas disposal system may continue f:: r; : I' f;,; provided H

grab samples are taken and analyzed either (1) every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during degassing operations of the reactor coolant system or (2) daily during other operations.

ACTION 44 - With the number of chancels OPERABLE less than required by the

' Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continued provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

' after the channel has been declared inoperable samples are I continuously collected with auxiliary sampling equipment as required in table 4.11-2.

e '

r SEQUOYAH - UNIT 2 3/4 3-79 l .. .

I L

1 TABLE 4.11-1 (Coninued) '

i 2.22x10s is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

}

A andis the radioactive decay constant for the particular radionuclide, olle i i between midpoint of sample and ti e of co n ng (midpoin t

1 It should be recognized that the LLD is defined as an a priori

! (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particu-late measurement.

b.

A composite sample is one which the quantity of liquid sampled is i proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

i c.

Prior to analyses, all samples taken for the composite shall be throughly mixed in order for the composite sample to be represen-tative of the effluent release. '

d.

A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, 3

.and then thoroughly mixed, by a method described in the ODCM, to assure representative sampling.

e.

! A continuous release is the discharge of liquid wastes of a non-

discrete flow during volume; e.g. , fromrelease the continuous a volume of system that has an input

' sWI glso be moeswed

f. The principal gamma em, wM en LLD d. fuIO .6 i

exclusively are the following itters for which the LLD speci cation applies radionuclides: Hn-54, F Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141 end Ce-144 59, ,This Co-58, list does not mean that only these 'nuclides are to be detected and y reported.

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

, g.

1 Releases from these tanks are continuously composited during releases.

.' With the composite sampler or the sampler flow monitor inoperable,

! the sampling frequency shall be changed to require representative i

batch samples from each tank to be released to be taken prior to release and manually composite for these analyses.

i h.

! Applicable only during periods of primary to secondary leakage or the

release of radioactivity as detected by the effluent radiatio monitor provided the radiation monitor setpoint is at a LLD of dix 10~g /Ci/mi and allowing for background radiation during periods when primary to secondary leakage is not occurring.

SEQUOYAH - UNIT 2 3/4 11-4

RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to t'ie liquid effluent to unrestricted creas (see figure 5.1-1) when averaged over 31 day:., would exceed 0.06 mrem to the total body

or 0.2 mrem to any organ

in a 31 day period.

APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid waste being discharged without treatment fr rc:; ti:2 31 d;,e and in excess of the above limits, in lieu of a ll LER, prepare and submit to the Commission within 30 days putsuant to Specification 6.9.2 a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action (s) taken to prevent a recurrence.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIPIMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with the methodology and parameters in the ODCM.

Per reactor unit SEQUOYAH - UNIT 2 3/4 11-6 f

m l' *

.J l

RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS

. DOSE RATE LIMITING CONDITION FOR.0PERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents to areas at or beyond the site boundary (tarestr-icted areas) (see figure 5.1-1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and i

2 4 e 133'

b. For Iodine 131,htritium, and for all radionuclides in particulate di :

form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

l APPLICABILITY: At all times.

4 ACTION:

i With the dose rate (s) exceeding the above limits, without delay restore the release rate to within the above limit (s). .

SURVEILLANCE REQUIREMEh7S 4

4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.

I I33 4.11.2.1.2 The dose rate due to I-131,+ tritium, and all radionuclides in g

particulate form with half lives greater than 8 days in gaseous effluents i

shall be determined to be within the above limits in accordance with the >

methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program

specified in table 4.11-2.

l

i l SEQUOYAH - UNIT 2 3/4 11-8 ,

c

. uwe *Wh

, , - , , - , , , _ ,,-n. - , - - - - . , . - -.

pr flinimum Lower Limit of -

m Sampling Analysis Type of p Gaseous Release Type Frequency Frequency Activity Analysis Detection ("LLD) ,

(pCi/ml) 8 Y P g A. Waste Gas Storage Each Tank Each Tank kiocp'lGemme!=8ine .g ll

Tank _r C2:2 1 x 10 Crah MwInf b- EmIMar B. Containment Pi c 1. Purge Di "I' ! : C: 8 1 x 10 ll

Each Purge Each Purge 11 - 3 1 x 10 q Grah Sample Q En.:nte

2. Vent Dj Dj y;; " _z

_ _: C:: 1 x 10 Each Day Each Day II-3 6 O Grah Sample 1 x 10 ,

C.

r frintiaal Gn-~n Fitter b, Noble Gases and ?! !! % "4 L C m 8 ~

Tritium Grab 1 x 10 " ll m o U

1. Condensgr Vacuum Sample !!-3 -6 0N Kg 1 x 10 Exhaust 2.AuxiliagBuilding yg Exhaust "ag

3. Service Building y g @.

Exhaust Sg7 4.Shieldguilging g&,

Exhaust $g*

x*~

Iodine and Parti- d D. Continuous f W 1-131 -12 '

g culaLes Sampler 1 x 10 g" g" "

Charcoa1

1. Auxiliary Build- Sample y.2 7 ing Exhaust yg e Continuous g

W Principal Gamma _jg yp

2. Shield Buiiding Sampler' d Particulate 1 x 10 Emitter 8 (I-131, Others) go Exhaust Samnle y g "

Continuous il Gross Alpha 1 x 10

_g3 Composite Sampler Particulate Sample Continutous 7 O Sr-89, Sr-90 1 x 10 q;

Composite Sampler Particulate g Sample E. Noble Gases all Continuous Noble Gas Noble Cases 1 x 10

-6 Releases types ?!onitor !!anitor Gross Beta or Gamma as listed in C

o TABLE 4.11-2 (Continued)

TABLE NOTATION

a. The LLD is defined, for the purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability virh only a 5% probability of falsely concluding that a blank coservation represents a "real" signal.

for a particular measurement system (which may include radiochemical separation):

LLD =

E . V . 2.22x10s . Y . exp (A.at)

Where:

LLD is the "a priori" lower limit of detection as defined above in microcurie per unit mass or volume.

h is the standard deviation of the background counting rate or of s

the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency as counts per disintegration, V is the sample size in units of mass or volume, 2.22x108 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable',

A and is the radioactive decay constant for the particular radionuclide, at for plant effluents is the elapsed time between midpoint of sample collection and time of counting (midpoint).

It should be noted that the LLD is defined as an a priori (before the

' fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

b.

Sampling and analysis shall also be performed following shutdown, startup, or a thermal power change exceeding 15% of rated thermal power within I hour unless (1) analysis shows that the dose equivalent I-131 con-centration in the primary coolant has not increased more than a factor of 3 and (2) the noble gas activity monitor shows that the effluent activity has

-- not increased by more than a factor of 3.:sf th: ::il: ;::

er" ; 3- ;;

-t 17::: '*% ;f ti: -.... .. .;,:i 1. ll SEQUOYAH - UNIT 2 3/4 11-10 W

/

I h TABLE 4.11-2 (Continued)

{ TABLE NOTATION ,

c.

(

Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months af ter changing (or af ter removal from sampler). Sanpling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 2 days following each shutdown from ?15% RATED THERMAL POWER, startup to 215% RATED THERMAL POWER or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in one hour and analyses shall 4

be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLD's may be increased by a factor of 10.

Ii

e. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fule 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 calcula-tion made in accordance with Specifications 3.11.2.1, 3.11.2.2 and .

3.11.2.3.

g. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, j Xe-133m, Xe-135, and Xe-138 for noble gases and Mn-54, Fe-59, I-131, Co-58, Co-60, Zn-65, Ho-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate principal gamma emitters. This list does not mean that only these nuclides are to be detected and reported. Other gamma peaks that are measureable and identifiable, together with the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.12.

h. During releases via this exhaust system.

i. Purging - Applicable in MODES 1, 2, 3, and 4, the upper and lower com-partments of the containment shall be sampled prior to PURGING. Prior to breaking containment integrety in MODE 5 or 6, the upper and lower compartments of the containment shall be sampled. The incore instrument room purge sample shall be obtained at the shield building exhaust between 20and 25 minutes following initiation of the incore instrument room purge.~

j. Venting - Applicable in Modes 1, 2, 3, and 4; the containment will be vented to the containment annulus and then to the auxilary building via containment annulus fans. The lower containment compartment shall be sampled daily when venting is to occur to account for the radioactivity being disenarged from the venting process.

SEQUOYAH - UNIT 2 3/4 11-11

RADI0 ACTIVE EFFLUENTS

.T 133 DOSE - I-131,%TRIkIUM,ANDRADIONUCLIDESINPARTICULATEFORM ll LIMITING CONDITION FOR OPERATION 2 - n t.'

3.11.2.3 The dose to a MEMEBER OF THE PUBLIC from I-131,4 tritium, and radio-nuclides in particulate form with half-lives greater than 8 days in gaseous ll effluents released to areas at or beyond the site boundary (see figure 5.1-1) shall be limited to the following from each reactor unit,

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and

b. During any calendar year:

organ. Less than or equal to 15 mrems to any APPLICABILITY: At all times.

ACTION:

r-133,

a. With the calculated dose from the release of I-131,htritium, and radionuclides in particulate form with half lives greater than ll 8 days, in gaseous effluents exceeding any of the above limits, in lieu of a LER, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are act applicable.

SURVEILLANCE REQUIREMENTS 2- 03.' -

r 4.11.2.3 Cumulative dose contr:

current calendar year for I-131,gutions tritium,for andtheradionuclides current calendar quarter and in particulate g form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

SEQUOYAH - UNIT 2 3/4 11-13

.,. ..AL.

- . _ _ - _ . - - . _ _ ____ - _ - - - _ = . _ - _ _ - . .

m TABLE 3.12-2 E

8 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONNENTAL SAMPLES 5

x _

Reporting Levels E

q Water Airborne Particulate Fish Milk food Products m Analysis (pCi/1) or Gases (pCi/m3 ) (pCi/Kg, wet) (pCi/1) (pCl/Kg, wet)

H-3 2 x 10 4( N.A. N.A. N.A. N.A.

Mn-54 1 x 10 3 N.A. 3 x 10 4 N.A. N.A.

2 4 Fe-59 4 x 10 N.A. I x 10 N.A. N.A.

4 Co-58 1 x 10 3 N.A. 3 x 10 N.A. N.A.

. Co-60 3 x 10 2 N.A. 1 x 10 4 N.A. N.A.

2 In-65 3- x 10 N.A. 2 x 10 4 N.A$ N.A.

2 Zr-Nb-95 4 x 10 N.A. N.A. N.A. N.A.

2 I-131 0.9 N.A. 3 1 x 10 Cs-134 30 10 1 x 10 3 60 1 x 10 3

i Cs-137 50 20 2 x 10 3 70 2 x 10 3

! Ba-La-140 2 x 10 2 N.A. N.A. 3 x 10 2 N.A.

(a) Fo driningwaterMI les. Thi Ve ea 3g000 (C aybg3h,is40CfRPart141value. If 80 drinkin) Wgter fGNway ex

&) If no drinkin3 mier perkw y esists , a val.e of zo pCi/t may be used. <

l e

O Y Al . *

m TABLE 4.12-1 g NAXIMUNVALUESFORTHELOWERLIMITSOFDETECTION(LLD)*'\ ff s

I Airborne Particulate c Water or Gag Fish Nilk Food Products Sediment z Analysis (pCi/1) (pci/m ) (pC1/kg, wet) (pCi/1) (pCf/kg, wet) (pCi/kg, dry) 1 X 10

-2 N.A. N.A. N.A. N.A.

gross beta 4 H-3 2000

N.A. N.A. N.A. N.A. N.A.

[

Mn-54 15 N.A. 130 N.A. N.A. N.A.

Fe-59 30 N.A. 260 N.A. N.A. N.A.

Co-58,60 15 N.A. 130 N.A. N.A. N.A.

R

Zn-65 30 N.A. 260 N.A. N.A. N.A.

U N.A. N.A. N.A. N.A.

4 Z r-95 30 N.A.

Nb-95 15 N.A. N.A. N.A. N.A. N.A.

-2 N.A. 60 N.A.

I-131 1 7 X 10 1 ll Cs-134 15 5 X 10 -2 130 15 60 150

~2 80 180 Cs-137 18 6 X 10 150 18 Ba-140 60 N.A. N.A. 60 N.A. N.A.

La-140 15 N.A. N.A. 15 N.A. N.A.

1 1

+14 no di.,k.'n) uster fathway exists, a velee of 3000 pCVI rney be used.

IS fli/l ny be used. q M k If no hink n3 wder ptkasy exists, a value of

1 TABLE 4.12-1 (Continued)

TABLE NOTATION h Th- '_ '_ n ': r -- - ' y ' ' - ' d r ' ' ' - .; a;;; ; . .d _- ' - - - * -- --- t -e -

, - .,. ..5. ... ,,. _. _.. _..'a 05:!'.

pt=

- : d by ..

,e ; e:- : ::::tr;;;;;, at :;;r::':: :1y 15 p0'/a.

. _ . _ s_ u. . _. . ._ r. n. ,i ___. . . .,,_

t., a m..+ --- c m. es. m13, e n- t y ; ; ; .; , _ , , ,,,,, , , ; g , _ _

pe*-4 --1-- - ar 7-111. drinking water ---tee <'i 5: s t y r.a + 3_

usu u ,. ...v.-,,

b. . Other peaks which are measurable and identifiable, together with the ll radionuclides in Table 4.12-1, shall be identified and reported.

)

SEQUOYAH - UNIT 2 3/4 12-9

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LANO USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A Land Use Census shall be conducted and shall identify within a dis-tance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest gardena of greater than 50 m2 (500 ft 2) producing fresh leafy vegetation.

APPLICA8ILITY: At all times.

ACTION:

a. With a' Land Use Census identifying a location (s) that yields a calculated dose or dose commitment 20% greater than the values currently being calculated in Specification 4.11.2.3, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.

b. With a Land Use Census identifying a location (s) that yields a

' calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) within 30 days to the Radiological Environmental Moni-toring Program given in the 00CM, if samples are available. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose comnitment(s), via the same

( exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted.

Pursuant to Specification 6.14, submit in the next Semiannual Radio-active Effluent Release Report documentation for a change in the 00CM including a revised figure (s) and table (s) for the 00CM reflecting the new location (s) with information supporting the change in sampling locations.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not appilcable.

I SURVEILLANCE REQUIREMENTS

' 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, mail survey, telephone survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environ-mental Operating Report pursuant to Specification 6.9.1.6.

Broad leaf vegetation sampling cf at least three different kinds of vegetation

,may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garder census. Specifications for broad leaf vegetation sampling in Table 3.12-1.4c. shall be fellowed,

, including analysis of control samples.

L.

l l

c48WPP049 - UNIT A 3/4 12-10

' l sm uove m

RADIOACTIVE EFFLUENTS

.s BASES 3/4.11.2.2 DOSE. NOBLE GASES This specification is provided to implement the requirements of Sections II.B.

III.A, and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasouably achievable". The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through sppropriate pathways is unlikely to be subs,tantially underestimated. The dose calculations in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, " Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors,"

Revision 1, July 1977. The ODCM equations provided for determining the air .

doses at the site boundary are based upon the historical average atmospheric conditions, ggggg,,3),

3/4.11.2.3 DOSE - IODINE-131, TRITIL?!. AND RADIONUCLIDES This specification is provided to impicment the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating f'exibility and at the same time implement the guides set forth in Sectica "V.4 of Appendix I to assure that the releases of radioactive materials in g aeous effluents will be kept "as low as is reasonably achievable". The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calcula-tional procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be sub-stantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are con:.istent with the methodologies provided in NUREG/CR-1004, " A Statistical Ananlysis of Selected Parameters fo'r Predicting Food Chain Transport and Internal Dose of Radionuclides", October, 1979 and Regulatory Guide 1.109, " Calculation of

' Annual Doses to Man from Routine Releases of Reactor Effluents for the Putpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determincing the actual doses based upon the historical average atmospheric conditions. The release rate specifications for I-131, tritium, and radio-d nuclides in particulate form with half-lives greater t n 8 days are dependent SEQUOYAH - UNIT 2 B 3/4 11-3

.T-133)

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SEQUOYAH - UNIT 2 5-2 ,

~

~ ~

ADMINISTRATIVE CONTROLS V

The 5nnual radiological environmental operating reports she'l include summarized and tabulated results in t'e format of Regulatory Guide 4.8, 7ecember 1975 of all radiological environmental samples taken during the report pe. #cc. In the event that some results are not available for inclusion with the repc t, the report shall be submitted noting and explaining the reasons for the mis 'ng results.

The missing data shall be submitted as soon as possible in a supp. 'mentary report. ;

The reports shall also include the following: a summary description 'f the radiological environmental monitoring program; a map of all sampling . cations keyed to a table giving distances and diYections from one reactor; and 5e results of licensee participation in the Interlaboratory Comparison Prog:im, required by Specification 3.12.3.

I SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT !

6. 9.1. 8 The semiannual radioactive effluent release report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality.

6.9.1.9 Semiannual radioactive effluent release reports shall include a summary of

~

the quantities of radioactive liquid and gaseous effluents and solid waste releaseo frcm the unit as outlined in Regulatory Guide 1.21, " Measuring, I Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio- -

! active Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix 8 thereof.

The annual radioactive effluent release report (Radiological Impact) i to be submitted 60 days afte- January 1 of each year shall include ai annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listig of wind speed, wind direction, atmospheric

, stability, and precipitation (if measured) on magnetic tape, or in the form of i joint frequency distributions of wind speed, wind direction, and atmospheric stabilityr$ This same report shall include an assessment of the radiation l doses due to the radioactive liquid and gaseous effluents released from the

unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary (Figure 5.1-1) during the report period. All assumptions used in making these assessments (i.e. , specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (00CM).

1/ A singie submittal may be made for a multiple unit station. The submittal 1

should ccmbine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

SEQUOYAH - UNIT 2 -2 rouabl.e fla at t l

+ stitotol*$

.Tn lirm. ofmy ical deig submhs*n be retsi wilk ho mek on site in a, f to NRC upon repost, 9

ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 Licensee initiated changes to the PCP:

1.

Shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change (s) was made. This submittal shall egntain:

a. sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information,

b. a determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and

c. documentation of the fact that the change has been reviewed and found acceptable by the PORC.

2.

Shall become effective upon review and acceptance by the PORC.

6.14 0FFSITE DOSE CALCULATION MANUAL (00CM) 6.14.1 The 00CM shall be approved by the Commission prior to implementation.

6.14.2 Licensee initiated changes to the OOCH: .

3dP

1. Shall be submitted to the Commission in the nextgI-release report pursuant to specification 6.9.1.9.annual radioactive This e Wat y submittal shall contain:

a.

sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.

Information submitted should consistent of a package of those pages of the 00CM to be changes with each page numbered and provided with an approval and date box, together with appropriate analyses *or evaluations justifying the change (s);

b.

a determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and c.

documentation of the fact that the change has been reviewed and found acceptable by the RARC.

-2.

Shall become effective upon review and acceptance by the RARC.

j SEQUOYAH - UNIT 2 6-30 l

l* . , .

j I N g

ADMINISTRATIVE CONTROLS 6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous and Solid) 6.15.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid):

M/

$gmi.amuel (ndiraclhe eft HVn

1. Shall be reported to the Commission in the ":- Q % :r 9 - Report ll fortheperiodinwhichtheevaluationwasreviewdbytheP5RC. The discussion of each change shall contain:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

b. sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

c. a detailed description of the equipment, components and proces-ses involved and the interfaces with other plant systems;

d. an evaluation fo the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendment,s thereto;

e. an evaluation of the change which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto;

f. a comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;

g. an estimate of the exposure to plant operating personnel as a result of the change; and

h. documentation of the fact that the change was reviewed and found acceptable by the PORC.

2. Shall become effective upon review and acceptance by the PORC.

4 Sdm;thl of I'nforM4fien r uired by tids section may be medt AS frf of thi nanuel FSAR yde .

/

b SEQUOYAH - UNIT 2 6-31

ML20140H223

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