ML19282B833

Forwards Draft Radiological Effluent Tech Spec Modified to Reflect Plant Design.Explains Reasons for Not Addressing Waste Solidification or Offsite Dose Calculation Manual

ML19282B833
Person / Time
Site:	Sequoyah
Issue date:	03/12/1979
From:	Gilleland J TENNESSEE VALLEY AUTHORITY
To:	Varga S Office of Nuclear Reactor Regulation
References
NUDOCS 7903160241
Download: ML19282B833 (85)

Text

. .

TENNESSEE VALLEY AUTHORITY CH ATTANOOG A. TENNESSrE 374ot 500C Chestnut Street Tower II MAR 121979 Director of Nuclear Reactor Regulation Attention: Mr. S. A. Varga, Chief Light Water Reactors Branch No. 4 Division of Project Management U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Varga:

In the Matter of the Application of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 As requested by D. B. Vassallo's letter of November 16, 1978, enclosed is a copy of the draf t radiological effluent technical specifications for the Sequoyah Nuclear Plant. These specifications have been modified to reflect the Sequoyah design.

The enclosed submittal does not address waste solidificacion. TVA has deleted this specification for three basic reasons. First, requirements for the shipment of radioactive vastes in 10 CFR 71 do not require solidification when a qualified shipping container is used for trans-portation. In addition, the Department of Transportation and the burial sites themselves do not require that wastes be solidified. Second, TVA does not agree with the NRC staff's definition of solidification, particu-larly the requirement for homogeneity. And third, compared to the benefits achieved, the projected dose levels associated with the proposed solid waste surveillance requirements are inconsistent with the ALARA program.

~

The Offsite Dose Calculation Manual (0DCM) has not been completed; con-sequently, it is not included with this submittal. It is anticipated that the ODCM will be in draft form and available for submittal to the NRC staff by March 20, 1979.

We would like to meet with the staff in the near future to discuss our ~

radiological effluent technical specification submittal.

Very truly yours,

( ,

) .# -

c

, 4 e m,-

J. E. Gilleland Assistant Manager of Power Enclosure 79031602%

\

l An Eaual Cecortumty Emc< oyer

8

]. 0 DEFINITIONS I

e E

?

CHANNEL CAllBRATION as -

1.9 A CHANNEL CAllBRATION shall be the adjustment, as necessary, of the k

channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL

, CAllBRATION shall encompass the entire channel including the sensor and l

alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.

The CHANNEL CALIBPATION may be performed by any series of sequential, over- .

lapping or total channe'l steps such that the entire channel is calibrated. [ __, ,

CHANNEL CHECK b "'

i e

jl.10 A CHANNEL CHECK shall be the qualitative assessment of channel be-jhavior during operation by observation. This determination shall include,

,,where possible, comparison of the channel indication and/or status with

other indications and/or status derived from independent instrumentation hchannels measuring the same parameter. L _.

CHANNELFUNCTIONALTESJ 1.11 A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify

, OPERABILITY including alarm and/or trip functions'. ----

b. , Bistable channels - the injection of a simulated signal into b hh

,, the sensor to verify OPERABILITY including alarm and/or trip

• n functions. -,

SOURCE CHECK gl .28 A SOURCE CHECK shall be the qualitative assessment of channel I -

j response when the channel sensor is exposed to a radioactive source.

1 -

L.

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SEQUOYAH UNIT 1 1-1 1

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• 1.0 DEFINITIONS (Continued) e 3

1-t 4 C 1 4A 4

f/1;ct y ,a 0FFSITE DOSE CALCULATION MANUAL (ODCM)  ;.

1.2.4 An 0FFSITE DOSE CALCULATION MANUAL (0DCM) shall be a manual contain- ,

ing the methodology and pa-ameters to be used in the calculation of off-site doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation , ,

c 5 [

Q 53m J(n g - '

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GASE0US RADWASTE TREATPENT SYSTEM k.h-::~~ ;:. '7" ~- ~ --D

- ,s 1.30 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and in-stalled to reduce radioactive gaseous effluents by collecting primary k

coolant system of fgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the enviroment.

VENTILATION EXHAUST TREATMENT SYSTEM 1.31 A VENTILATION EXHAUST TREATNENT SYSTEM is any system designed and

%,4' installed to reduce gaseous radiofodine or radioactive material in parti-culate fom in effluents by passing ventilation or vent exhaust gases - - - -

through charcoal adsorbers and/or HEPA filters for the purpose of removing .

iodines or particulates from the caseous exha"et stream prior to the -

release to the environment. Errgineetim safety Feafvtes (e5F) - -

afsnOyhenL C\ tan vP G Mtenk Ys nd V :o n ddet'N W U (E- U. .

\fEA.m ts-rtoA) GXHAUST 'G W A 7! W W S W N W CO' \W'O' -

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TABLE 1.2 FRE00EfiCY fl0 TAT 10l1 fiOTATIOfl FRE JEtiCY '

S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W At least once per 7 days.

M At least once per 31 days.

s v.,

Q At least once per 92 days. - d SA At least once per 184 days.

R At least once per 18 months.

S/U Prior to each reactor startup. -

r -.. .

P Completed Prior to each release. $)[,*

fi. A. flot applicable.

me

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, INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT INSTR.UMENTATION LIMITING CONDITION FOR OPERATION

~ ,. . ,

3.3.3.9 The radioactive liquid effluent monitoring instrumentation DF channels shown 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.

APPLICABILITY: As shown in Table 3.3-12.

l ,

ACTION: ~

a. With a radioactive liquid effluent monitoring instrumentation channel alam/ trip setpoint less conservative than a value which will ensure that the limits of 3.11.1.1 are met, imme-diately suspend the release of radioactive 1jquid effluents monitored by the affected channel or declare the channel in-operable. - '

b. With less than the minimum number of radioactive liquid effluent

j. monitoring instrumentation channels OPERABLE, TAke the [id;,.

• jj ACTION shown in Table 3.3-12. i p c. The provisions of Specifications 3.0.3 and 3.0.4 are not i applicable.

O NSURVEILLANCEREQUIREMENTS - - ...

d .

N .

4.3.3.9.1 The setpoints shall be deterttined in accordance with procedures -

/

as described in the CDCM and shall be recorded, l channel shall be demonstrated OPERABLE by perfomance of l the CHA CHECK, SOURCE CHECK, CHANNEL CAllBRATION, and CHANNEL FUNCTIONAL TEST

, operations during the MODES and at the frequencies shown in Table 4.3-11. - ,

g _ =!._ -

4.3.3.9.3 Records - Auditable records shall be maintained, et D 7_$

ww =c _ - . . dMM of all radioactive liquid effluent -

monitoring instrumentation alarm / trip setpoints. Setpoints and setpoint calculations shall be available for review to ensure that the limits of Specification 3.11.1.1 are met.

SEquoYAH UNIT 1 3/4 3-54 s

8 kp.g. , . . :. .. . , . - .

.; m . ~ c. m .x. s .. . w ... e p .T. 5

<i '- '

'j Q' h s N TliBLE.3.3-12

.-f'.p g RADI0 ACTIVE LIQUID EFFLU2flT M0t1ITORIrlG IrlSTRUMErlTATI0tl -

.. o

• 11

=

s MIrllMUM

• < c CHAtitlELS OPERABLE APPLICABILITY ACTI0tl

, 5 IrlSTRUMEtiT a ,

's.

1. Gross Radioactivity Monitors O Providing Automatic Termination

'ts, of Release At all tir:es during effluent I8

,r, a. Liquid Raduaste Effluent Line 1 releases

b. Steam Generator Bloudown 1 At all times during effluent 19 releases when primary to secondary

,i, -

Effluent Line leakage occurs At all times during effluent 19

c. Condensate Denineralizer Bldg. 1 Liquid Radwaste Effluent Line

• releases when primary to secondary leakage occurs

$; m f4 r 1

?. ','2 . Gross Radioactivity Monitors g flot Providing Automatic Termination y of Release -

j.  ! a. Essential Raw Cooling Water (ERCW)

Effluent Line 1 ,At all times 20 1

> l t

• l .- i

• Includes r nse, flush, and slurry waste from secondary system condensate deep bed demincralizer or filter-l'

'} demineralizers.

c. .

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l k

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Z~.

{ -

• * , y . .y r..--

y  : ,

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nf l '

TV -

0; y, TABLE 3.3-12 (Continued)

RADIOACTIVE LIOUID EFFLUE!!T f10:lITORIrlG IriSTRUMEtlTATIOil ,

c:= MI llMU:1 c- CHATflELS l ,

IrlSTRU:'ENT OPERABLE APPLICABILITY ACTIC_]

3. Flow Rate Measurement Devices ** .

a. Liquid Radwaste E'ffluent Line 1 At all times during effluent release 3 21

b. Condensate Derineralizer Effluent Line 1 At all times during effluent releases 21 when primary to secondary leakage occurs

. c. Steam Generator Bloudown Effluent 1 At all times during effluent releases 21 Line when primary to secondary leakage occurs

4. Radioactivity Recorders

a. Liquid Radwaste Effluent Line 1 At all times during effluent releases 23 u>

t b. Steam Generator Blowdown Effluent Line 1 At all times during effluent releases 23 u,

when primary to secondary leakage occurs ,

a At all times during effluent releases 23

c. Condensate Demineralizer Effluent Line 1 i i when pri, mary to secondary leakage occurs

5. Tank Level Indicating Devices (for tanks outside plant buildings) g, Condensate Storage Tank 1 At all times during primary to secondary 22

• • • leakage b, Steam Generator Layup Tank 1 At all times during primary to secondary 22

. leakage

• " Pump curves may be utilized to estimate floa; in such cases, ac tion statement 21 is not required.

t 4 l *** When connected to the secondary sys tem of the af fected uni t 6

6

TABLE 3.3-11 (Continued)

TABLE NOTATION

~

ACTION 18 With the number of channels OPERABLE less than required by the 6w Minimum Channels OPERABLE requirement, effluent releases may be resumed for up to 14 days, provided that prior to initiating '

EM:

a release:

1. At least two independent samples are analyzed in accordance wi th Specification 4.11.1.1. 3, and;

2. At least two technically qualified members of the Facility Staff independently verify the release rate calculations y and discharge valving;

'.l Ot!.erwise, suspend release of radioactive effluents via this pa thway.

ACTION 19 With the number of channels OPERABLE less than required by The Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14

• days provided grab samples are analyzed for gross radioactivity (beta or gamma) at %_

a limit of detection of at least 10-/ uCi/ gram or an isotopic evaluation is performed;

1. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the N secondary coolant is > 0.01 uCi/ gram DOSE EQUIVALENT I-131.

2. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is ,$ 0.01 uCi/ gram DOSE EQUIVALENT I-131.

ACTION 20 With the numbers of channels OPERABLE less than required by the Minimum Chanaels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided that at Icast once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> grab samples are collected and analyzed h.).

for gross radioactivity (

detection of at least 10 geta uCi/mi or gamma) at a lower or an isotopic limit of evaluation is performed. ~1' -

ACTION 21 With the number of channels OPERABLE less than required by the ',

Miniinum Channels OPERABLE requirement, effluent releases via ..

this pathway may continue for up to 14 days provided the flow "'

rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual . ,"J ' '

releases.

ACTION 22 With the numbers of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue for up to 28 days provided the tank liquid level is estimateo during all liquid additions to the ,,.

tank.

r-ACTION 23 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via ('

the affected pathway may continue for up to 14 days provided E the gross radioactivity level is recorded at least once per ""

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual release.

SEQUOYAU UNIT 1 3/43 57 g e , 8 *-

@ 8* h $n., $ " p I

• I

, _ _ _ , , . - - + - - - -

• TABLE 4.3-11 .

E c

• S RADI0 ACTIVE LIQUID EFFLUEf4T f40t1ITORIrld IriSTRut1EllTATI0ti SURVEILLAtlCE REQUIREf4EtlTS

$ CHAtitiEL c FUtlCTI0tlAL CHAtitlEL SOURCE CHAtitlEL '

5 H CHECK CHECK CALIBRATI0tl TEST IriSTRUMErlT

1. Gross Radioactivity rionitors Providing Alarm and Automatic Isolation

a. Liquid Radwaste Effluents Line D* P R(3) . Q(1)

I

b. Steam Generator Blowdown Effluent D* M R(3) Q(1)

Line

' c. Condensate Demineralizer Effluent D* P R(3) Q(1) i Line l

2. Gross Radioactivity f>onitors ,

y Providing Alarm l>ut- t@r fNidtag *

• y ' dar.wsatic. Isotection .

a. Essential Raw Cooling Uater D* M ,R(3) Q(2)

Effluent Line i

3. Activity Recor ders (6) .

a. Liquid Raduaste Effluent Line D* fl.A. R Q

b. Steam Generator Blowdown Effluent Line D* fl . A . R Q

c. ' Condensate Cemineralizer 9* ti . A . R Q Effluent Line e

~ ~~

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, j{. I '~' ' [ i' ~ ~ '

i g ,

.) j _ TABLE 4.3-11 (Continued)

a . .

y RADI0 ACTIVE LIQUID EFFLUErlT M0!!ITORIrlG INSTRUNENTATION SURVEILLAtlCE REQUIREME!1TS

~

=

. 4

~

g CHA:ltiEL

~ CHAtlNEL SOURCE CHAtitlEL FUNCTI0f1AL

- INST;.UME!!T CHECK CHECK CALIBRATIO1 TEST

4 Tank Level Monitors (for tanks outside the building) (7) a 4 Condensate Storage Tank D** N.A. R Q e b. Steam Generator Layup Tank D** h A. R Q 9

y m j.' 5 Flow Rate Monitors

' mh

a. Liquid Radwaste Effluent Line D I4) N.A. R Q

b. Steam Generator Blowdown Effluent O(4) ti . A .

R

)! Line Q

[ c. Condensate Demineralizer Effluent D(4) N.A. R Q Line

d. (_cobn 'Teu; er- Slaed uul ' o(4) ti.A. R Q l

l I s

\,

t; .

f%

TABLE 4.3-11 '

(Continuco) 1 TABLE NOTATION __

• During radioactive releases via this pathway ,

I

• • During system of primary to secondary the affected unit. leakage when connected.to the secondary (1)

The CHANNEL FUNCTIONAL TEST shall also demonstrate ,

tha if any of the following conditions exist: isolation of this pathway -- an 1.

Instrument indicates measured levels above the alarm / trip setpoint.

h

2. Circuit failure,

3. t Instrument controls not set in operate' mode p.-

(2)

The CHANNEL alarm annunciation occurs FUNCTIONAL if any of the TEST shall following also conditions om demonstrate exist: th 1.

Instrument se tpoint. indicates measured levels above the alarm / trip

2. Circuit failure. . - --._

3.

Instrument controls not set in operate mode

%. O (3)

The vendor channel calib' ration for radioactivity measurement ' ' ' '

instrumentation shall be accepted for initial calibration. Subsequent ' ~"'

calibrations.are to be performed at intervals of at least once per _

18 months using grab samples analyzed by laboratory instrumentation The laboratory instrumentation used in the calibration program shall .

have been calibrated using standards that have been obtained from ,

suppliers that participate in measurement assurance activities with -

the National Bureau of Standards. g,.g.,, .

(4) d.

s CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily [ '

on any day on which continuos, periodic, or batch releases are made. .

SEQUoYAll UNIT 1 3/4 3 60

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.s INSTRUMENTATION RADI0 ACTIVE GASE0US PROCESS AND EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION y

3.3.3.10 The radioactive gaseous process and effluent monitoring instru-imentation channels shown in Table 3.3-13 shall be OPERABLE with their alam/ trip setpoints set to ensure that the limits of Specifica-tion 3.11.2.1 are not exceeded.

jAPPLICABILITY: As shown in Table 3.3-13. l ACTION: h

a. With a radioactive gaseous process or effluent monitoring in-trumentation channel alam/ trip setpoint less conservative i than a value which will ensure that the limits of 3.11.2.1 are met, declare the channel inoperable.

. b. With les,s than the minimum number of radioactive gaseous process  !

or effluent monitoring instrumentation channels OPERABLE, take ~ ;- '

the ACTION shown in Table 3.3-13. pp

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

a SURVEILLANCE REQUIREMENTS 4.3.3.10.1The setpoints shall be determined in acccedance with procedures .--

as described in the ODCM and shall be recorded. @y* *

'4.3.3.10.2Each radioactive gaseous process or effluent monitoring instrumen- l -

itation channel shall be demonstrated OPERABLE by perfomance of the CHANNEL " ,

' CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST opera-Itions during the MODES and at the frequencies shown in Table 4.3-12.

. ,7 .- ,

4.3.3.10.3 Auditable records shall be maintained of the calculations madef pi-nN: c H anc m o. @ ccedu-c: " the ^< ,11 r,Nc ti . c ,., cc ;n

e**4 ef fl uent monitoring instrumentation al am/ trip setpoints. Setpoints Land setpoint calculations shall be available for review to ensure that the '

i limits of Specification 3.11.2.1 are met.

.I 0 f 4l[ radb4c.N6 g aSeou$ >

l

'f "f e-i

[ SEQUOYAll UNIT 1 3/43 61 h3-

[

. G l.k:. ;

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• ~

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_m . __. a a > J-m i

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f., I .f

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c. ; ' .

w .

r1

,; ; g JABLE 3.3-13

,  :' S i .5, g RADI0 ACTIVE GASEOUS EFFLUErlT MotlITORIr:G It;STRU:1EtiTATIO 1 C

2 U Mirift.!Ufl

<f - CHAfitlELS

_IllSTRUME:IT OPERABLE APPLICABILITY FUff CT IO.'l ACTIC.

1. Waste Gas Holdup System Effluent System Flow Rate

a.

• 1 System F1 w Rate 25

Measuring Device

s. Measurema..t

2. Waste Gas Holdup System Explosive i

j,' Gas Monitoring System

-1. .

i.-i o a. Hydrogen tfonitor 1 9 Zm **

% Hydrogen 27

b. Oxygen tionitor l'. m, 1 ** g0xygen

. 27 i

i .-

e 9.

I 4

• I m

D '

i'

'{

') , .

a

i9

.s-l

y. .

". L . -

~. ?. w TABLE 3.3-13 (continued)

')t' E g

, RADIOACTIVE GASEOUS EFFLUErlT f40:11 TORII:G IflSTRUf4E lTATI0tl

. l :

- si f4IllI 4UM E

IfJSTRU"E::T CHAffilELS OPERACLE APPLICABILITY FUliCTint: ACTIO!!

'[ ~

cont.ucus Saldase P0mts

3. (see Iist belcu;)

, a. floble Gas Activity f4cnitor 1

• Radioactivity Rate Ite3surement 26 f.

'[-

, b. Iodine Sampler Cartridge 1

• hple IodM25 28

c. Particulate Sampler '

Filter 1

• famglc go.-t. c utteteg 28

d. Effluent System Flow 3 Rate fleasuring Device 1

• System Flow Rate f*easurement 25 -

. u .

e. floble Gas Sampler Flow -

Rate fleasuring Device 1

• Sampler Flow Rate fleasurement 25

. 3. e

.p. (a) Condenser Vacuum Exhaust Sys tem

'}.

(b) Shield Building Exhaust System 'A

)

./ (c) Auxiliary Building Ventilation Syste.n N

j

.. ; (d) serv.'ce Bs.ta mg Ve.itd4.o t .5$s tem e

.[

• 4

.=,.

.i I x tein ge w.1tn ws pItaw Jm 'A ^&

f's:r.

f/ ,. _. . g s. - ,. ; . .. . --

-e f ,

TABLE il0TATION i i I

l '

• During radicactive rele'ses via this pathway p

' f*p rY.

• • During the filling of the waste gas decay tanks i

i ACT1011 2 5 With the number of channels OPERABLE less than required by the ,

l Minimum Channels OPERABLE requirement, effluent releases via j this pathway may continue for up to 28 days provided the flow j rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.  ;

ACTION 26 With the number of channels OPERABLE less than required by the '

Minimum Channels OPERABLE requirement, ef fluent releases via this pathway may continue for up to 28 days provided grab $-

samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are anal.yzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. ,

ACTION 27 With the number of channels OPERABLE less than required by the

Minimum Channels OPEP.'BLE requirement, operation of the waste gas hold m system may continue provided grab samples are collected at least.once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within ensuing 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 28 With the number bf channels OPERABLE less than required by the Minimum Channels OPERABLE requirener.L, ef fluent releases via h

this pathway may continue for up to 28 days, provided samples are continuo 0 sly collected with auxiliary sc nling equipment for periods on the order of seven (7) days. ,

\ .

I h

n 1 .

iV& . .

'.2d4.1 i

Ii P

d SEQUOYAll UNIT 1 3/4 3 64 I

1

.,ff .S .

- . . , _ ~ c , ,, ' ,

. . . . ; . . . e y, .

, , /2, '

K:; -

.e .,: .

s - -

V l 4 l p. TABLE 4.3-12 i

E S RADI0 ACTIVE GASEOUS EFFLUEtiT t10filTORiflG IflSTRut!EtlTATI0tt SURVEILLArtCE REQUIREf1EtlTS g

c CilArlflEL z '

CilAftflEL SOURCE CilArlflEL FurtCTI0tlAL

, U IflSTRUt1ErlT CilECK CilECK CALIBRATI0tl TEST

' ~

l , 1. Waste Gas Decay Tanks

a. System Effluent Flow Rate P* ft/A R Q fleasuring Device

,- 2. Waste Gas Holdup System Explosive Gas flonitoring System s y a. Hydrogen tionitor D** ft/A Q(4) ll ti

b. Oxygen f1onitor

[ .

Da* tl/A Q(5) .

LTl l

Y 4

t e

G T.

9 t

.;; I , .

T l

' 3'

. .. ! 4 . . .  ; .

J '

.Y TABLE 4.3.12(Continued)

~

$ RADI0 ACTIVE GASEOUS EFFLUEllT M0ilITORING INSTRUMENTATI0fl SURVEILLAllCE REQUIREMErlTS E CHAtlNEL SOURCE CHANilEL CHAfillEL FUf1CTI0flAL '

, y IriSTRUMErlT CHECK CHECK CALIBRATION TEST

• c:. Cu.,1mais Relesse Po, ors

• l 5 3. (see list below)

! H

~ a. floble Gas Activity Monitor D* i: R(3) Q(2) f

! b. Iodine Sampler D* N.A. N.A. N.A. '

! c. Particulate Sampler D* N . a .- N.A. N.A.

l d. System Effluent Flow Rate i

Measurement Device D.* N.A. R Q e- floble Gas Sampler Flow Rat Measurement Device D* fl . A - R Q. .

u -

w .

g (a) Condenser Vacuum Exhaust System -

(b) Shield Building Exhaust System Y (c) Auxiliary Building Ventilatio n System (d) ferv,'ce $s;lja Vg,1 t Iafi M 6 5 M ^

1 t

Y Ih I w" Y) o p.

U 2

b,

. ,/ ,

6

, .< .,a ..

i ,. .

)

'"1-j TABLE 4.3-12

! (. Con tinued) l J l TABLE NOTATION

??g;!-g *During radio

' active releases via this pathway 3p .-=

• • During the filling of the waste gas decay tanks i

l

) . ,

(1)

J L. --

The isolation CHANNEL of this pathwayFUNCTIONAL and control room TEST alarm at automatic shall a also dem

.s.,

3454 if any of the following conditions exist: nnunciation occurs j 1.

p,, .'

4 Instrument indicates measured levels setpoint.

rip above the 2.

Circuit failure.

3.

4.

Instrument indicates a downscale failure.

5N Instrument controls not set in operate mode . '

F 9pm (2) ~~

l, The CHANNEL alarm annunciation FUNCTIONAL occurs if any of theTESTfollowing at control shall also demo conditi room

1. ons exist:

an

\

Instrument indicates measured levels se tpoint.

. rm/ trip above the ala

2. _..

Circui t failure. - .

3. M il 4.

Instrument indicates a downscale failure. '~'

11 Instrument controls not set in operate mode .

(3) 1 'i The vendor channel calibration for radioactivity measurement '

instrumentation shall be accepted for initial calibration. Subsequent .

f calibrations are to be performed at intervals of at least once per 18 months using grcb samples analyzed by laboratory instrumentation.

4 The laboratory instrumentation used in the calibration program shall have been calibrated using standards that have been obtained from suppliers that participate in measurement assurance activities with

__ the National Bureau of Standards.

a SEQUOYAll UNIT 1 -

3/4 3-67 . - . . - -

~

.. g g w.r n +.,.: ;. ~...:.

.r.,.

s. . n ...:. y m .. m >=m 4

1 ns . .n=.,m.4;y

. TABLE 4.3-12 (Continued) i (4) The CHANNEL CALIBRATION shall include the use of standard gas samples '

containing a nominal: '

l. One volume percent hydrogen, balance nitrogen; and i

2. Four volume percent hydrogen, balance nitrogen.

(5) The CHANNEL CALIBRATION shall include the use of standard gas samples {'

containing a nominal: -

1. One volume percent oxygen, balance nitrogen; and

2. Four volume percent oxygen, balance nitrogen.

1 U

r~?%m -

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i

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e 3/4.11 RADI0 ACTIVE EFFLUENTS e.. 3/4.11.1 LIOUID EFFLUENTS

• 48 CONCENTRATION 1

.4 LIMITING CONDITION FOR OPERATION jn' 3.11.1.1 The concentration of radioactive material released at anytime from the site to unrestricted areas (see Figure 3.11-1) shall be limited

, to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolged or entrained noble gases, the concentration shall be limited

.} to 2 x 10- uCi/ml total activity.

APPLICABILITY: At all times. -

! ~ 4. ,

.. ACTION:

Ih-With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits, immediately restore con-centration within the above limits and provide prompt notification to the Commission pursuant to Specification 6.9.1.12.

SURVEILLANCE REQUIREMENTS - 4.11.1.1.1 The concentration of radi'oactive material at any time in liquid effluents released from the site shall be monitored Q ]d in accordance with Table 3.3-12.

4.11.1.1.2 The liquid effluent monitors having provisions for automatic termination of liquid releases, as listed in Table 3.3-12, shall be used to limit the concentration of radioactive material released at any time from the site to unrestricted areas to the values given in Speci-fica tion 3.11.1.1.

-2O]

4.11.1.1.3 The radioactivity content of each batch of radioactive liquid waste to be discharged shall be determined prior to release by sampling and analysis in accordance with Table 4.11-1. The resul ts of pre-release analyses shall be used with the methods in the ODCM to assure that the concentration at the point of release is limited to the values in Speci fication 3.11.1.1.

4.11.1.1.4 Post-release evaluation of composite samples shall

be perfonned in accordance with Table 4.11-1. The resul ts of the post-

.dQM,  : release analyses shall be used with the methods in the ODCM to

~^m .

assure that the concentrations at the point of release are limited to the values in Specification 3.11.1.1.

3/4 11-1 SEQUOYAH UNIT 1

i .

SURVEILLANCE REQUIREMENTS (Continued) 4.11.1.1.5 The radioactivity concentra' tion of liquids discharged from

• continuous release points shall be detemined by collection and analysis ,~

of samples in accordance with Table 4.11-1. The results of the analyses .

t-(WT k

shall be used with the methods in the ODCM to assure that the concentrations at the point of release are limited to the values in Speci fication 3.11.1.1.

4.11.1.1.6 Reports. The semiannual Radioactive Ef fluent Release Report shall include the infomation specified in Specification 6.9.'.9.

h-

$..^ $ *?  %

e

. ee-

. =s e .% .

. 1, \ ,.

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SEQUOYAli JNIT 1 3[411-2 k#N m * '

y f M~'$ g $ e a$ (m e

.. , ..e. - - .

. 7. , ....

. ;..q , g,,9 TABLE (.11-1 RADIOACTIVE LIOUID WASTE SAMPLIt!G At;D At;ALYSIS PROGRAM

- i

..j Lower Limit'

.s Liquid Release Type Sampling Minimum Type of Activity of Detection 4 Frequency Analysis Analysis (LLD)

Frequency (uCi/ml)a P P i A. Batch Waste Re- Each Batch Each Batch Principal. Gamma 5 x 10-7 b

, lease Tankse Emitters 9

"~

1. Waste Condensate ~

'M Tanks (3) 1-131 1 x 10-6

2. Cask Decon Tank (1 1

3. Laundry Tanks (2)

_ 4. Chemical Drain Dissolved and 1 x 10-5 One Batch /M M Tank (1) Entrained Gases

5. Monitor Tank (1)

%~vf. T 6. Non-reclaimable

' P H-3 1 x 10-5 i

Waste Tank (1) Each Batch M 9 C' CompsiteC

'fns Gross a 1 x 10-T

8. Distillate Tanks (2) P-32, 1 x 10-6 Each Batch Sr-89, Sr-90 5 x 10-8

-Q g) Compositec B. Plant Continuous once per dayC W Principal Gamma b Releases f Composite d Emitters 9 5 x 10-7 (Steam generator grab sample blowdown performec I-131 1 x 10-6 when primary to -

,p 4 4

secondary leakage g

" 9 occurs and Grab Sample discharging to M Dissolved and Entrained Gases 1 x 10-5 l

theenvironment).

d M

H-3 1 x 10-5 g weekly - d Composite l Gross a 1 x 10-7 P-32 1 x 10-6

~ . - .

monthly d Q, Sr-89, Sr-90 5 x 10-8 a Composite

,, j . SEQUOYAll UNIT 1 374 11-3

a . . _ ..

TABLE 4.11-1 (Continued)

TABLE NOTATION u-4 A5]T]

• 1 a. The lower limit of detection (LLD) is defined in Table Notation a. of

, . Tabl e 4.12-1 of Speci fication 4.12.1.1.

For certain radionuclides with low gamma yield or low energies, or for

'4 b.

certain radionuclide mixtures, it may not be possible to measure radio-nuclides in concentrations near the LLD. Under these circumstances, the LLD may be increased inverpely proportionally to the magnitude of the gamma yield (i.e., 5 x 10 /I, where I is the photoa abundance expressed as a decimal fraction).

. ~ . ,

au c. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which

, the method of sampiing employed results in a specimen which is repre-sentative of the liquids released.

d. Samples shall be collected in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the comoosite shall be thorouchly mixed in order for the cnmnnsite sample to be representative of the effluent release.

g e. A batch release is the discharge of liquid wastes of a discrete vol ume.

2

f. A continuous release is the discharge of liquid wastes of a aon-di sc rete volume; e.g., from a volume of system that has an input flow during the continuous release.

g. The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, .

Q, . Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144

.. W

~

This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identi fied and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level . When unusual circumstances resul t in LLD's higher than required, the reasons i shall be documented in the semiannual Radioactive Ef fluent Release Report.

I SEquoyAH catr i 3/4 11 4 I '

4 l .

$6 6 *

- 8 '

/ >,

h. /,

Td I yf b -

1

-k L ___.

l }/' a. -

This figure shall consist of a map 9shW. '

of the site area showing the unre-stricted area boundary for liquid i effluents as defined in 10 CFR Part 20.3(a)(17).

k

.\/ . , . . .

~ W&

wn s

Figure 3.11-1 - ' - -

is.M PWR-STS-I 3/4 11-5

^ .

. .--m :.n, ;. ,.. ; -

O..{.-- .,. .. : ,<. . ..

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RAC10 ACTIVE EFFLUENTS DOSE .

LIMITING CONDITION FOR OPERATION ~

s .-

,4J .

3.11.1.2 The dose or doso commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas (see Figure 3.11-1) shall be limited:

a. During any calendar quarter to < 1.5 mrem to the total body and to < 5 mrem to any organ, a3d * .

l

b. During any calendar yea,r to ,< 3 mrem to the total body and to

~ < 10 mrem to any organ.

l g' -

pi At all times.

APPLICABILITY:

Ed ~

ACTION: f cv M VbE#g p ?',

a.

f(A Mt';rtM b i b.4 \

With the calculated dose froq the rele'ase of radioactive materials

,I in liquid effluents exceedin any of the above limits, prepare and --

I submit to the Commission wit in 30 days, pursuant to Specifica- r.h i tion 6.9.2, a Special Report which identifies the cause(s) for ex- %T

' ceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose or dose commitment to an individual from such re-leases during these four calendar quarters is within 3 mrem to the I

total body and 10 mrem to any organ. This Spec.ial Report shall - ^ -

also include (1) the results of radiological analyses of the r?r drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act. ( Applicable only if

%n'*

l~

drinking water supply is taken from the receiving water body.) < '

b. The provisions of Specifications 3.0.3 and 3.0.4 are not appl icabl e. *

, .t . m s. ,

SURVEILLANCE REQUIREMENTS - 4.11.1.2.1 Dose Calculations. Cumulative dose contributions from liquid affluents shall be detennined in accordance with the Offsite Dose Calcu- .

lation Manual (00CM) at least once per 31 days. >.

4.11.1.2.2 Reports. The semiannual Radioactive Effluent Release Report shall include the information specified in Specification 6.9.1.9. .

• These doses are per reactor 3/4 11-6 SEQUOYAH UNIT 1

.y,.a

.. >. 7... .. . x ,- .

3,. .

- (, , .y -;. q:p

.- ,.r-

. R'AD10 ACTIVE EFFLUENTS LIQUID WASTE TREATMENT .

LIMITING CONDITION FOR OPERATION - - -

5.-

c;ppropria4e, subsystem o f -the,. plR6 3.11.1.3 TheAliquid radwaste treatment system shall be OPERABLE. The system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected dose due to liquid effluent releases to unrestricted areas (see Figure 3.11-1) when averaged over M 3l l days would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

APPLICABILITY: During liquid effluent releases

'22?'s ACTION

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special\,Report l., g ,Cwhich m s>includes k a NN.N theofollowing r*p .rMel

• infonnation:[h..t*Ct h .* %. N q'I-

1. Identification of equipment or subsystems nod OPERABLE and the reason for inoperability.

2. Action (s) taken to restore the inoperable equipment to

~

.W OPERABLE status.

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

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

SURVEILLANCE REOUIREMENTS .

4.11.1.3.1 Doses due to liquid releases to unrestricted areas shall be -- - -

projected at least once per 115f days. l

31 4.11.1.3.2 The liquid radwaste system shall be demonstrated OPERA 3LE at ,

least once per 92 days unless the liquid radwaste system has been utilized -

to prccess radioactive liquid effluents during the previous 92 days.

S

. #*e 6 e.-

l l)

S EQUO ' i' ti if, ; n l_  ?/q

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w ,. . ..

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• 4 g g g g g* gd '

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RA010 ACTIVE LffLUENTS LIQUID HOLOUP TANKS LIMITING CONDITION FOR CPERATION 3.11.1.4 The quantity of radioactive material contained In each of the l f o l l ow i ng t ank s sha l l be l im i t ed Q Teag= bas, exc l ud i ng tr i t i um and dissolved or entrained noble gases.

4 . Condensate Storage Tank b . Steam Generator Layup Tank b6 DN#C ,

APPLICABILITY: At all times.

Cf ACTION: E, mFct.m3pc9 L.

a. With the quantity of radloactive material in any of the above listed tanks exceeding"the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hrs either reduce the tank contento to within the limit or provide ,

i, prcrnpt notIf IcatIon to the Comm!sslon pursuant to SpecIf Ica-tion 6.9.1.12. The written followup report shall include a p y.

t y.*

schedule and cescription of activities pleaned and/or taken to *~

reduce the tank contents to within the above limit,

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

r_.

SURVEILLANCE REQUIREMENTS s ,.' , ,

4.11.1.4 The quantity of radioactive material contained in each of the W

above listed tanks shall be determined to be within the above ilmIt by ..,..

~

analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to th( tank. .

.. l .

w

~...

Ys .'.

SEQUOYAH UNIT 1 3/4 11-8

6,>lW

1 .. . ' ,.

^ ~ .<-< %G:.u..-ve w nn++, .c :' ::G.W

=

. R D10 ACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS 0

0_0_SE RATE -

LIMITING CONDITION FOR OPEf<ATION 3.11.2.1 The dose rate, at any time, in the unrestricted areas (see Figure 5.1-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values: ,

i

a. The dose rate limit for noble gases shall be j 500 mrem /yr to I the total body and j 3000 mrem /yr to the skin, and

b. The dose rate limit for all radioiod:nes and for all radioactive -

materials in particu. late fom and radionuclides other than noble gases with half lives greater than 8 days shall be j 1500 mrem /yr to any organ.

APPLICABILITY: At all times. .

ACTION

With the dose rate (s) exceeding the above ifmits, immediately decrease the hE

. release rate to comply wi th the limit (s) give in Specification 3.11.2.1

and provitte prompt notification to the Commission pursuant to Specifica-

': tion 6.9.1.12.

1. ! SURVEILLANCE REQUIREMENTS

[4.11.2.1.1 The release rate, at any time, of noble gases in gaseous gs '

': effluents shal.1 be controlled by the offsite dose rate as established above in Specification 3.11.2.1.

4.11.2.1.2 The noble gas effluent continuous monitors having provisions for the automatic temination of gaseous releases, as listed in Table 3.3-13, shall be used to limit offsite doses within the values established in [ ,-

Specification 3.11.2.1 where monitor setpoint values are exceeded. ,_

4.11.2.1.3 The release rate of radioactive materials, other than noble ,

gases, in gaseous effluente shall be determined by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, speci fied in Table 4.11-2.

e W .mo SEQUOYAH UNIT 1 3/4 11-9 $

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. ~ . . ' p;, ' ,

c

. i',.. : w c . .. ? ~~' '.' M

.  :.;-.E.,.u;, ,~j.

~ '

. SURVEILLANCE REQUIREMENTS

'4 11 2 1 4 The dose rate in unrestricted areas, due to radioactive materi-als other than noble gases released in <jaseous effluents, shall be ,,

determined to be within the required limits by using the results of the sampling and analysis program, speci fied in Table 4.11-2, witn the methods [. 5' in the ODCri.

4.11.2.1.5 Reports The semiannual Radioactive Ef fluent Release Report shall include the infomation specified in Specification 6.9.1.9.

s 5 .

~hV p

D ja y

. #'eW st OMe-t-

o r-t SEQUOYAll UNIT 1 e-

'i$p; t s. ',, . ... v. . .

= ~. . & ~' 's.; + : e ,: , . --_ .. ; . .-y 7- -;. .a. : e . ,' . - . .. ~- .-:, .s,;.4 -;~p3Q. 'r. .

t

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TABLE 4.11-2 ~

h RADI0 ACTIVE GASE0US WASTE SAtiPLif1G AffD AflALYSIS PROGRA!!

4

.{ .

'. Sampling ay s w tM

, j f E

Gaseous Release Type Frequency Frequency Type of Activity Analysis

• C 1 (LLD) i

~b h Mob \o Gosey 1 *Idt iver E $1. Condenser Vacuuri -4y

' M li Principal Gamma Emitters _f 1 x 10 3 Exhaust 9,c . Grab li

• Sample H-3 1 x 10-6

2. Auxiliary Bidg.

Exhaust c

[-

3. Service Bldg.

Exhaust

4. Shield Bldg.

Exhaust h,c J R , 6. To dine n a d I b ticube [

^ d 13 All Release Types Continuous e W _

I-131 1 x 10-12

~ as listed in A. Charcoal 7

Sample I-133 1 x 10-10 ,

t 5 Continuous e pd Particulate Principal Gamma Emitters f -j)

Sample (1-131,Others) 1 x 10 Continuous e M G:oss alpha 1 x 10-II Composite Pa rticula te Sanple Continuous e Q Sr-89, Sr-90 1 x 10-II Composite Particulate Sample __

l h

I +7 4

i l

. r't "i

• g

.4

, ,. 4 TABLE 4.11-2 (Continued)

TABLE NOTATION

, a. The lower limit of detection (LLD) is defined in Table Notation a. of .

Table 4.12-1 of Spe~ci fication 4.12.1.1.

g

b. For certain radionuclides with low gamma yield or low energies, c.-

for c,ertain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near the LLD. Under these circum-stances, the LLD may be increased inversely proportionally to the magnitude of the gamma yield (i.e.,1 x 10-4/I, where I is the photon abundance expressed as a decimal fraction).

. i

\

c. Analyses shall also be performed following shutdown, startup, or similar operational occurrence which could alter the mixture of radionuclides.

d. Analyses shall also be perfonned at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 7 days foll owi ne each shutdown, startup or similar operational occurrence  %

which did lead to significant increases or decreases in radio-iodine releases. Samplers shall also be changed and analyzed at the in tervals in Speci fications 3.11.2.1 and 3.11.2.3. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased by a factor of 10.

l e. 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 wi th Specifications 3.11.2.1, -

3.11.2.2 and 3.11.2.3. '

f. ..

The principal gamma emitters for which the LLD specification will - * ' '

apply are exclusively the following radionuclides: Kr-87, Kr-88, l Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-55, Mo-99, Cs-134, 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 measurable and identi fiable, together with the above nuclides, shall also be identi fied and reported. Nuclides which are below the LLO for the analyses should not be reported as being present at the LLO -

level for tha t nuclide. When unusual circumstances resul t in LLD's t-higher than required, the reasons shall be documented in the semi-annual ef fluent report. --

M-? t

g. Sampled during primary to secondary leakage

h. Sampled only when in service g

i 4

SEQUOYAH UdIT 1 3/4 11-12 esse - e ee ema- ..

==am.m-we

I" RADI0 ACTIVE EFFLUENTS DOSE, NOBLE GASES .

LIMITitlG CONDIT10?! FOR OPERATION [,

3.11.2.2 The air dose in unrestricted areas (see Figure 5.1-1) due to E noble gases released in gaseous effluents shall be limited to the following: e

a. During any calendar quarter, to j,5 mrad for gamma radiation and j 10 mrad for beta radiation; l ,

i

b. During any calendar year, to j 10 mrad for gamma radiation and  !..._

j 20 mrad for beta radiation;

• l APPLICABILITY: At all times.

{h dM f#fcN %y(l.I R' ACTION: p\ hN .W

a. With the calculated air dose f om radioactive noble gases in gaseous ef fluents exceeding any of the above limits, prepare and submit to the Commission wit in 30 days, pursuant to Speci-fication 6.9.2, a Special Report which identifies the cause(s) l!

for exceeding the limit (s) and defines the corrective actions to -

be taken to reduce the releases of radioactive noble gases in **u,

} gaseous effluents during the remainder of the current calendar ,

i quarter and during the subsequent three calendar quarters so that

~

the average dose during these four calendar quar.ters is within --

(10) mrad for gamma radiation and' (20) mrad for beta radiation.

, '-l

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

, ~ . .

SURVEILLAtlCE REOUIREMENTS 4.11.2.2.1 Dose Calculations Cumulative dose contributions for the total time period shall be determined in accordance with the Of fsite Dose Calculation Manual (CDCM) at least once every 31 days. - -

4.11.2.2.2 Repc.-ts The semiannual Radioactive Ef fluent Release Reprot j shall include the information specified in Specification 6.9.1.9.

• These doses are per reactor SEQUOYAH UNrr 1 3/4 11-13 7 d

)

,g- -._

.. k: , . ; ,b * + :sl,, ' .Y_. , u~. . . r ?.- _ s ,,* , . . ,q%* .;< <,q,fe.[ z 'k.C '.l.' h ? "'* -

_m,J[f sl.9 Q*{ ,

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lh ,

RADIDACTIVE EFFLUENTS

- DOSE, RAD 1010 DINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOULE GASES s

LIMITING CONDITION FOR OPERATION

.9 WI 3.11.2.3 The dose to an individual from radioiodines, radioactive materials in particulate fom, and radionuclides (other than noble gaseth with half-lives greater than 8 days in gaseous effluents released to unrestricted areas (see Figure 5.1-1) shall be limited to the following:

a. During any calendar quarter to j 7.5 mrem to any organ;

• I l  ;

'b.

During any calendar year to f 15 mrem to any organ; and * .

l l APPLICABILITY: At all times. F y of"U i.n.l

( ,,M .

ACTION: \n Y' W{ '

{Ef(t l a.

With the calculated dose from the release of radioiodines, Q.g

! radioactive materials in particulate fom, o other than noble gases in gaseous effluents (c radionuclides xceeding any of the above limits, prepare and submit to the ommission with-in 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 j

releases of radioiodines, radioactive material,s in particu- . _.

late fom, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents during the  %.

f' I remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose or ~

dose commitment to an individual from such releases during f these four calendar quarters is within (15) mrem to any organ, y

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

applicable. i SURVEILLANCE REQUIREMENTS 4.11.2.3.1 Dose Calculations Cumulative dose contrinuucr.: for the tota' time period shall be detemined in accordance with the ODCM at least once every 31 days. " ' '

t..

4.11.2.3.2 shall include Reports The semiannual Radioactive Ef fluent Release Report . l.

the infomation specified in Specification 6.9.1.9.

• These doses are per reactor fiTO SEQUOYAH UNIT 1 3/4 11-14 g ,,, ,, ,, ,, , .~.... m. ,p ,

. 7, .e,v ' q.

, -n 's . . .h .. Q ..;ed.Qg@id,h.'i

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RADI0 ACTIVE EFFLUENTS GASE0l' R RADWASTE TREATMENT

,L LIMITING CONDITION FOR OPERATION l'yp[b -c ui gd ..h .> y4,.m agr.y+ ate. bowprem ob -tM. ,)

,3.11.2.4 TheAgaseous radwaste treatment, syjtem and the ventilation exhaust

treatment system shall be OPERABLE. Thq/ gaseous radwaste treatment system shall be used to reduce radioactive materials in gaseous waste prior to

. their dischargi when the projected gaseous effluent air doses due to gaseous

! effluent releases to unrestricted areas (see Figure 5.1-1) when averaged

over 31 days would exceed 0.2 mrad for gamma radiation and 0.4 mrad for

' beta radiation and ventilation exhaust treatment system shall be used to '

'.. reduce radioactive materials in gaseous waste prior to their discharge when t the projected doses due to gaseous effluent releases to unrestricted areas l

. (see Figure 5.1-1) when averaged over 31 days would exceed 0.3 mrem to any '

[ organ. $.  ;

hAPPLICABILITY: At all times.

1. h N ['-b

(,N . f- cu~j p

, ACTION: , '

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a. With gaseous waste being discharged for more than 31 days without -

treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2,  :

a Special Peport which includes the following infonnation i

1. Identification' of equipment of subsystems not OPERABLE and the reason for inoperability. l.

l

2. f

' Action (s) taken to restore the inoperable equipment to  !

OPERABLE STATUS. '

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

' l currence.

j b. The provisions of Specification 3.0.3 and 3.0.4 are not '

I appl icabl e. i -

l lSURVEILLANCEREQUIREMENTS  !

i  !

l4.11.2.4.1 Doses due to gaseous releases to unrestricted areas s;.all be l projected at 1 cas,t-once-per-31= days. d h%c -^ c-( u w M e '

wl 6x l'4.11.2.k'2fhe appropriate 3. ll. 2.1 c~ J J. ll. L L systems shall be demonstrated OPERABLE at leastl once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.

K Tim cDmo nu!., y N c6" M*

der 3/4 11-15 Sc: GOOYAtt urh T 1

RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION - '

( w ., -

3.11.2.5 The dose or dose commitment to a real individual fecm all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except the thyroid, which is limited to < 75 mrem) over a -

period of 12 consecutive months?

g APPLICABILITY: At all times. , jd d / b*'

.p'fA sq Q &

in \ ,

ACTION:

a. With the calculated dose from the release of radioactive ..#

materials in liquid or gaseous effluents exceeding twice the limi ts of Speci fica tions 3.11.1.2.a . 3.11.1.2.b , 3.11.2. 2.a 3.11.2.2.b, 3.11.2.3.a , or 3.11.2.3.b, prepare and submi t a (./ v Special Report to the Commission pursuant to Specification 6.9.2 and limit the subsequent releases suqh that the dose or dose i commitment to a real individual from all uranium ft.el cycle I sources is limited to < 25 mrem to the total body or any organ .-

(except thyroid, which is 1imited to < 75 mrem) over 12 consecu-tive months. This Special Report shat 1 include an analysis which g-

"r democstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Othervise, obtair a variance from the Commission to pemit releases which exceeds the 40 CFR Part 190 Standard. .

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable. ' Qy'e SURVEILLANCE REQUIREMENTS * ' '

4.11.2.5.1 Dose Calculations Cumulative dose contributions from liquid n and gaseous ef fluents shall be determined in accordance with Specifi- ---

ca ti o ns 3.11.1. 2. a , 3.11.1. 2.b , 3.11. 2. 2.a , 3.11. 2. 2. b , 3.11. 2. 3. a . a nd 11.2.3.b, " ' " -^ " ~ ^ ' ' ' ' ' " " ' " ' - ~ ' ' "

4.11.2.5.2 Reports Special Reports shall be submitted as required under Speci fication 3.11.2.5.a. '

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3/4 11-16 M" '

SEQUDYAll UNIT 1 l

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g RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE

{

LY LIMITING CONDITION FOR OPERATION

. C.9 3.11.2.6 The concentration of hydrogen and/or oxygen in the waste gas 7,*.y ** holdup system shall be limited to j 2% by volume.

APPLICABILITY: At all times.

. ACTION:

- - , . , a. With the concentration of hydrcgen and/or oxygen in the waste p/- gas holdup system > 2% by volume but j 4% by volume, restore the concentration of hydrogen and/or oxygen to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

• q.s.

b. With the concentration of hydrogen and/or oxygen in the waste

. gas holdup system > 4% by volume, immediately suspend all

• ?i *; additions of waste gases to the system and reduce the concentra-

.- tion of hydrogen and/or oxygen to j 2% within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />,

c. The provisions of Specification 3.0.3 and 3.0.4 are not appl icabl e.

SURVEILLANCE RE0VIREMENTS -

4.11.2.6 The concentrations of hydrogen and/or oxygen in the waste D... - . ; gas holdup system shall be determined to be within the above limits

-j by monitoring the addition of waste gases to the Waste Gas Deca Tank

. with the hydrogen and/or oxygen monitor required OPERABLE by Ta le 3.3-13 of Specification 3.3.3.10.

Jh m

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$M SEQUOYA!! UNIT 1 3/4 11-17

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RADI0 ACTIVE EFFLUEt4TS GAS 5 D / Z TAtlKS

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LIMITING C0tiDIT10N FOR OPERATION /

3.11.2.7 The quantity of radioactivity contained in each gas sw tank shall be limited to <- curies noble gases (considered as Xe-133).

~

APPLICABILITY: At all times 80,006)

ACTICH:

a. With the quantity of radioactive material in any gas decay j tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> either reduce the tank contents to within the limit or provide prompt notification to the Commission pursuant to Speci fication 6.9.1.12. The written followup report shall include a description of activities planned and/or taken to i reduce the tank contents to within the above limit.

I

{

b. The provisions of Specifications 3.0.3 and 3.0.4 are not appl icabl e.

k9 r j.

,SbRVEILLAtlCE REQUIREMENTS I4.11.2. 7 The quantity of radioactive material contained in eacn gas

! decay tank shall be determined to be within the above limit at least } ~

.once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the I jtank. ,

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1 SEQUOYAll UNIT 1 3/4 11-18 .

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'. , 3/4.12.1 10tilTORIrlG PROGRAF t LIri!TitlG C0tlDIT10tl FOR OPERAT10tl .

1. 3.12.,1 The radiological environmental monitoring program shall be con-ducted as specified in Tov.u :J. ,. +

The occ.m -

APPLICABILITY: At all times.

I ACTI0ti: I s / _ _ _ . .

a. With the radiological environmental monitoring program not being conducted as specified in iss'u ;.4" ;, prepare and submi t to -

h the Commission, in the Annual Radiological Operating Report, a '

description of the reasons for not conducting the program as required and the plans for preventing a recurrence. (Devia tions i are permitted from the required sampling schedule if specimens 1 ,

are unobtainable due to hazardous conditions, sample unava*,1-

, ability, or to malfunction of sampling equipment. If l the latter, every ef fort shall be made to complete correct'.D action prior to the end of the next sampling period.s y

b. With the level of radioactivity in an environmental sanpling -

, medium at one or more of the locations specified in "aL' --

cf exceeding the limits of Table 6.9-2 when avera,,ed over ar.y calendar quarter, prepare and submit to the Commission wi thin 30 days from the end of the affected calendar quarter, a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Table 6.9-2 to be exceeded. This report is not required if k, the measured level of radioactivity was not the resul t of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental

,~.,

Operating Report.

l

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

g

! SURVEILLAtlCE REQUIREMEtlTS n , , .us

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tomct @ s a m t tc M '.c  : . L i , v... u.u 1.- a U : : -h~ .

Fi,;  : 3 !? 1, ' l' :, _ j :. : 3 :rd :"2 'm '"':e" r" ~ '"' l t t o th e m a ii u...u. a v. Tau ca :.12 ; a;.3 .1 1.

.I, 4.12.1 Reports - The resul ts of analyses perfomed on the radio-logical environmental monitoring samples shall be summarized in the Annual Radiological Environmental Operating Report, pursuant to Speci fication 6.9.1.6. i l

3/4 12-1 1 SEQUOYAll UNIT 'l l

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. 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 the loca- 5 tion of the nearest milk animal, the nearest residence und the nearest garden

• of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles. N r

( Fr - 01 ; . . ; d . J u o u o. d; Th.m d " "cp : trj C? "o I !!!, " : . O, th "d "-n

"- m ',' ' cl ;c i d :r ti f, thc l : : ti ; r.; ^, f ;' ' -' .. . J s a "" O' ' jasduna vi 3 CCtC' th?" ECO Op. C [C C ; ,, v d #. ing, i. c a. . l ui[

vc3ctabl o .a euwn vi u.e to c.e teoroi vy n.ul au w. .

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APPLICABILITY: At all times.

ACTION: C 6 those,. \ivte6 tn. -tke ODCM .

a. With a land use census identifying a . location (s) which yields f I

a calculated dose or dose commitment greater than the values currentlyebeing, .u calculated in Specification 4.11.2.3.1, ret-p3r, , n ,4 4 + +n +sc c:- 5 ;; j 3, , , L ,, , g, ; .; , _ . . , _ ,

l S? CC# #i C 2 t# 2" 6 9.2, '

3::#:l IC Crt 'iCi. . u..w5i.gs w..

g-g 1ccat.;r' i add -tQ.5 (ocafe -to -th.ose. h th8 --O O C.M i 3 +<,' -

H a

b.

v.ot M a 3 0 c%.

With a land use census identifying a Tocation(s) which yields

'I a calculated dose or dose commitment (via the some exposure pathway) greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, l, pcra w W -'h-i t *e !": C;. .~v., n.. 20 ';, : , ,, m o_: * *^

4 tan d'ir2ticr. G.3.2, a .,p e u . a . A ,. t . : . . . n .vem...e3 u.e nrw l.esa ti c a 'h, r~ 1-st'  :":b;;jjcdtot, ;dL' p d %g, .,, a, e w rn mnnt q rn-4+7r4r; 7-: p v4+s4- 2n g ;, : cp;;; , J 7. A.,.h The sampling location having the lowest calculated dose or dose "'" #

commitment (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.

e

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

applicable.

', . _{

• SURVEILLANCE REOUIREMENTS 4.12.2.1 The land use census shall be conducted at least once per 12 mo'.ths between the dates of April l and October 1, by door-to-door survey, I s

aerial survey, or by consulting local agricul ture authorities. I 4.12.2.2 Reports - Tha results of the land use census shall be included in the Annual Radiological Environmental Operating Report.

• • A conservatively calculated 15 mrem /yr isodose line will be constructed around the plant and the milk-cow ce sus pJ' p'

• Broad leaf vegetation sampling may be per orme imited at the to.

si te th soundary area. in j the direction sector with the highest D/Q in lieu of the garden census.

3/4 12-14 2 SEQUOYAH UNIT 1 4 _

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• RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITI0tl FOR OPERATION . ~ . .

3.12.3 Analyses shall be perfomed on radioactive materials supplied as part of an 1- _ Comparison Program which has been approved by NRC.

Inter lab o ra.-tor V3 APPLICABILITY: At all times.

ACTION:

a. With analyses not beir.g perfomed as required above, report the corrective actions taken to prevent a recurrence to the hp Commission in the Annual Radiological Environmental Operating Report.

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

SURVEILLANCE RE0VIREMENTS

$p 4.12.3 The results of analyses perfomed as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radio-logical Environmental Operating Report pursuant to Specification 6.9.1.6.

. s,:w W.W

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em SEQUOYAH UNIT 1 3/4 12- 9 4

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(

• INSTRUMENTATION ~'

BASES

_ . . ~ . -

3/4.3.3.9 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION

\'

. The raa.0 active liquid effluent instrumentation is provided to t&

monitor and control, as applicable, the releases of radioactive materials ,

' in liquid effluents during actual or potential releases.

setpoints for these instruments shall be calculated in accordance withThe alarm / trip p.WedJW odflahed. in the ODCM to ensure that the alarm / trip will 1 occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY '

and use of this instrumentation is consistent with the requirements  ;

' Part of General

50. Design Criteria 60, 63 and 64 of Appendix A to 10 CFR ,

9

., }

3/4.3.3.10 RADI0 ACTIVE GASE0US EFFLUENT INSTRUMENTATION 3

The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases.

i 'proce#J/h setpoi.nts for thesq instruments shall be calculated in accordance withThe alarm / trip cott.MJ occur prior to exceeding the limits of 10 CFR Part 20.in the ODCM to ensure t ---

tation also i mludes provisions for monitoring the, This instrumen-concentrat holdup s) tem.h.is of potentially explosive gas mixtures in the waste gas { '

The OPERABILITY and use of this instrumentation is con-sistent of wiL.Athe Appendix requirements to 10 CFR Part 50.of General Design Criteria 60, 63 and 64 I -

NM i .

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ry .n, -

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SEQUOYAll UNIT 1 B 3/4 3-4 N u -

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3/4.11 RADI0 ACTIVE EFFLUENTS '

BASES 3/4.11.1 LIOUID EFFLUENTS 3/4.11.1.1 CONCENTRATION l

This specification is provided to ensure that the concentration of

[ radioactive materials released in liquid waste effluents from the site to

! unrestricted areas will be less than the concentration levels specified t in 10 CFR Part 20, Appendix B. Table II. This limitation provides addi- ,

l' tional assurance that the levels of radioactive materials in bodies of. -

[ water outside the site will not result in exposures witnin (1) the h Section II. A design objectives of Appendix I,10 CFR Part 50, to an h.

individual and (2) the limits of 1G CFR Part 20.106(e) to the population.

]The concentration limit for noble gases is based upon the assumption that

'Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP)

Publication 2. ,

. 3/4.11.1.2 DOSE -

g

' y4

This specification is provided to implement the requirements of 9 Sections II. A 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. A 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 liquid effluents will be kept "as low as is -

reasonably achievable". Also, for fresh water sites with drinking water j, supplies which can be potentially affected by plant operations, there is h',]

p reasonable assurance that the operation of the facility will not result Pin radionu;1ide concentrations in the finished drinking water that are T in excess of the requirements of 40 CFR 141. The dose calculations in i 1

lthe ODCM implement the requirements in Section III.A of Appendix I

.-that confomance with the guides of Appendix I is to be shown by cal- a

. culational procedures based on models and data such that the actual .:. . ..

i,' exposure of an individual through appropriate pathways is unlikely -

hto be substantially underestimated. The equations specified in the k!0DCM for calculating the doses due to the actual release rates of Uradioactive materials in liquid effluents will be consistent with the Imethodology provided in Regulatory Guide 1.109, " Calculation of Annual

}qDoses

.of Evaluatingto Man from Routine Compliance Releases with 10 CFR Part 50, of Reactor Appendix Effluents for the Purpose I," Revision t}1, October 1977, and Regulatory Guide 1.113, " Estimating Aquatic Dis- .

Opersion of Effluents from Accidental and Routine Reactor Releases for

' the Purpose of Implementing Appendix I," April 19l7. NUREG-0133 provides j

dmethods for dose calculations consistent with Regulatory Guides 1.109 i@N.

and 1.113. ' ' " '

SEQUOYAH UMT 1 8 3/4 11-1

. ??l[, c . Q W & % ~- M W % R U & . W ? .: 4 : < * .* "' b

.. SW

~

s RADIOACTIVE EFFLUENTS BASES This specification applies to the release of IIquid effluents from m*v each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are prcportioned

[M among the units sharing that system.

3/4.11.1.3 L10UID WASTE TREATMENT The OPERABILITY of the liquid radwaste treatment system ensures that ,

this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirements that the  ;

appropriate portions of this system be used when specified provides assur- -!

ance that the releases of radioactive materials in liquid effluents will .

be kept "as low as is reasonably achievable." This specification imple-ments the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Append v A to 10 CFR Part 50 and design objective Section ll.D of Appendix A .o 10 CFR Part 50.' _The specified limit,s governing the use of appropriate portions of the liquid radwaste treatment system were specl-fled as a su table frtction of the guide set forth in Section ll.A of Appendix 1, 1 FR Part 50, for liquid ef fluents.

3/4.11.1.4 Ll0UID HOLDUP NKS Restricting the quantity of radioactive material contained in the specified tanks provides assurance that the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix A Table 11, Column 2, at the nearest potable water supply and the neares surface water L supply in an unrestricted area. -

3/4.11.2 GASEOUS EFFLUENTS 3 .s.%

N,%

3/4.11.2.1 DOSE RATE -

This specification is provided to ensure that the dose rate at any- '

time at the exclusion area boundary frcrn gaseous af fluents frcm all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with g{. ,,,

the concentrations of 10 CFR Part 20, Appendix B, Table !!. These limits ,

provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an Individual in an unrestricted area, either within or outside the exclusion area boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table il of 10 CFR Part 20 (10 CFR Part 20.106(b)). For Individuals who may at times be within the exclusion area boundary, the ,,.

occupancy of the individual will be sufficiently low to compensate for SEQUOYAH UNIT 1

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. W-%[~7.y . .. **~- ~= .

n'

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RADI0 ACTIVE EFFLUENTS BASES any increase in the ataospheric diffusion factor above that for the ex-clusion area boundary. The specified release rate limits restrict, at g'p,

j. all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to 3 (500) mrem / year to the total body or to < (3000) mrem / year to the skin. These

~

release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to j 1500 mrem / year for the nearest cow to the plant. ,

This specification applies tn the release of all reactors at the site. Fog oMw M 'swogaseous effluents from cadwaste -treatmed '

h;--::

' sptems, -rk yascovs. e9 flue *S from h e- dtued sysiem cWca '

p roprt ooned ko.teg at units sitar % -ekt y te % ,

3/4.11.2.2 DOSE, NOBLE GASES .

This specification is provided to implement the requirements of Sections II.8, 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 1. 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 assure that the releases of radio-active 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 confonn with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate path- _ _ _ _

ways is unlikely to be substantially underestimated. The dose calcul'a- .

tions established in the ODCM for calculating the doses due to the actual f@'f release rates of radioactive noble gases in gaseous effluents will be _

consistent with the methodology provided in Regulatory Guide 1.109, _ ,, ,

" Calculation of Annual Doses to Man from Routine Releases of Reactor Appendix for Effluents I,"

the Purpose of Evaluating Compliance with 10 CFR Part 50, .

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 exclusion area boundary will be based upon the historical average atmos-pheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

3/4.11.2.3 DOSE, RADIOI0 DINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES 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 SEQUOYAH UNIT 1 B-3/4 11-3

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RADI0 ACTIVE EFFLUENTS ,

BASES Conditions for Operation are 'the guides set forth in Section II.C of Appendix 1. The ACTION statements provide the required coerating flexi-  ? @#

bility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effl'uents 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 confom-ance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially under- N estimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials N '

are required to be consistent with the methodology provided in Regulatory Guide 1.109, " Calculating 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 l of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," --

j Revision 1, July 1977. These equations also provide for determining w

t the actual doses based upon the historical average atmospheric conditions. . he

! The release rate specifications for radiofodines, radioactive material lin particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area.

iThe lare: pathways which are examined in the development of these calculations

1) individual inhalation of airborne radionuclides,,2) deposition

.jof radionuclides onto green leafy vegetation with sub" sequent consumption

by man, 3) deposition onto grassy areas where milk animals and meat' -

jproducing animals graze with consumption of the milk and meat by man, FF5 dand 4) deposition on the ground with subsequent exposure.uf man,

. fM W

3/4.11.2.4 GASEOUS WASTE TREATMENT i The OPERABILITY of the gaseous radwsste treatment system and the ventila- ,

i tion exhaust treatment systems ensures that the systems will be available '"-

for use whenever. gaseous effluents require treatment F ior to release to ~.

Y the enviroment. The requirement that the appropriate portions of these hsystems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as dlow as is reasonably achievable." This specification implements the i requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appen- -

dix A to 10 CFR Part 50, and design objective Section IID of Appendix I W .,.

to 10 CFR Part 50. The specified limits governing the use of appropriate -

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

gp l

SEQuoyAH UNIT 1 B 3/4 11-4 I

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RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.5 DOSE  %,S This specification is provided to meet the reporting requirements of 40 CFR 190.

3/4.11.2.6 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas treat-ment system is maintained below the flammability limits of hydrogen W4 and oxygen.  ;

i lSintaining the concentration of hydrogen

and oxygen below their flammability limits provides assurance that j the releases of radioactive materials will be controlled in conformance ~~

'with the requirements of General Design Criterion 60 of Appendix A A l to 10 CFR Part 50.

I

3 /.4.11.2.7

[C>ECAY GAS TANKS 8 l l1 Mricting the quantity of radioactivity contained in each gas tank provides assurance that in the event of an uncontrolled

! release of the tanks contents, the resulting total body exposure to { __ _

~. .

an individual at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard Review Plan 15.7.1, " Waste NT Gas System Failure." .,__ .

F pm . % 9 -

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2 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4 12.1 MONITORING PROGRAM -

The radiological monitoring program required by this specification '

provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation expsures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological ef fluent monitoring program by verifying that the measur- ,.,

able concentrhtions of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and

' modeling of the enviromental exposure pathways. The initially specified monitoring program will be effecti.ve for at least the first three years of commercial operation. Following this period, program changes may be initiated based on' operational experience. .

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l3 /4.12.2 LAND USE CENSUS This specification is provided to ensure that I

t changes in the use of unrestricted areas are identified and that modifi-cations to the monitoring program are made if required by the results of 1

.this census. This census satisfies the requirements of Section IV.B.3 of i

' l Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater

!than 500 square feet provides assurance that significant exposure pathways

' !via leafy vegetables will be identified and monitored since a garden of -

'this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a (Of A3 child. To deterTnine this minimum garden size, the following assumptions were used,1) that 20*. of the garden was used for growing broad leaf '" -

vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation M' .

yield of 2 kg/ square meter. '

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an. Interlaboratory Comparison program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environnmental sample matrices are perfomed as part of a quality assurance program for environmental raonitoring in order' to demonstrate that the results are -

reasonably valid. ,

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SEQUOYAH UNIT 1 B 3/4 12-1 gy>.: -

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6.0 ADMIrlISTRATIVE CONTROLS

• 6.1 RESPONSIBILITY 6.1.1 The Plant Superintendent shall be responsible for overall unit operation and shall delegate in writing the succession to this respon-sibility during his absence.

6.2 ORGANIZATION OFFSITE_

6.2.1 The offsite organization for unit management and technical support shall be as shown on Figure 6.2-1.

UNIT STAFF 6.2.2 The Unit organization shall be as shown on Figure 6.2-2 and:

a. Each on duty shift. shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

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b. At least one licensed Operator shall be in the control room when fuel is in the reactor. .

c. At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

d. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor,

e. All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent respon- -

sibilities during this operation.

f. A Fire Brigade of a) least 5 members shall be maintained onsite at all times' . The Fire Brigade shall not include 3 I members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire e.nergency.

1. Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accomodate unexpected absence of Fire Brigade members provided imediate action p is taken to restore the Fire Brigade to within the minimum requirements.

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i LICErl5E APPLICI,8LE POCES CATEGORY 1, 2, 3 & 4 526

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• Does not include the lice.nsed Senior Reactor Operator or Senior Reactor Operator Limitec to Fuel Handling, supervising CORE h ALTERATIO:IS.

, \d # Shift crew comoosition may be less than the minir.um requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accomr.odate unexpected absence of on duty shif t cre , memcers proviced ir. mediate action is taken to resttre the shift crew composition to within the minimum requirements of Table 6.2-1.

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ACMINIST3AT!'lE CONTr0LS

6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed .the minimum

, qualifications of ANSI N18.1-1971 for c:mparable positions, except for the Health Physicist who shall meet or excaeo the qualifications of Regulatory Guide 1.8, September 1975.

6.4 TRAINING 6.4.1 A retraining and replacement training pregran for the unit staf f

. shall be maintained und:r the direction of the Assistant Plant Sucerintendent and shall meet or exceed the requiremeqts and recce.mendations of Section .

___ 5.5 of ANSI N18. .-1971 and Appendix A" of 10 CFR Part 55.

AF3 6.4.2 A training program fcr the Fire Bridgade shall be maintained under the direction of the Assistant Plant Su erin endent and shall meet or exceed the requirements of Section 27 cf the NFPA Code-1975, excepc for Fire Bridage training sessions which shall be held at least once fg per 92 days.

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'-* ' "' 6.5 REVIEW AND AUDIT

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6.5.0 The 113 nager of Pcwer is responsible for the safe operaticn.cf all

- - TVA power plants. The functiona1 organizacion for Review and Audit is .

shown on Figure 6.2-1. .

! 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (pCRC) l FUNCTION .,

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6.5.1.1 The PORC shall function to advise the Plant Superintendent on

'j7j c all matters related to nuclear safety.

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... CO:',POS I T 103 6.5.1.2 The PORC shall be cceposed of the:

Chairman: Plant Superintendent '

lteber: Opera tions Supervisor

• • • ltember: Results Supervisor-

llember: -

1tember:

" Maintenance Sucervisor Itember: - Assistant Plant Su:erintendent Member:

Quality Assurance Staff Supervisor .

Health Physicist ALTER:ATES

• 6.5.1.3

[ -- - All alternate members shall be ac;cinted in writing by the FORC Chairman to serve on a temporary basis; ho,;ever, no more than two alternates 3.lall participate as voting members in FORC activities at any one time.

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_ O, / I'EETiliG FRE00E!!CY 6.5.1.4 Tne FORC shall meet at least once per c'alendar ocnth and as convened by the PORC Chairman or his designated alternate. -

OUORU:t -

'I 6.5.1.5 The minimum quorum of the PORC necessary for the performance of l

• • the PORC resconsibility and authority provisions of these technical specifications shall ccnsist of the Chairman or his designated alternate and four members including alternates.

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RESP 0llS IB IL ITIES

'. 6.5.1.6

, The PORC shall be responsible for:

a.

Review of 1) all procedures required by Specification 6.8 and

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changes thereto. 2) any other proposed procedures or changes

.d' thereto as determined by the Plant Superintendent to affect nuclear safety.

l' b.

Review of all proposed tests and experiments that affect nuclear safety. *

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• SEQUOYAH-Dilli 1

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c. Review of all proposed changes to Appendix "A" Technical Specificaticns.

d.

Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.

e.

Investigation of all violations of the Technical Specifica-tions including the preparation and forwarding of reports covering evaluation and reccmmendations to prevent recurrence to the Chief, fluclear Generation Brancn and to the Chairman of the Nuclear Safety Review Board.~

f.

Review all written reports requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to tne Ccmmission.

g.

Review hazards, of unit operations to detect potential nuclear safety b.

Performance of special reviews, investigations or analyses and reports thereon as requested by the Plant Superintendent or the Nuclear Safety Review Board.

i.

Review of the Plant Physical Security Plan and implementing procedures 3nd shall submit recommenced Changes to the fluClear Safety Review Board.

j.

Review of the Site Radiological Emergency Pian and implementing procedures and shall submit recommended changes to tne Nuclear Safety Review Board.

k.

Review of every unplanned release of radioactive material to the environs; evaluate the event; specify remedial action to prevent recu,rrence; and document the event description, evaluation, and corrective action and the disposition of the corrective action in the plant records.

AUTHORITY 6.5.1.7 The PORC shall: '

a.

Recommend in writing to the Plant Superintendent approval or disapproval above. of items considered under 6.5.1.6(a) through (d) b.

Render deterninations in writing with regard to whether or not eacn item considered under 6.5.1.6(3) thrcugn (e) above constitutes an unreviewed safety question.

SEQUOYAH-UNIT 1 6-7 u -

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' cf disagreercent however, bett.een th2 PORC and the Plant Superintenden the Plant Supzrintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above .

.. RECOROS 6.5.1.8 The PORC shall maintain written minutes of each PORC meeting that, at a minimum, document the results of all PORC activities performed under the ressor.,ibility and authority provisions of these technical specifications.

Copies shall be prov.ided to the Chief, Nuclear Generation .

Branch and the Nuclear Safety Review Board. ,

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'. 6.5.2 NUCLEAR SAFETY RE7tE'.I ECARD (USR3)

_F_L NC T I CN 6.. 2.1 The HSP.3 shall function to provide independent review 'and audit

, of designated activities in the areas of:

, a. nuclear power plant operations ,. .

b. nuclear engineering

c. chemistry and radicchemistry

d. metallurgy

e. instrumentation and control ,

.[- ,4 f. radiological Jafety

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9 mechanical and electrical engineering

h. quality assurance practices

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{,. ,tlMINISTRAT I'.'C CCHIROLS

{ . .' COMPOSITION 6.5.2.2 The chairnan, members and alternate nenbers of the NSRB shall be annointed in triting hv the Manager of Power and shall have an academic degree in an engineering or physical science field, or the enuivalent; and in addition, shall have a minimum of five years technical experience, of which a minimum of three years shall be in one

.. or more areas given in 6.5.2.1.

1 ." .'.

6.5.2.3 The NSRB shall be composed of at least five members, including the Chairman. Members of the NSRB may be from the Office of Power,

',,, f rom other of fices or divisions within TVA, or f rom external to the

_ , , , TVA.

2g'gg) CC"5ULTAMTS .

6.5.2.4 Consultants shall be utilized as determined by the fl5R3 Chairman to provide expert advice to the tiSRB.

HEETIf!G FRECUE?;CY '

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~~~T"5 6.5.2.5 The !! SRB sha'.1 meet at least once per calendar quarter during

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- - - the initial year of unit' operation follouing fuel loading and at least once per six months thereafter. .

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6.5.2.6 The minimum nuorum of the MSRB necessary for the performance of the NSRB review and audit functions of these technical specifications shall consist of members, or alternates, and the Chairman, or his E desinnated alternate in total number to be at leant 4.

gEWE!PERN No more than two al ternates shall participate as voting members in-NSRB activities at any one tine. No more than a ninority -

of the quorun shall have line resposibility for operation of the Sequoyah Nuclear Plant.

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6.5.2.7 The NSRB shais review:

a.

'; The sa fety evalua tions for 1) changes to procedures , equipm or systems provision of and 2) tests Section 50.59,or exoeriments 10 ccnaleted under the

~' did not constitute an unreviewed safety question.CFR, to verify t b.

Proposed changes to procedures, equipmen 50.59, 10 CFR.

c.

j safety question as defined in50.59, SectionProposed 10 CFR.

tests o

[* d.

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• Proposed License. changes to Technical Specifications or this Opera 1

e.

Violations of ccdes, regulations, erhers, Technical Specifi-cations, license requirements, or of internal procc3 ares or instructicas having nuclear safety significance.

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,"% Significant ooerating abnormalities or deviations from normal and safety.expected performance of unit equipment that affect nuclear

g. .

All written Ccamission. resorts requ. iring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the i

i-h.

, Ali recognized indications of an unanticipated deficiency in scme aspect of design or operation of structures, systems, or components that could affect nuclear safety.

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Reports and meetings minutes of the PORC.

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, AUDITS 6.5.2.8 of the USRb. Audits of unit activities shall be These audits shall enccmpc s:

erformed under tn e cognizance

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a.

t The conformance of unit operation to provisions ned contai conditions at least once per 12 months.within e tne Tec b.

unit staff at least o..ce per 12 months.The re perform c.

The results of actions taken to correct urring defic

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that affect nuclear safety at least once per 6 months

d. .

i The performance of activities required by the nal Operatic Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months .

s e.

at least once per 24 months.The Site Radiological procedures Emerg f.

at least once per 24 months.The Plantocedures Physical Security g.

NSRB or the Manager of Power.Any other

• e by area tne of unit op

h. .

dures at least once per 24 months.Theproce- Facility Fire Pro i.

An independent fire protection anc loss prevention rogram p inspection and audit shall be performed annually utilizing either cualified protection firm. offsite licensee personnel or an outside fire j.

An inspection and audit of the firereven- protection a

_ ,1 consultant at , intervals

- . . . . no greater than 3 years.

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k. _..

Thr rmliological envirnmental rioni toring prograi and the <

resul ts thereof at least once per 12 months.

l 1.

The ciTsITE 00sE C AI. Cut A T 10H 11ANUAL and ....plementing procedures at least once per 24 months.

l AUTHORITY 6.5.2.9 The fl$RS shall report to and advise the Manager of Power on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

SEQUOYAH-UNIT 1 6-11 AUG 1 S EU

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.j RECC?DS

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6.5.2.10 distributed as indicated belcw: Records of NSR3 activities shall be prepare i

a.

Itinutes of 'each NSRB meeting shall be prepared, approved and forwarded

'each meeting. to the Manager of Power within 14 days following l4 ,

b.

Reports of reviews enccmpassed by Secticn 6.5.2.7 above, shall

'l be prepared, accroved and forward 3d to the Manacer of Power Y

within 14 days folicwing completion of the review.

c.

. Audit reports enccmaassed by Secticn 6.5.2.8 above shall be '

.3'*-

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forwarded to the Man 3ger of Pc..er and to the manageTent positions after res;onsible ccepletion foraudit.

of the the areas audited within 30 days 6.6 REPORTABLE OCCURRE::CE ACTIC: 1 Q 6.6.1 The folkwing acticns shall be taken for REPORTABLE OCCURRENCES:

. .ht

c. -

a.

The tommissicn shall be notified and/or a re;crt submitted l

pursuant to the require,ments of Spacification 6.9.

b.

i Each REPORTAELE JCCURREtiCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Cormission snall be revieued by the PCRC and submitted to i the NSRB and the Chief, fluclear Generation Branch.

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6.7 SAFETY LIMIT v!OLATION -

6.7.1 The following actions shall be taken in the event a 5afety Limit is violated:

l

a. The unit shall be placed in at least HOI STANDBY within one hour.

l

b. The Safety Limit violation shall be reported to the Connis-i i sion, the Chief, Nuclear Generation Branch and to the NSRB within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. A Safety Limit Violation Report shall be prepared. The report ,

snall be reviewed by the PORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects -

of the violation upon facility cciconents, systems or struc-tures, and (3) corrective action taken to prevent recurrence.

d. The Safety Limit Violation Repor; shall be sule,itted to the Ccmmission, the NSRG and the Chief, Nu~ clear Generation Branch within 14 days of the violation.

6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below:

O

a. The applicable procedures reconmended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.

b. Refueling operations. '

c. Surveillance and test activities of safety related equignent.

d. Plart Physical Security Plan implementation.

e. Site Radiological Energency Plan implementation.

f. F, ire Protection Progtam impic.aentation.

3 The radiological environmental monitoring program.

h, OFFSITE DOSE CALCULATION MANUAL implementa tion.

6.8.2 Ear.h procedure of 6.3.1 3bove, and changes thereto, shall be reviewed by the PORC and approved by the Flant Superintendent prior to inplc: rent ticn 3r.c revicwed ;cricdicall., as sat Tort'i iii as.iin b tra tive procedures.

SEGUOYAH-UNIT 1 6-13

O ADMINISTRATIVE CONTROLS -

6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a. The intent of the original procedure is not altered.-

b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected,

c. The change is documented, reviewed by the PORC and approved by the Plant Superintendent within 14 days of implementation.

6.9 REPORTING REQUIREMENTS

• ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to,the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to j' the Director of the Regional Office of Inspection and Enforcement unless-otherwise noted.

O STARTUP REPORT -

6.9.1.1 A summary report of plant startyp and power escalation testing shall be submitted following (1) receipt of an operating license (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that. may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of -

the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other comitments shall be included in this report.

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ADMIllISTRATIVE C?lTROLS -

6. 9.1. 3 Startup reports shall De submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or comencement of comercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or comencement of comercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

Aflf4UAL REPORTSO 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial. report-shall be submitted prior to March 1 of the year following initial' criticality.

6. 9.1. 5 Reports required on an annual basis shall include a tabulation on an annual basis for the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr a O

theirassociatedmanremexposureaccordingtoworkandjobfunctions,g e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste F. processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or filnr badge measure-ments. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions, y A single submittal may be made for a multiple unit station. The -

submittal should combine those sections that are common to all units at the station.

2] This tabulation supplements the requirements of 520.407 of 10 CFR Part 20.

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M INISTRATIVE C0liUOLS 6.9.1.6 On an annual basis, a report shall be submitted which will include an assessment of offsite radiation doses from the radioactive liquid and gaseous effluents released from the unit during the previous year. Doses to be evaluated shall include, for effluents to the atmosphere: Noble gases- gamma air, beta air, total body, and skin; Iodines and Particulates- maximum organ. Population deses (total body and thyroid) within 80 km (50 miles) shall also be calculated. Meteor-ological conditions for the period shall be used for determining the doses due to gaseous effluents and a summary of the meteorology shall be included. Reported doses due to liquid effluents shall include total body, skin, and maximum organ. Population doses (total body, skin,and maximum organ) frcm the plant to the mouth of the Tennessee River shall also be calculated. River flow conditions for the same period shall be used in determining individual and population doses. An assessment of onsite radiation doses from direct radiation and gaseous effluents shall also be included in this report. This report shall be transmitted with the Semiannual Radioactive Effluent Release Report for the second half of the year. __

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT U 6.9.1.7 Routine radiological environmental operating reports covering the operation of the. unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.

6.9.'.8 l The annual radiological environmental operating report shall include summaries, interpretations, and evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparisen with preoperational studies, operational controls (as appropriate),

and/or previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the land use censuses required by Specification 3.12.2. If harmful effects or evidence of irreversible damage are detected by .

the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Table 6.9-1 of all radiological envir-onmental samples taken during the report period. In the event that same results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The report shall also include the following: a summary description of the radiological environmental monitoring program including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used, and maps and tables of appropriate sampling stations giving their location relative to the site; the results of land use censuses required by Specification 3.12.2; SLQUoyAll UNIT 1 6-16

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ALMINISTRATIVE CONTROLS and the results of licensee participation in Quality Assurance Prograa required by Specification 3.12.3.

SE'!IANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1!

6.9.1.9 Routine radioactive ef fluent release reports covering the operating of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality.

6.9.1.10 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid And Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B thereof.

The radioactive ef fluent release reports shall include the following information for all unplanned releases to unrestricted areas of ram active materials in gaseous and liquid effluents:

a. A description of the event and equipment involved.

b. Cause(s) for the unplanned release.

c. Actions taken to prevent recurrence.

d. Consequences of the unplanned release.

3/

-- A single submittal may be made for a cultiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify releases of radioactive material from each unit.

SLycoyAU UNIT 1 g,gg

A0111HISTR ATIVE CONTROLS I1ONTHLY REACTOR OPERATING REPORT 6.9.1.f3 Routine reports of operating statistics and shutdown experience '

shall be submitted on a ncnthly basis to the Director, Of fice of Panage-ment and Program Analysi s, U.S. Nuclear Regui d tory Cormission, Wa shington, D.C. 20555, with a copy to the Regional Of fice of Inspection and Enforce-ment, no later than the 15th of each month following the calendar month covered by the report. In addition, any changes to the Of fsite Dose Cal-culational fianual of Specification 6.13 shall be submitted with the lionthly Operating Report wi thin 90 days from which the change (s) was made.

e f fec tiv e. ,

REPORTABLE OCCURREUCES 82- i+ 13 6.9.1.9 T.he REPORTABLE CCCURRENCES of Specification 6.9.l.tE and 6.9.1.53 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplenental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplcaental reports, a licensee event report shall be com-

, pleted and reference shall be made to the original report date.

PR0l*PT NOTIFICATION WITH WRITTEH FOLLOWUP t3 O 6. 9.1. S The types of events listed below shall be reported within 24 g hours by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Of fice, or his designate no later than the first working' day following the event, wi th a written followup report wi thin 14 days. The written followup report shall in-clude, as a minimun a conoleted copy of a license event report form.

W.'s Infomation provided on 'he license'e event report fom shall be supple-mented, as needed, by addi:i:nal narrative naterial to provide complete explanation of the circumstances surrounding the event.

. . . . a. Failure of the reactor protection systen or other systems,

---iy subject to limiting safety system settings to initiate the recuired protective function by the tine a monitored para-meter reaches the setpoint specified as the limiting safety system se tting in the ' technical speci fications or failure -

to complete the required protective function.

b. Operation of the unit or affected systens when any carameter or operation subject to a limiting condition for operation is less conservati"e than the least conservative aspect of the limiting condition for operation established in the technical specifications.

c. Abnomal degrada tion discovered in fuel cladding. reactor coolant pressure boundary, or primary containment.

O p e SEQuoYAH UNIT 1 6-19

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! d. Reactivity ancmalies involving disagreement with the predicted i value of reactivity balance under stcac/ state cor.diticr.s

' during scwer cperation. greater inan or equal to 11 sk/k; a calculated reactivity balance indicating a ShUTCO'/3 MARGIN Iess conservative than specified in the technical scecifica-Ij - tions; short-term "eactivity increases that corresacnd to a reactor ; cried of less tnan 5 seccnds cr. if subtritical, an unpianned reactivity insertier, of eare than 0.5% ak/h. or occurrence of any unplanned criticality.

e. Failure or malfunctior. of one er more ccmponents which prevents or could prevent, by itself, the fulfillment of the functional

' requirements of system (s) used to ccpe with accidents analyzed in the SAR.

f. Persennel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functicnal re;utre-ments of systems required to cope.with accidents analyzed in the SAR.

g. Conditions arising frem natural or ran-made events that, as a direct result of the event require unit shutdown, cceration

of safety systems, or other protective measures required by technical specifications.

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/**\ h. Errors discovered in the transient er accident analyses or in the methods used for such analyses as described in the safety analysis report er in the bcses for the technical specificaticns that have or could have permitted reacter 0;= ration in a manner less conservative than assumed in the analyses.

i. Performance of s*ructures, systems, or components that requires remedial action or cnrrective measures to prevent cceration in a manner less conservative than assumeo in the accident

- analyses in the safety analysis report er technical scecifica-tions bases; or discovery during unit life of conditions not specificall;, considered in the safety analysis report or

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technical specifications that require re,edici action or cor-I rective measures to prevent the existerce or development of an

. unsafe condition. .

j. Occurrence of an unusual or imcortant event that causes a significant environmental imoact, that affects potent'al environmental imoact frcm unit operation, or that has high public rr catcntial public interest concerning environmental impa.:t frca uni t opera tion.

. , _ , k. Occurrence of radicactive material contained in liquid or gaseous holdup tanks in excess of that permitted by the limiting condi-tion for operation established in the technical specifications.

/ 6-20 SEQUOYAll UNIT l

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A::C1iSTR .T V!E r3 30. S .

D lI Th!RTY DAY WRITTE.*l cEFCRT5 l'f

6. 9.1. -d The types nf even s listed below shall be tne subject of l

written re;:

days of occurrence orts to the Director of the event. of the Regional Office within thirty mir.im u m, a completed copy of a licer.see event re;;;rt for i.The written re:: ort shall ii prJviced Cn the licensee event report form shall be su;;plemented, Infornation as eeced, by additional narrative material to provice ccmplete explcnation of the circumstances surrounding the event.

a.

,'i Reactor prot.ction system er engineersd safety feature instru-ment settings wnicn are fou1d to be less conservative than those established .ty the technical specifications but which do not prevent tne fulfillment of the functional requirements of

! affected systems.

b.

Conditions leading to opera: ion in a degraded mode ::crmitted by a limiting condition for opera tion er plant shutdown re-qaired by a limiting condition for operation.

c.

Observed inadecuacies in the implementation of administrative or procedural controls which threaten ta cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.

O d.

Abnornal degradatien of systems other than those specified O in 6.9.1.Yd.c above designed to contain radioactive material resulting#ren the fission process.

I3

• e.

An unplanned offsite release of 1) r cre than I curie of radicoctive material in licuid ef fluents. 2) more than 150 curies of ncble gas in gaseous effluents, or 3) more than 0.05 curies o radioicdine in gasecus effluents. The report of an unplann.:c )f fsite release of radioactive material sh: 1 include the following infomation:

1. A desc- ption of the event and equipment involved.

2. Cause(s) for the unplanned release.

3.. Actions taken to prevent recurrence. -

4 Ccnsequerces of the une'anned release.

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6-21 SEQUOYAH UNIT 1 O

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D' ACMl?tISTRAi!VE C0 lit 7CLS -

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"easured levels of radioactivity in an enviror.nen*al scroling medium determined to e.tceed the reocrtina level values of Table 6.9-2 wnen averaged over any calendar cuarter semcling period. When more than one of the radionuclid:. in Table 6.9-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) ' concentration (2) limit level (1) limit level (2)

+

... 1 1.0 When radionuclides other than those in Table 6.9-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifica-tions 3.11.1 2, 3.11. 2. 2 and 3.11. 2. 3.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

v SPECIAL REPORTS O

r 6.9.2 Special reports shall be sutnitted to the Director of the Office of Inspection and Enforcement Regional Office within tne time period

.specified for each report.

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TABLC 6.9-2

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$ REPORTitiG LEVELS FOR RADIDACTIVITY C0]lCEtiTRATIO.'iS Ili Eti'!IR0tiMEtiTAL 4 .

, 4 ,

Reporting Levels Water Airborne Particulate- Fish f Analysis Milk Vegetables (DCi/!) or Gases (pC1/.T.3) (pct /Kg, wet) (pC1/l) 5- 1 (pCi/Kg, wet)

! 1(- 3 3 x 10 4

• Mn-54 1 x 10 3 3 x 10 4 Fe-59 4 x 10 2 1 x 10 4

3 Co-58 1 x 10 4 3 x 10

? Co-60 3 x 10 2 -

4 0 1 x 10 Zn-65 ..3 x 10 2 2 x 10 4

/r-t;b-95 4 x 10 2 I-131 /5 0.9 1x 10 2 3

Cs-134 30 , 10 1 x 10 3 60 1 x 10 3

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

P.a-La-140 2 x 10 2 3 x 10 t

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<s i I6.10 PE GP.0 RETEMHON

n accition to the acolicabie record retention recuire,ents of Ti tle 10, J, Ccde of Fede-al Regula ticns, the following records snall oe retained for

,; at leas the minimum periot indication. ,

1 l 6.10.1 Tne folicwing recorcs shall be retained for at least five years:

b a. Records and logs of unit operation c:vering time interval at each power level .

. b. Records and logs of principal maintenance activities, inspec-tions, repair and replacement or principal items of ecuipment i

il related to nuclear sa fe ty. ,

l

c. ALL REPORTABLE OCCURRENCES submitted to the Ccamission.

.. d. RecCrds of surveillance activities, inspections and cali

• I brations required by these Technical Specifications.

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e. Records of changes made to the procedures required by Speci fica tion 6.8.1. .

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f. Records of radioactive shipments. .

O g.

Records of licensable sealed source and fission detector leak tests and results.

h. Records of annual physical inventcry of all licensable sealed source material of record. ~

6.10.2. The following records shall be retained for the duration of the Unit Operating License:

a. Records and drawing changes reflec ting unit design modi fica-tions made to sy, stems and equipment described in the Final Sa fe ty Analysi s Report.

b. Records of new and irradia ted fuel inventory, fuel transfers and assembly burnup histories.

c. -.

Recceds of radia tion exposure for all individuals entering radia tion control areas.

d. Records of gaseous and liquid radioactive material released to the environs. .

I 6-24 Q)"%

N' SEQUOYAll UNIT 1 e

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, c. Records of radiation exposure for all individuals entering radiation control areas.

d. Records of gaseous and liquid radioactive material released to the environs.

e. Records of transient or operational cycles for those unit components identified in Tat 5.7-1.

f. Records of reactor tests and experiments. '

. g. Records of training and qualification for current members of the unit staff.

s-

h. Records of in-service inspections performed pursuant to these Technical Specifications.

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Records of Quality Assurance activities required by the Opera-f.g .

tional Quality Assurance Manual.

J. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

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k. Records of meetings of the PORC and the NSRB.

. yg; 6.11 RADIATION PROTECTION PROGRAM 3<

q Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all cperations invciving personnel radiation exposure.

6.12 HIGH RADIATION AREA i

6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2) of 10 CFR 20, eacn high radiaticn area in which Uhl) the intensity of radiation is greater than 100 mrem /hr but less than "trr-1000 mren/hr shall be barricaded and conspicuously posted as a hign radia-tion area and entrance thereto shall be controlled by requiring issuance of a Special Work Permit *, Any individual or group of individuals permitted to enter such areas shall be provided with or acccmpanied by one or more of the following:

• Health Physics personnel or personnel escorted by Health Dhysics

,.hhd personne in octoraance witn approved emergency procedures , shall be exenot from the SWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radia-

,s tion areas.

SEQUOYAH - UNIT 1 6-25 1

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a. A radiation monitoring device which continuously indicates the radiation dose rate in the area,

b. A radiation monitoring device with continuously integrates the radiation dose rate in the area and alarms when a preset inte-grated dose is received. Entry into such areas with this I monitoring device may be made after the dose rate level in the I;iF -

area has been established and personnel have been made know- $4Nhv ledgeable of them. L

c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.

This individual shall be responsible for providing positive control over the activities within the area and shall perform control over the activities within*the area and shall cerform ( '- ~

periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Special Work Permi t. [h:fip 6.12.2 The requirements of 6.12.1, above, shall also acoly to each high radiation area in which the intensity o.f radiation is greater than 1000 mrem /hr. In addition, locked doors shall be provided to prevent unauthor-ized entry into such areas and the keys shall be maintained under the

/"S administrative control of the Shif t Engineer on duty and/or the Health Physicist. , , , , .

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O' ADMINISTR AT I'.'E CONTROL S 6.13 0FFSITE DOSE CALCULATICH MAUUAL (OCCM)

FUNCTION

6. 13 . 1 The OCCM shall describe the nethodology and parameters to be used in the calculation of of fsite doses due to radioactive gaseous and liouid effluents and in the calculation of gaseous and liquid effluent monitoring

.gg,,.

instrumentation alarm / trip setpoints consistent with the applicable LC0's contained in these Technical Specifications. Methodologies and calcula-tional procedures acceptable to the Commission are contained in HUREG-0133.

Tt shall cT"o centnin a flow diagram of the liquid and gaseous radwaste treatment systems and a description of the radiological enviror. mental monitoring program. .

The ODCM shall be submitted to the Comnission at the time of proposed Radio-logical Ef fluent Technical Specifications and shall be subject to review and approval by the Commission prior to implenentation.

6.13.2 Any changes to the ODCM shall be made by either of the following methods:

, A. Licensee initiated changes:

1. Shall be submitted to the Commission by inclusion in the Monthly Operating Report pursuant to Specification 6.9.1.10 within 90 days of the date the change (s) was made ef fective and shall contain:

a. suf ficiently ~ detailed informa tion to totally support the

1. ?J; rationale for the change wi thout benefit of additional or suppl emental i n fo rma ti o n. In fo rma tion sub.mi tted should consist of a package of those pages of the ODCM to be chang. d with each page numbered and provided with an t:96 approvai and date box, together wi th appropriate analyses or evaluations justifying the change (s);

. b. a determination that the chance will not reduce the -

accuracy or reliability of do'se calculations or setpoint determinations; and

c. documentation of the fact that the change has been '

reviewed and found acceptable by both the PORC and NSRB.

2. Shall become ef fective upon a date specified and agreed to by both the PORC and the NSRB following their review and acceptance of the change (s).

(*)'

' -l 6 27 SEQUOYAll UNIT 1

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A0!11tilSTRATIVE CCflTROLS I

B. Commission initiated changes:

1. Shall be detemined by the PORC to be applicable to the .

facility af ter consideration of facility design.

2. The licensee shall provide the Commission with written noti-

, fication of their detemination of applicability including any necessary revisions to reflect facility design.

3. Shall be reviewed by the NSRB at its next regularly scheduled meeting.

6.14 itAJOR CilAtlGES TO RA010 ACTIVE 'n'ASTE TREAIMEflT SYSTEf45 (Liquid and Gaseous)

FullCT 10?!

6.14.1 The radioactive waste treatment systems (liquid and gaseous) are those systems described in the facility Final Sa fety Analysis- Report or llazards Summary Report, and amendments thereto, which are used to p maintain that control over radioactive materials in gaseous and licuid effluents required to meet the LCO's set forth in Specifications 3.11.1.1, 5.11.1.2, 0.11.1.3, 3.11.1.4, 3.11.2.1, 3.11.2.2, 3.11.2.3, 3.11.2.4, 3.11.2.5, and 3.11.2.7.

6.14.2 liajor changes to the radioactive waste systems (liquid and gaseous) shall be nade by either 'of the following' methods. ror the a purpose of this specification ' major changes' is defined in Specifica-tion 6.14.3 below.

A. Licensee initiated changes:

1) The Ccemission shall be infomed of all changes by the in-clusion of a suitable discussion of each change in the Smiannual Radioactive Ef fluent Relegse Report for the -

period in which the changes wer e mde. The discussion of each change shall contain:

a) a summary of the evalua tion that led to the detemina-tion that the change could be made (in accordance with 10 CFR 50.59);

b) suf ficient detailed infomation to totally support the reason for the change wi thout benefit of additional or supplemental infomation; D *

, c) a detailed description of the equipment, components

} and processes involved and the interfaces with other plant systems;

' d ;.{

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SEQUOYAll UNIT I r

(~% .

ADrith1STRATIVE CONTROLS D

d) an evaluation of the change which shoks the predicted releases of radioactive materials in liquid and gaseous ef fluents frcm those previously predicted in the license application and amendments thereto; c) an evaluation of the change which shows the expected

.;;;; maximum exposures to individual in the unrestricted area and to the general population 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 ef fluents to the actual releases for the period in which the changes were made; g) an estimate of the exposure to plant operating personnel

-4 .

as a result of the change; and h) documentation of the fact that the change was reviewed and found acceptable by both thC PORC and tL? NSRB.

D

2) The change shall become ef fective upon review and acceptance 8 by both the PORC and NSRB.

B. Commission initiated changes:

9l;". 1) The applicability of 'the change to the facility shall be

" - determined by the PORC after consideration of the facility design.

2) The licensee shall provide the Commission with written

? . noti fication of i ts deternination of applicability including any necessary revisions to reflect facility

. design. .

3) The change shall be reviewed by the NSRB . at its next regulariy scheduled meeting.

4) The change shall beccce ef fective on a date specified by .

the Commission.

6.16.3 Background and definition of what constitutes ' major changes' to radioactive waste systems (liquid and gaseous).

O

-29 rN '

SEQUOYAH UNIT 1

.3

' M.

N * - - * --e m

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ADMlll!STR ATIVE C0filPOLS A. Background

1) 10 CFR Part 50, Section 50.14a(a) recuires tha t each -

application to construct a nuclear power reactor provide a description of the equip,ent installed to maintain control over radioactive material in gasecus and liquid ef fluents produced during normal reactor operations in-ori-y , cluding operational occurrences.

2) 10 CFR Part 50, Section 50.34a (b)(2)' requires that each application to construct a nuclear power reactor provide

, an estimate of the quantity of radionuclides expected to .

be released annually to unrestricted areas in liquid and gaseous ef fluents produced during normal reactor operation.

3) 10 CFR Part 50, Section. 50.34a(3) requires that each application to construct a nuclear power reactor provide a description of the provisions for packaging, storage and shipment offsite of solid waste containino radio-active materials resul ting frcm treatment of gaseous and liquid effluents and from other sources.

4) 10 CFR Part 50, Section 50.34a(3)(c) requires that each

'sf- application to operate a nuclear power reactor shall in-clude (1) a description of the equiccent and procedures for the control of gaseous and licuid ef fluents and for the maintenance and use of equipment installed in radioactive waste systems and (2) a revised estimate of the infe rma tion requi red in ( b)(2 ) if the expec ted

'jyj; rel ea se: mt exposures dif fer significantly from the estimat'e submitted in the application for a construction pe rmi t.

. 5) The Regulatory sta f f's Sa fe ty Evalua tion Report and amend-ments thereto issued prior to the issuance of an operating licente contains a description of the radioactive waste systems installed in the nuclear power reactor and a de- -

tailed evaluation (including estimated releases of radio-active materials in liquid and gaseous waste from normal operation, estimated annual maximum exposures to an individual in the unrestricted area and estimated exposures to the general poulation) which shows the capability of these systems to meet the appropriate regulations.

(~5 -

SEQUOYAH UNIT 1 6-30 -

O e eEf g

AD:!INISTRATIVE CONTROLS .- . - . . . -

6) The Regulatory Staff's Final Environmental Statement issued prior to the issuance of an operating license I contains a detailed evaluation as to the expected envir-l onmental Lnpact from the estimated releases of radioactive material ir liquid and gaseous effluents.

B. Definition

" Major Changes" to radioactive waste systems (liquid and gaseous) shall include the following:

1) Major changes in process equipment, components, structures and effluent monitoring

• instrumentation from those described in the Final Safety Analysis Report (FSAR) or the Hazards Summary Report and evaluated in the staff's Safety Eval-uation Report (SER) (e.g., deletion of evaporators and installation of demineralizers);

2) Major changes in the design of radwaste treatment systems (liquid and gaseous) that could significantly alter the characteristics and/or quantities of effluents released from those previously considered in the FSAR and SER;

3) Changes in system design which may invalidate the accident analysis as described in the SER (e.g., changes in tank capacity that would alter the curies released); and

4) Changes in system design that could potentially result in a significant increase in~ occupational exposure of operating perscnnel (e.g., use of skid mounted equipment, use of mobile processing equipment).

j . .

SEQUOYAH UNIT 1 6-31 1