Text

Proposed Tech Specs Relocating Procedural Details & Adding Programmatic Controls
	ML20081M621
Person / Time
Site:	South Texas
Issue date:	06/26/1991
From:	; HOUSTON LIGHTING & POWER CO.
To:	;
Shared Package
ML20081M613	List: ML20081M621; ST-HL-AE-3811, Application for Amends to Licenses NPF-76 & NPF-80,re Relocation of Procedural Details & Addition of Programmatic Controls for Radiological Efflutent Tech Specs,Per Generic Ltr 89-01;
References
	NUDOCS 9107100058
	Download: ML20081M621 (159)
	v • d • e

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l ATTACHMENT _A2 PROPOSED CHANGES TO

' TECHNICAL SPECIFICATIONS i.

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l-9107100058 910626 PDR ADOCK 0"iCoo498 PDF A1/OO3.N13 t-

ATTACHMENT A 4 INDEX ST HL-AE-Js //

PAGE l 0F 5 7 4

1.0 DEFINITIONS

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SECTION PAGE 1.1 ACTION............. .......................................... 1-1 1.2 ACTUATION LOGIC TE5T.......................................... 1-1 1.3 ANALOG CHANNEL OPERATIONAL TE5T............................... 1-1 1.4 AXIAL FLUX DIFFERENCE......................................... 1-1 1.5 C HANN E L CA L I B R.\T I 0 N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.6 CHANNEL CHECK................................................. 1-1 )

1.7 CONT AI NME NT I NT EG R I TY. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 1.8 CO NT RO L L E D L E A KAG E . . . . . . . . . . . . . . . . . . . . . T. . . . . . . . . . . . . . . . . . . . . . 1-2 1.9 CORE ALTERATIONS.............................................. 1-2 1.9a CORE OPERATING LIMITS REP 0RT. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 l 1.10 DIGITAL CHANNEL OPERATIONAL TE5T.............................. 1-2 1.11 DOSE EQUIVALENT I-131......................................... 1-2 1,12 E-AVERAGE DISINTEGRATION ENERGY............................... 1-3 1.13 ENGINEERED SATETY FEATURES RESPONSE:iIFE...................... 1-3 l

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1.14 FREQUENCY N0TATION....................... .................... 1-3 1.15 GASEQUS WASTE PROCESSING SY5 TEM............................... 1-3 1.16 I D E NT I F I E D L E A KAG E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 1

1.17 MASTER RELAY TE5T............................................. 1-4 ll n;

l- 1.18 HEMBER(5) 0F THE PUBLIC....................................... 1-4 i

1.19 0FFSITE DOSE CALCULATION MANUAL............................... 1 !

1.20 O P E RAB L E - O P E RAB I L I TY. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 1.21 O P E RAT I O N A L MOD E - H0D E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 i

1.22 PHYSICS TE5TS................................................. 1-4 l

1.23 PRESSURE BOUNDARY LE A KAGE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 1.24 PROC E S S CONT RO L P R0G RAM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 1.25 PU RG E - PU RG I NG . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 l

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1. 2 6 ' QU AD RANT POWE R TI LT RAT I 0. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 p

1.27 RAT E D TH E RMA L P0VE R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 l

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SOUTH TEXA5 - UNITS 1 & 2 Unit 1 - Amendment No. 9 Unit 2 - Amendment No.1

F A1TACHMENT A 2.

ST HL AE 32Il PAGE_2 _.OF 5.2. ~ ~ ~ ~

1NDEX l 43 r.

E OEFINIl10NS SECTION PAGE i 1.28' REAC10R TRIP SYSTEM RESPONSE TIME...... ...................... 15 1.29 R E PO R T AB L E E VE NT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 -

1.30 SHUTDOWN MARG]N...... ........................................- 1-5 1.31 511E 80VHDARY................................................. 1-6

1. 3 2 S L AV E R E L AY T E 51. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6

- dr3 3. o rSO LI DI F I C A1 10 N r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . --l-&-

1.,34 SOURCE CHECK................ ................................ 1-6 1.R.1e STAGGERED TE51 BA515..... .................................... 1-6 l

i ... . ... ............................ 1-6 l 1.3F{-

THERMAL- POWER..........

TRIP ACTUAllNG DEVICE OPE RA110NAL TEST. . . . . . . . . . . . . . . . . . . . . . . 1-6 1.Al2 1.)& ' UN I DE N11 F ] E D L E A KAGE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6

-E .19-UNREST RICT ED- ARE A. . . . . . .. . . ................. .......... 7 - 1 i

-1AO- VENT I NG~. .'. . . . . . . . . ... ............... . ........ ........ - -- l -

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.. , . TABLE 1.1 FREQUENCY NOTATION. .. . . . . ......... ..... ... 1-8 _

.)- TABLE 1.2 OPERATIONAL MODES.... .. .. .. ...... ..... .... .. .. 1- 9 l

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SOUTH TEXA5 - UNITS 1 & 2 ii l

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ATT ACHMENT A *.1 ST-HL-AE-32 / l INDEX PAGE_ 3 0F mS7 tIMlllNG COND1110NS FOR OPERA 110N AND SURVEILLANCE REQUIREMENTS SEC110N PAGE TABLE 4.3-4 SE15MIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS........... ......... ....................... 3/4 3-57 ,

Meteorological Instrumentation............ .............. 3/4 3-58 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION.. . ........ 3/4 3-59 TABLE 4.3-5 METEOROLOGICAL HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS. ................... ....................... 3/4 3-60 Remote Shutdown System ... . .... . .. ... ........ ..... 3/4 3-61 TABLE 3.3-9 REMOTE SHUTDOWN SYSTEM . . . . . . . .. .. 3/4 3-62 TABLE 4.3-6 REMOTE SHUTDOWN MON 110 RING INSTRUMENTATION SURVEILLANCE PEQUIREMENTS. ... . . ... .... ....... ... 3/4 3-66 Accident Monitoring Instrumentation. . . .. . ... . 3/4 3-67 TABLE 3.3-30 ACCIDENT MON 110Rlh3 INST RUMENTAT10N. . . . . . . . . . . . ... 3/4 3-68 1ABLE 4.3-7 ACCIDENT MON 110 RING INS 1RUMENTATION SURVElLLANCE REQUIREMENTS. .. ... . ....... . . ... ....... 3/4 3-73 Chemical Detection Systems. . . . . . .... .., .. 3/4 3-75

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IABLE 3.3-11

-s (This, tab)e number is

c. c . wam ic $ n not

/ cx d ;used. ). . ... . . .. 3/4 3-77 in,Radj'stiveLiquifEffluent:

( - - -

Monitor. 3/4 3-79 l IDACTIVE

), i s n n !., w nx dIQUID in Ef f t,UENT .= b )ing -Instrumentation.

TABLE 3.3-12 R M0W!10 RING-INSTRUMENTATION- 3/4 3-80 m , .. n..

RA 10ACTIVLil' UI,D m nu TABLE 4.3-8 Q EFFLUENT ~ MONITORING Itt5 T RUHLN T AT 10N- 50RVEJ L L ANCE; REQy l REME N T S. . . ... 3/4 3-82 v ww w : p u en

-Radi.pactive ff lmu,gnt .

3/4 3-84 l / ~n >, Gasf,,oug, c c 1, L 's w;Monytorjng e - m a m .:1,Insty~umentation.

Ta r1 TABLE 3. 3-13 M910 ACTIVE-GASE005 Ef FLUENT" MONITORING ltl51]LUMENTAT z e_-nu cw, 10ti. . . . ./w,.

.- . . .;..e. % , .

s fm. ,.ge- >

3/4 3-85 TABLE 4.3-9 RAbl 0 AC-11 V E- G A SE OU S - E F F L UEhU: , MON I TO R 1 NG

-1NSTRUMENT v.ge - SURV AT1,0N. m.E ILLANCE

+:.= m., R.EQU,IREMpj15.

w.- ..... . .. 3/4 3-87 3/4.3.4 TURBINE OVERSPEED PROJECTION..... .. . . .. , . .. 3/4 3-89 500 H TEXA5 - UN;IS ] 62 vi

ATTACHMENTA -

ST-HL-AE-39/ /

PAGE 4 0F 57 INDEX

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LIMITING CONDITIONS FOR OP"ATION AND SURVEILLANCE REQUIREMEWTS SEC110N PAGE 3/4.9.11 WATER LEVEL - STORAGE POOLS Spent-fuel Pool . ... .... .. . ... ............... ..... 3/4 9-12 .

In-Containment Storage Pool ....... .. .................. 3/4 9-13 l l

3/4.9.12 FUEL HANDLING BUILDING EXHAU3T AIR SYSTEM ............... 3/4 9-14 j 3/4.10- SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGlN. .... .. ... ............. ........... 3/4 10-1 3/4.10.'2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS... 3/4 10-2 3/4.10 3 PHYSICS TESTS. ..., .. . . . ........ .... .. ... ...... -3/4 10-3 3/4-10.4 REACTOR COOLANT LOOPS..

. ... ....... ... ........... .. 3/4 10-4 3/4.10.5 POSIT ION INDICATION SYSTEM - SHUTDOWN. . . . . . . . . . . . . . . . . . . 3/4 10-5 3/4.11 RADIDACTIVE EFFLUENTS h w s-s p i c h m wkC6 3/ b1.1.1 LIQUID EFFLUENTS s -

N 4cncentration..... ... .., ... ..,. . . . . . 3/4-11-1 N

Dose.s. .. .. . . . . - . ... ... ..... . .. ...... ... ~3/4 11-2 Liquid Wast qProcessing System. ... .. .... .... .. 3/4 11-3 N .-

Liquid Holdup ranks. ,. ..... .. . .. ...'.. . 3/4 11-4 x

3/4.11.2 GASEOUS EFFLUENTS N Oose Rate. .. . , .

N' . . . .

..,[.. .. 3/4 11-5 i

Dose - Noble Gases. . y. . . . ... ...... 3/4 11-6 Dose _- lodine-131, lodine-133, Tritium, and Radioactive Material in Particulate Form... . . . 'y.

. ......... . 3/4 11-7 Gaseous Waste. Processing System.. . .................... 3/4 11-8 Explosive Gas Mixture. .. .... ... .. . .. ....... . .

3/4 11-9 Gas Storage Tanks. . . . . . . .......[..s. N 3/4 11-10 3/4.11.3 ' SOLID RADIOACTIVE-WASTES. .. ... ..... ... . ' 3/4 11-11 3/4.11.4 TOTAL 00SE...... . . .. .. .. . . . ..... 3/4 11-13 l

l= T l

l SOUTri IEG5 - UNii515 2 xi l

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"~5?IAd5IdENt A a ST HL-AE-3 RII PAGE A 0F 5 '/

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INDEX -- -

illlNG CONDIl10NS FOR OPERAT10N AND SURVEILLANCE REQUIREMENTS SECTION PAGE r

<.[ . Scop.W e,et c'i . '[4 1

3/4.12 RADIOLOGICAL ENVIRONMf NT AL HON 110 RING Tb,

~~~ .-

3/4.12.1 MONITORING-PROGRAM.... . .......... ......... 3/4 12-1 3/4.12.2 LAND USE CENSUS, . Z.lT.^. T. m .........,., . ...,... .

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3/4 12-3 3/4.12. 3 .1NilRL ABORATORY COMPARISON PROGRAM . . . . . . . . . . . . . . . . . . i7 .7 ' 3/4 S _

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SOTIH T E/.A5 - UNIT 5 1 & 2 xii

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ATTACNMENT Al- i l

ST HL-AE 32 I t -

PAGE A 1

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-INDEX' 0F 57 - ,

. BASES-SECTION/ PAGE !

3/4.11 ' RAD 10AC11VE Ef FLUEN15 ( u.b b mace ^> O v @ ,,,,.W p

374rll L L l QU I D E f f L UE N15. . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . , .. . . r~~T,3/4 11-1.

3/4.11.2 GA5T005' E f f LUENI S . . . . . . . . . . .. . . . .wrr.~.". .~.'.T.

~~, _.x ........... B 3/4 11-2 3/4.11.3 SOLID RAD 10ACTIVC VASTE5..n ...

~r n .. , ,............... B 3/4 11-6

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505E...............................................

3/4. n J 101st 'B'3/4-11-6--

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3/4.12 b RADIOLOGICAL ENVIRONMENTAL MONITORING (lhia 'newee - w[m n . . .ncr;';7.T~ ~B 3/4 ~ 12-1

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T/4rh*-1-N0 tdt ORING PROG RAM. , . . . . . . . . . . . . . . . . .. . ....

E -3/4.12.2 LAND USE CENSD5'.7.r*=.9. b m .,_ .,_....._.._.... _.........

. B 3/4 12-1 ,

3/4.12.3 INTERD,BORA10RY COMPARISON PROGRAM.... .......... . .... B 3/4 12;2 -

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c xvi

, SOUTH TEXAS - UNITS 1 & 2

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'Th CXM Afd? .dbo ce*1!-hD th Mdd' "'* NMA "A MhEO h"W"U

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ELLINj UQNL___ -- -

$51ERRELAYlEST L17 ' A MASTER RELAY TEST shall be the energi2ation of each master relay and verification'of OPERABILITY of each relay. The MA51ER RELAY TE51 shall inc,1ude

-a continuity check of each associated slave relay, MEMBER (Sl 0F THE PUBLIC .

1.1B HEFGER(5) 0F THE PUBLIC shall . include all persons who are not occupa- I tionally associated with the plant._ This category does not include employees of tSe licensee, its conti-actors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

This category does include persons who use portions of the site for recre- 1 ational, occupational, or other purposes not associated with the plant.

OFF511E DOSE CALCULA110N MANUAL yc '*d L19 The OFF5ITE DOSE CALCULATION MANUAL (00CM) shall contain the methodology and param<ters used in the calculation of of fsite doses 4we-t+ radioactive gaseous and liquid ef fluents, in the caleviation of gaseous and liquid j ef fluent monitoring Alarm /1 rip 5etpoints, and in the conduct of the Envir on- 4 mental Radiological Monitoring Program. , , ;

OPERABLE - OPERABIL11Y . . _ _ . _ - - - - '

L 20 A system, subsystem, train, component or device shall be OPERABLE or have OPERABill1Y when it is capable of performing its specified function (s),

and when all necessary attendant instrumentation, controls, electrical power,

. cooling or seal water, lubrication or other auxiliary equipment that are requ' red for the system, subsystem, train', component,- or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL MODE - MODE L 21 An OPERATIONAL MODE (i.e. , MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolent temperature specified in Table L2.

PHYSICS TESTS-L 22 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrenentation:

(1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions

- of 10 CFR -50.59, or (3) other-ise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE .

L 23 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leatage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall. '

ATTACHMENT 4'1 ST.HL-AE- 3M PAGE 7 0F q7 SOUTH TEXA5 - U!;lT51 t. 2 P4

MACHMENT ST HL-AE-32 II A 1 u_PAGE M _ 0F J' 7 PMJNL110t6. _ _ _ __ _ _ ._ _ _ _ __

I, PROCESS CON 1ROL PROGRAM 1.24 The PROCESS CCulROL PROGRAM'(PCP) shall contain the current formulas, ll sampling, analyses, tests, and determinations to be r!.ade to ensure that l:

processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Farts 20, 61, and 714 -

ic & ral and-State regulations, burial ground requirements, and other require-ments governing the disposal ofA radioactive waste.

PURGE - PURGING 1.25 PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to puri_fy the confinement.

QUADRANT POWER Titi RATIO 1.26 QUADRANT POWER lill RA110 shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector cali-brated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. With one excore detector inoperable, the remaining three detectors shall be used f or computing the average.

RATED THERMAL P0w'ER L

1.27 RATED THERMAL POWER stiall be a total reactor core heat transfer rate to the reactor coolant of 3500 MWt.

REACTOR TRIP SYSTEM RESPONSE llME 1.2E The REACTOR TRIP SYSTEM RESPCNSE TIME shall be the time interval from when the monitored parameter exceeds its Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage.

[ REPORTABLE EVENT 3.29 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.

SHU100WN MARGIN 1,30 SHUIDOWN MARGIN shall be'the instantaneous amount of reactivity by which the reacter is subtritical or would be subtritical f rom its present condition I assuming all f ull-length rod cluster assemblies (shutdown and control) are ful_ly inser*.ed except for the single rod cluster assembly of highest reactivity worth whic4 is assu. red to be fully withdrawn.

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!OUIH ' E ). A : - Ufn i i & 2 1-5 i

I ATTACHMENT A ?4 ST HL AE 3F//

RE!M1RW- _n -

PAGE 9 0F 5 7

$11E BOUNDARY 1.31,- The 511E: BCUNDARY shall be that line beyond which the land is neither owned, nor leased, 'nor. otherwise controlled by the licensee.

SLAVE RELAY IEST 1.32 A' 5 LAVE' RELAY TEST shall be the energi2ation of each slave relay and verification of OPERABILITY of each relay, The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.

-50L401 r! to!cs -

+-33-50HfdfE*MethtraH-be-theerwwsdon--of--wet-wastMTito a r orm tnai --

,cects-shipping-and-t+uriaL-gro=d re quitementv:-

-SOURCE CHECK

1. A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

5TAGGERED TEST BASIS I A'5TAGGERED lEST BASIS shall consist of:

, a. A test schedule for n systems, subsystems, trains, or ,ther desig-nated components obtained by dividing the specified test interval into n equal subintervals, and

b. The testing of one system, subsystem, train, or other designated

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component at the beginning of each subinterval.

THERMAL F0WER L THERMAL POWER shall be the total reactor core heat transfer: rate to the

! reactor coolant.

TRIP ACTUATING DEVICE OPERATIONAL TEST

1. A TRIP AC10ATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or trip _ functions, The TRIP ACTUATING DEVICE OPERA 110NAL TEST shall include-

j. adjustment, as necessary, of- the Trip Actuating Device so that it actuates at the required Setpoint within the required accuracy, UNIDENTlflED LEAKAGE l 1. UNIDENTlflE0 LEAKAGE- shall be all leakage which is not IDENTIFIED LEAKAGE j or CONTROLLED LEAKAGE.

SOUTH TEU5 - UNii51 f. 2 1-6

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' ATTACHMENT Al ST HL AE 3gil PAGE h 0F C

- (l MLIEll30NS-

.tbESTRICTEDAREA "O UY f x y L 39 ' AUNRESTRIClED n' - AREA shall be any area at or beyond the 511E'B0VliDARY access to which is not controlled by the licensee for, purposes'of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters'or for industrial, commercial, institutional, and/or recreational, purposes. .

VENilNG

. :L 1.40 VENTING shall be the contr611ed process.of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other

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operating condition, in such a manner that replacement air or gas is not pro-vided or required during VENilNG. Vent ~, used in system names, does not imply a VENTING proce'ss.

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ATTACHMENT A 1 ST HL AE-32/1 TABLE 3.3-4 (Continued) PAGE #: OF fi 57 (u

TABLE NOTATIONS

Time constants utilized in the lead-lag controller for Steam Line Pressure-Low-are 1 2 > 50 seconds and T2 < 5 seconds.

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CHANNEL CAllBRATION shall ensure that these time constants are adjusted to these values. -

- The time constant utilized in the rate-lag controller for-Steam Line .

Pressure-Negative Rate-High is greater than or equal to 50 seconds. CHANNEL CALIBRATION shall ensure that this time constant is adjusted to this value.

1

2.0% span for Steam Generator Level; 0.2% span'for Reference Leg RTDs

1. Until resolution of the Veritrak transmitter uncertainty issue, the trip setpoint will be set at 1 1869 psig, with the allowable'value at 3 1861 psig.

1. 1. This setpoint value may be increased up to the equivalent limits of C)[12is\

Ocghtd :4pec4 fee 4 den 3.11.2.1 in accordance with the methodology and parameters of the ODCM during containment purge or vent for pressure control, ALARA and respirable air quality considerations for personnel entry.

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SOUTH TEXA5 - UN!TS 1 & 2 3/4 3-36 Unit 1 - Anendment No. I,4

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IN51 RUME NI A110N. :3 3 , S ,t O [ ces nun@dd -

-4%DM%HVEtlfgiFE4+ i tee 4ME+Nij0MNG 7 1161RUP.EN1 AlIDN [ 003 0$Eh ATTA AENT A R

-li$itn:WW99hEGh0Mft*11&- ._ _

pm 3_j 3.3. 30 The radioactive liquid ef fluent monitoring instrumco(ation channels shown Tablu 3.3-12 shall be OPERABLE with their Alarm /Trjp'Setpoints set to ensure the limits of Specification 3.11.1.1 are not eeded. The Alarm /

Trip setpo gts of these channels shall be determined an djusted in at Jance with the methodology- and parameters in the Of f 5ITE DOS CALCULA110N MANUAL (ODCM).

APPLICABIL1TY: At 1 times.

M, T10fj:

a. With a radioactive icuid effluen monitoring instrumentation channel I Alarm / Trip 5etpoint 'ss cons ative than required by the above specification, immedia ly s pend the release of radioactive liquid ef fluents monitored by the ff f ected channel, or deciare the channel inoperable, b.

With less than the mi; mun numbronitoring PERABLE, take instrume the ACTION tation shownchanne)of r in Table 3. 3-12. store the inoper e instrumentation to OPERABLE status within t time specified in th CTION, or explain in the nextSeciannu)a Radioactive Effluent ReleMe Report pursuant to Specificatiop 6.9.1.4 why this inoperability was not corrected within th 1me specified.

c. The pro 4sions of Specification 3.0.3 are not appl able.

Sl!RVIJ LLEE dQUIIEEUUJ _

L 4.3.3.10 abh radioactive liquid ef fluent molitoring instrumentation c nnel

! b demonstrated OPERABLE by performance of the CHANNEL CHECK, 500RC shall / CHANNEL CAllBRA110N, and O!GITAL CHANNEL OPERATIONAL TEST at the CHE-f rep...cies shown in Table 4.3-8. \

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! SOUTH TEXA5 - UNIH I L 2 3/4 3-75 l . - . _ - ._ ._ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ __ __ _ _ __ _ _ __ __ ______ __ _

Dbb y, TABLE 3.3-12 ) 5E a

y , TADIGAGFWfH-lQUiG-4fft4E4L-WrNHORING--INGTRUMENTAHON-M .

b N MINIMUM i

N_ . . C!!ANNELS c INSTRtMENL ' OPERABLE ACTION il d 1. Radioactivity Monitors Providing Ala7' W <

~ Automatic Termination of Relo,- N Liquid Waste Pro _ s ng Discharge Monitor N'l 43

2. Flow Rate " urement Devic s

~ ~.

Liquid Waste Processing Discharge Line 1 46 o,

G=

g m >

C N)N N 2

_,E GT j Wz A -4

,o r P 1

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nadS TABl[ T hrs L h{b S AUACHMENT d ST HL-AE-3911 3.3-32(Continued](pi"O PAGE ._Jft 0F M l -AM10MT AlfMEJ1t-N N With the number of channels OPERABLE less than required by the

/

AC110t4 43N Minimum Channels OPERABLE requirement, effluent releases via ghis pathway may continte for up to 14 days p vided that prior t initiating a release:

a. tsleast two independent sample a're analyzed in accordance wit ecification 4.11.1.1.1 d

b. At leastNtwo technically alified members of the facility staff ind3hqndently verify the release rate calculations anddischarge}ine Tving.

Otherwise, sospend ryJ *N e of radioactne effluents via this pathway.

AC110N 44 -

(Not Usec)/

ACTION 45 - (Not Use ACTION 4E - the number of channels OPERABLE less an required by the Wi[ttPi imum Channels OPERABLE requirement, effluch(releases via thispathwaycaycontinueforupto30daysproviQdtheflow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during a qual 7

, releases. Puip perf ornance curves generated in place hy, be used to estimate flow.

SOUTH TEy.A5 - UNii5 1 & 2 3/4 3-81

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'diTACHMENTA:

ST HL AE 3V //

L

/ PAGE.A 0F 57 (1)

DIGITAL CHANNEL OPERA 110NAL TEST shall al

' *a n '$5c atioNec$IY$n' of ttlI "iSU$'c"'IiTf!n'"e"x%",t[ l

a. Instrurn n icates measured le e 5 above the Alarm / Trip Setpoint, or ' l

b. Monitor failure, (2) (Not used) i (3) The initial CHANNEL cat!),ATION shall be perforrned using one or more of !

the reference standarjf(certified b,'th- National Bureau of Standards (4BS) or usirs stan;aros Jriat have been obtaine 4 rom suppliers that participate in sneasurement a 6rance activities with NB5 h se standards shall permit calibrating the ystem over its intended range o gy and rneasurernent rangc. for - sequent CHANNEL CAllBRA110N, sources have been related to the ini M ,al calibration shall be used.

(4) CHANNE ECK shall consist of verifying indication of flow duri periods of r teast. CHANhil. CHECf. shall be inade at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months de S on which continuous, periodic, or batch releases are made.

)

50VIH TEXAS - unjl5 1 & 2 3/4 3-83

. . _m. ._. .__. . _ . . _ _ _ ._ _ _ _ . _ -. _ . _ _ ___.___ -

_ _ = _ . . _ _

ATTACHMENT A IN51F:ugjjl A1105 ST.HL.AEO//

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A E -/l.- 0F 3 7 -

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w m m.m m m _m .>n ., a

01. p \ os N4 tyx>

3. 3. 3. H lhe radioettwog,anous +4(luent, onitoring instrunentation (hannels shown in lable 3.3-13 shall t t OPERABtt ensure that the limits of 5pt:ification$ith U 3. 2 their 2 ? 2 Alarm W. 3.M.2. /1 5rip are5ctroints not exceeded. set to-The-Alare/1cipicipointrofmese-thennels tectingipecif itation-3rlhPe

.shalLbc_dcteredn+4-andadjuntcHn attordance-with-the-ee thedol ogy-and -tioree ot+rs.4n-the-CD?4-

,APPt IC ABl tl_lY- As shown in hble 3.3-23

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cc0 g plos w, .c

a. With / woioact4ve :as cewef41eee monitoring instrucentation channel Alarm /lrip letpoint less ci ervative than required by the ebeu s pec i f icat i o . .ir.n dietely.-w eed4he-nl+ew-ef--r+diac tin 1ere the :

.catm:s-tfiluentuni4ered-tethe,rtf tttTd ttanneig'.r de: channel inoperabic Lon up ydge thc t%fnwGM nun.ber of MU+H- rac uttu gasc w -t+f4w44 rani t c r i n;

b. Vitt i ins treentation c ht ncis 1+w4heetheJhiru CLw+1+ OrtRABt[, - /

take the AC110N she.n in labic 3.313. Restore the inoperabic / #9.h7 ,

instrun entation to ?PE RABL E st atus within 4he-.tir+-Hm4th a-indt.c 3 E JJCLg or-e > pl e br-w,- tbne w t-feei en9oel-4(4eac Wt.-t44 hret Er.lt = < Lhpor! p ur44 n t ..tcu $ pec i f ita t4 on 4 r9 r id + ny-this.._J nor.eeet ij i ty wdLtorny ted v th-in-the-thr ee Vied.g g y p ,g,f/g Oceufsss __,

(,d>t?fd35W W$$$l)3 ?$5 Tl p$3'Nikk h'hb '"./ Mhl'b M'"*"* *' ' r c.

Theprovisionscd:>ecificationJ. .ohare not applicabic 4@d] to w rad % O'S

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4. 3. 3. D tech tw<ctive gr ues t-eff ktnt monitorir.g inst run entat ier c ht nm 1

s. hall be denons trated OPf RAE,t! by perf oir.ance of the CHANNEL CHEC A, %e:+

CHKtt, Cri;NNEL r AtlE RA110N ar: ANALOG CHANNEL OPERA 110NAL lE51 or OlCll AL CHANNEL OPERA 110NAL lL5i, u fppliceble, at the frequencies shown in lable 4.34.

SOUlH 1[Mi - tN15 ) L 2 3/4 3-H a - m w w.,,%y,,v..y..m-ew+._ ,e,m,.,.,,,.,yypy, ---.,,,..mi-e y,,e- .,-r,------+twr-p- **

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ATIACHMENT /4 l Ot[3.3-13(Continues ST HL AE 32/I l

PAGE 19 0F 57 i 1ABlE N01A110NS =

'* At'all t4*ew-

- During GA$l005 WA$~E PROCESSING SYS1EM operation.

AC110N STATEMF.Nis ACTION 47 - ot used) ve'l 05 ec0 ACTION 48 - ith-tee . nun.ber-of_channe1LOPIRABtt-lesMhan required 4y4he Alinimu -Channels-OPERABib requirement,_ettluent-releases-vt e--

4his -psthway-may <entinue-for-up--to-30-days-provided-the-44ew AC110N 49 -

MeHt (ao+ ettim)trd oud at-1cartmev7er4-.houtL_

W1h-Miniw tl.c_nucer_.pLcip@nne,hAPf Channels OPERT tE~requiremant7 RABLE-le ss 4han-ef fluent requi red -by the~

releases-vie tAiG-ptthway1nay-tontinue for up-to-304ays-provided-grsh tamplorare-taken at leest-once per it hurr and-these Samples.

aro6ndyzed f or radiceetivity wi-thin _244. cur 4, ,.

ACTION 50 - (Not visd)

ACTION 51 - With t*s number of channels OPERABLE less than required by the Minimu- Criannels OPERABLE requirement, operation of this GASE0Vi WA51E PROCESSING SYSTEM may continue provided grab samples are collected at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the folloH ,g 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 52 - (Not used)

ACTION 53 - (h!,f&cl un r e nv . co4-+hanno4-Op[4Astf-4 est-thar, require ++y4he H4*4muMhennt45-oftRABtE ii;quirwant;-e444uent-r+4 ease &-vie th e-ef4ec t ed-pa thwey-e sy-ton ti nue-f omp4o_34J ay s-p r ov4 d e6-544plet aremntinuouslyTottFctTd vt th aud-Itary sagline eqttipment--as required-in-Part-Amf-tte-CDCM---

l SOUT H 1 E X A5 - UNll 5 1 :. 2 3/4 3-8fa

97 ATTACHMENT Al ST HL AE ?su PAGE .20_0F S 7 . _ . -

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SNi . TD A5 - UNils 16 2 3//. 3-57

1 ABt E 4. 3-9 (Continuedl ATTACHMEN93 ST Hl. AE 3R d 1 ABtI NOTA 110NS PAGE_al 0F 57 i

MotO M D)

.t-a Wt 4*u .

" During GASI: J5 WASTE PROCESSING SYS1[M operation.

(1) ~~~ -

(Not fasf Used)Q

~

q y -

(2) /%e DIGilAL HANNEL OPERATIONAL TEST shall also demonstrate room alarm r.nunciation occurs if any of the following-roridWions existsi

[a. Instruttnt in icaterm s above the Alarm Setpoint, or utdni tot f ailure.

/Igsi E Eb ~

m (3) The initia)i hat"i!L : Cot}CRCION tholi be perferrad usinc one - r:os# 'j the referen:! standards certified by the National Burejh_of-StaEdards (fiES)

~

f or using strcards that have been obtalgfmmtFpTiers that participate in measuren.rt assurance a ;,Jvit-irs 1th NB5. These standards shall permit ;

calibrating .ht s-~ ~ ver its intended range of energy and measurement i rangtQr .usequent CHANNEL CAllBRA110N, sources that have been related j

, tv-ne i ni t ' ! L cJ libration shall be used.. _ _ . . d.

(4) (Notlised) .

(5) The CHANNE! :ALJERATION shall include the use of a standard gas sample -

containing e nor.inal two volurc percent oxygen, balance nitrogen. ,

l l

l i

SOUlH TEXA5 - UN:~F 1 L 2 3/4 3-88 -

~ AHACHMEST7\ :L ST HL-Aq W//

4 3/4.11 RAD 10AC11VE [IflUEN15 PAGE b, 0F 67 3/4.11.1 t10010 ErrlUEN15 hius uppt lIu t bt+1 (L urbeq m w b G e CONCEfff RAl t0tf-----

. - j MMlulMNilMkf.2_t2MfdME-- . < l

's i 3.11.1.1 The concentration of radioactive 9aterial released in liquid effluents-to URRESTRICTED AREAS (see Figure 5.1-4) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table 11. Cohen 2 for radionuclides other tha'nsdissolved or entrained nobic gases, for dissolved or entrained noble gasesh the concentration shall be limited to 2 x 20 8 microcurle/al total activity s s i

APPLICABILITY: t al times. '

i x l ACTION: 'N '

s\

With the concentration of rad' inactive material released in liquid effluents to

~

UNRESTna.iED AREAS exceeding the'ohove limits, immediately restore the concen-tration to within the abovefimits.

Mfd'1111MCLAE2Vgl{1 U - - - -

\-

- s 4.11.1.1.1,Mhloactive liquid wastes shall be sam' pled and analyzed according to the sem; sling and analysis program specified in Part'A the ODCH.

/

4.11 ~' 1.1. 2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the 00CM to assure that the concentrations

/atthepointofreleasearemaintainedwithinthelimitsofSpecification'

/ 3.11,1.1. *

/

SOUTH TEXAS - UN115 1 & 2 3/4 11-1 .

l

ATTACHMEf0M ST HL AE M h a PAGE 13 _.OF N 5 7

!%D10V ilv! liiitiENls 5. l {, \ , L "Y'"' ". M' ;

Un en ?a. "C 'f 7, 00$E ,/

/

N .Nk . . :.-== ~ = n. m -.m:= m = =um me mcm

.1.2 lhe dose or dose committrent to a MLMM.R Of THE PUBtlC f M) radioactive als in liquid effluents released, from each unit, to UNRESH1ClED ARLA5 niater(figure (see 5.1-4) shall be limited: -

a. ring any calendar quarter to less than or equalj o 1.5 mrems to thlhwhole body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or eqval to 3 mrems to the whole bodyhid to less than or equal to 10/mrems to any organ.

/

APPt1CAtltllY: At all ti s.

Atl10!j:

a. With the calculated dose (rom thefrelease of radioactive er +ials in liquid ef fluents escoedT g apy of the atiove limits, pre:

and subnit to the Commission (thin 30 days, pursuant to 5p 'ication 6.9.2, a Special Report that Antifiesthecause(s)forex ing the limit (s) and defines it cortittive actions that have t: talen to reduce the releases anf the produged corrective actions to De taten to assure that sut;6equent relcays will be in compliance with the above limits. Thi, Special Report Wall also include: (1) the

, results of radiolooipa)l analyses of the drqnting water source, and (2) the radiologica) irrpact on finished drir(Ling water supplies with regard to the reqdrer*ents of 40 CF R Part 141x Saf e Drint ing Water Act.' \

b. lhe provision ('of Specif ication 3.0.3 are not ap; icable

'N mvu uMULqtWyML _= _ __ _ _ _ __

4.11.1.2 Cumula e dose contributior.s f rom liquid ef fluents for ttlescur:ent calendar quarte and the current caleridar year shali be determined in %ccordance with the (netho ology and parameters in the ODCH at least once per 31 dayr..

\

\\

N

\

'Thf requirements of ACTION a.(1) and (?) are applicable only if drinting water *

. sdpply is t aken f rom the receiving water body within 3 miles of the plant \

.ischarge. In the case of river-sited plants, this is 3 miles downstrear, only. \

SOUTH 1DAS - UN1151 & ? 3/4 11-?

/

,,3udabo a "M I:AD10 4t11vt tiit ut N1s 2, , i \ i \ ,2. 1 h.s

.-, n & - ,'

t_1_qu_l0_WAs1 t I roc _I s_ site, 5Ysit h y'

g)) Aggy[g q ST4tLAE Mi

. pq y%e.. el M. .e=u

.. . - . =. p + p:.1)c.t

.- -- n -v PAGE- ._TL ~OF G ,e

/

3. h s 1. 3 1he liquid Waste Processing System shall be OPERABI,f and appropriate porticM of the systec shall be used to reduce releases of fadioactivity when the projected doses due to the liquid ef fluent, f rom eactVbnit, to UNR[51RICl[0 '

AREAS (see Naure 5.1-4) wvid exceed 0.06 mrem to the iole body or 0.2 trrem to any organ 1 31-day period.

APPLICABll]1Y: A t 'al l t i r,e s ,

ACTION:

s'N

a. With radioactive yquid waste beiph discharged without treatrtent and e limits apd any portion of the liquid Waste io (acess Systert processing of the aCby\in not opera, tion, prepare and subrtit to the Commis-sion within 3D days, pksoanJto Specif iration 6.9.2, a $perial Report that includes the f ollowiyinf ot mation:

1, [splanation of wh q radsaste was being discharged without tr<attent, ident fication of any inoperable equipment of subsystems, a re the reason (or the inoperability, N

2. Action (s) .a cn to restore theynoperable equipment to CPLRABl[

status, e d N\

(h

3. S um.a r description of action (s) ta to prevent a recurrence.

b T he prov "s ions of Sp c if ications 3.0. 3 are )191 ai;;1ic able.

s N

c

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cor

: , er1ilty

.* t . . t ,,/n")

v.>r r r: e, > .

.v=. _

4.11.1.3.1 oses due to liquid releases f rom each unit to UN ISlRICIED Af:LA5 shall be y'rojected at least once per 31 days in accordance with'the methodology and par .eters in the OXM when Liquid Waste Processing Systems are not being fully ilizeu. s 4.1).l.3.2 The installed Liquid Waste Processing System shall be considered OP 'RABL E by meet i ng Spec i f u at iens 3.11.1.1 and 3.11.1. 2.

SOUTH lly AS - UN1151 & 7 3/4 11-3

. . ~ _ - . - . -- . . - - - . - _ - . - _ . . - - -

ATTACHMENT A2, ST HL-AE 3r///

RAD 10AC11VI TTflufN15 '

- e,-

3/4.J1. 2 GASIDU! _ [f f LUENTS Tho 'fA ""

"1'"* ^^ ' ~ "

s9d us e d. ,

DOSE Rtg

'tiPMDidfjMilP4-MLFE8AT3ENrr Dis 2.1 1he dose rate due to radioactive materials / released in gaseous -

efflul45 from the site to areas at and beyond the 11E 80llNDARY (see Figure 5.1-3) sha e limited to the followi~1: I

a. For le gases: Less than or equal o 500 stems /yr to the whole body a less than or equal to 300 nrems/yr to the skin, and

b. for lodine- 1, for lodine-133, or tritium, and for all radio- !

nuclides in r iculate form wi h half-lives greater than 8 days:

less than er eq 1 to 1500 m ms/yr to any organ.

ADPLICABill1Y: At all times. /

l ACT10N:

\ -

With the dose rate (s) exceedi the e limits, immediately restore the release rate to within the a sve limit (s m u u3x u n nu m _/_____m _ _ _ _

4.lL 2.1,1 The dose fate due to noble gases in gas us effluents shall be determined to be within the above limits in accordant with the methodology and parameters in iie ODCM.

4.11.2.1.2 ium and all radionuclidesThedoserateduetolodine-131, n particulate form with half-lives lodine-133,tr(ansy,daysin greater th caseous offl nts shall be determined to be within the above lintits in accordance ith the methodology and parameters in the ODCM by obthiping represent, ive samples and performing analyses in accordance with the am;)l ing and anap' sis program specified in Part A of the ODCH.

N SOUTH Tf xAS - UN1151 t. 2 3/4 11-5

g RAD 10Ac11vt E r r t ut uls 6 i l 2. L T 6 p. . b <Sk "m e n1 k' 1

y ,v# m d j j 005t - noctt casts ,,,,,g ST HL AE ' ?y/ /

PAGE M OF G7 LISJ11M29HFdtiqfdBEPAl!M _ _ _ __ ..

3 12 The air dose due to noble gases released in gascous pf luents, f rorn eachh.2it, to areas at and beyond the 511E BOUNDARY (see figure 5.1-3) shall be limh rd to the follo >ing: -

a. ring any calendar quarter: Less than or eqv 1 to 5 nrads for ga.ma radiation and less than or equal to IVrnrads f or beta radiation, and

b. During g calendar Less than op equal to 10 strads f or gar:aa year:or equal radiation less than to 26 inrads f or beta radiation.

APPLICABitl1Y: At all irr e s .

ACT10% /

a. With the calculated Mr do) f rom radioactive noble gases in gaseous ef f luents exceeding anhof the above limits, prepare and submit to the Co mission within 3f tays, pursuant to Specification 6.9.2, a Special Report that iQfntih ts the cause(s) f or exceeding the limi t(s) and the releases and ethe defines proposed CDrtective actions c[orr/ttive acMons to be talen thatto have been take s'

assurt that subsequent releases wi'l(be in compliance with the above l i rai t s . N

. N

b. t applicable.

T he provisjons of Specification 3.C.3 are'rg\

/

/ \

ifNULMNCL1[g'JJJfiNll . _ . _ _ _._._,._.._._..lx._......~_ _

C./...ulative dose contributions f or the current calendar' quarter

'N 4,11.2.2 md current cpfendar year f or noble gases shall be determined in accord 3qr< with the metb6dology and parameters in the ODCM at least once per 31 days. N

'N 6

SOUTH ltXA5 - UN1151 & 2 3/4 13-6 l

/

' ' / N '"

RAD 10ACllV[ [i f tt'f N15 A,ih?.5 s su-m{W-c 4' OD5[ - 10DINf-131, .10DifR-133,1RITlUM, AND RAD 10ACllVI HAl[RI AL IN -

I MTRTtTTFT0Ta Aiiat;ithENT A L ST Ht:AC: 1I PAGE J U"OF W ditUltCR!@ll]0rfEff EM10N- 1- l 3.Sh .3 The dose to a MEMBER OF THE PUBLIC f rom lodine,21, lodine-133, triti and all radionuclides in particulate form withjfielf-lives greater -

than 8 ays in gaseous effluents released, from each voit, to areas at and beyond the'NSITE BOUNDARY (see figure 5.1-3) shall be/ limited to the following:

\

Ourtta any calendar quarter:

/

a. less tharvor equal to 7.5 rnrems to any organland, /

b.

N /

Duringan)qalendaryear: less tt,gn or equal to 15 inrems to any organ.

\

APptlCAB!llTY: At all tiges.

\ ,

ACT10N:

\N

a. With the calculated dd5 f rom the release of lodine-131, lodine-133, tritiut, and radionucipJeg in particulate f orm with half lives greater than 8 days. ,in gas (ous ef fluents exceeding any of the above lircits, prepare and Aubmit the the Commission within 30 days, pursuant to Specification C 9.2, a Spec'ial Report that identifies the cause(s) 7 s forexceedingthy/mit(s)andde(inesthecorrectiveactionsthathave li been teken to riduce the releases h d the proposed corrective actions to be taken to/ assure that subsequentxteleases will be in compliance with the abo /e lirnits. N

/ \

b. The provitions of Specification 3.0.3 are n0t. applicable. "

/

SVhilLL6'sLJyaVIFRiM 5_ ___ _ _ _. __ . ,._ mi_

x 4.11.2.3 Cym/ulative dose contributions for the current calendar quarter and current calendar year f or lodine-131, lodine-133, tritium and radionuclides in partic41 ate form with half-livc3 greater than 8 days shall be deterrnined in acc per 3}p/ dance with the teethodology and parameters in the ODCM at least once days.

SOUTH TEXA5 - UN115 1 L 2 3/4 11-7 I l

RAD 10AC11VE EfflUEN15 511.2 M hG 4 i & ^ V "h ' " "' O GASEOUS WA51f PROCESSING SYSTEM M lerCHMENT A 2.

ST HL AE-32/l

-til"jlE_QWU10 tim 2f$iHEs - _ __

PAGE B 7

- ___..n 0F .

57 N

3. /

. 2. 4 The GASEOUS WASTE PROCESSING SYSTEM shall be OPERABLE and Appropriate por lens of this system shall be used to redute telt asu of radioactivity when the p'bqjected doses 'in 31 days due to paseous ef fluent releases.Arom each unit, -

to area t and beyond the 511E BOUNDARY (see figure 5.1-3) woufd exceed:

a. 2 mrad to air f rom gamma radiation, or

b. 0.4 rad to air f rom beta radiation, or

c. 0.3 mr to any organ of a MEMBER Of THE 00BEIC.

/

APPLIC ABI L IT Y: At - 1 t i rne s .

AC110N:

a. With radioactive paseous waste b>ing discharged without treatment and in excess of the above lipits, prepare and submit to the Commission within 3Dx da ys, rydrsuant to Specification 6.9.2, a Special Report inat includrt the following information:

N 1.

ldentificationoffn s inoperable equipment or subsystems, and

( the reason for e ino bility,

, 2. Action (s) tal n to restore \ he inoperable equipment to OPERABLE status, and

3. Sumer scription of action (s) n to prevent a recurrence.

b. The provis) ns of Spec i f icat ion 3.0. 3 are Iid pplicable N

EULVL1LUS[JL~IqtRNTL ___., __&,--. -

4.11.2.4.1 es due to gaseous releases from each unit to area'tsat and t>eyond the flTE BOUNDARY shall be projected at least once per 31 days in accordancV with the methodology and parameters in the ODCH when the CASE 005 WASTE P CESSING SYSTEM is not being fully utilized. s 4.11.

\

4.2 Thc installed GA5t0US WASTE PROCESSING SYSTEM shall be considered OPE,$BLE by meeting Specifications 3.11.2.1, and either 3.11.2.2 or 3.11.2.3. s ,. l 50VIH TEXA5 - UN115 1 & 2 3/4 11-E Unif j - Amendment No. 4

h 10AC11vt ifItt:[N15 AEfAC'HIAENiM k-3/4. n 3 50t ID R A010AC11gyA51f 5 ST HL AE ,A /

PAGE.29 0F 6. / .

lEll!'HOMUE TP FL m !0'L__ _.__ _

3.11.3 Radica 'a vastes shall be solidified or dewatered in ccordance with the PROCESS CONI 4 PROGRAM to meet shipping and transportati requirements during transit, and (isposal sitt requirements when received t the disposal -

site.

APPLICAE'lll1Y: At all t ces.

ACTION:

a. With 50L10lflCA110N dewatering not meeting disposal site and shipping and transpor tion requirementy,' suspend shipment of the inaaecuately processed 'astes and cort

Solid Wast System as necessary to prevent recurrence.b. With 50L10lflCA110N or dew \aqring r/t perfortred in accordance with the PRDCESS CON 1ROL PROGRAM, est he improperly processed waste in each container to ensure that(it meets burial ground and shipping requirerents and take appropria administrative action to prevent recurrence.c. T he pros isions of 5;'ecificat on '/3.k.3 are not applicable.( M 11}llMiC.Lfi M lMEN15 m -,= m=m -- - =m ___=_ 4.11.3 50LIDiflCAT10N of at le ,t one representat ge test specimen f rom at least every tenth batch of eacly type of wet radioactT e wastes (e.g. , filter sludges, spent resins, evapor (or bottoms, boric acid olutions, and sodium sulfate solutions) shall be crified in accordance wit the PROCESS CON 1ROL PROGRAM-a. If any test sp simen f ails to verify 50L10lflCA1 QN, the 50L10lflCA110N of the batch nder test shall be suspended until s\ch time as additional test specime s can be obtained, alternative 50L10lf1 CAT!0N parameters can be dete .ined in accordance with the PROCESS CONIROL PROGRAM, and a subs quent test verifies 50L10lf! CAT 10N. 50L101EICA110N of the batt 'may then be resumed using the alternative 50L)DiflCAT10N parametr 's determined by the PROCESS CON 1ROL PROGRAM;b. If th initial test specimen from a batch of waste fails to\yerify 50L}dlFICAT10N, the PROCESS CONTROL PROGRAM shall provide fo co)'lection and testing of representative test specimens f cach rorr.gthe cdnsecutive batch of the same type of wet waste until at least 'three/onsecutiveinitialtestspecimensdemonstrate50L101 The PROCESS CON 1ROL PROGRAM shall be modified as required, as provided FICA 110N. \ in Specification 6.13, to assur e 50L10lflCA110N of subsequent batch'es of waste; and -50tH H~lf E A5m VN115 h? _ - -3/4 11 - _ _ - - - _ _ _ _ _ - _ - __ / ( AD10AC11VE EFFLUENTS / ATTACHMENT R~ / ST HL AE 3r/ t -( N / PAGE 30 0F 57 SEVO [QUM[!1!!1L(ContinuedV __c. With nStalled equipment incapable of meeting Specification 3.11.3 or dec1&re4' inoperable, restore the equipment to OPERABLE status or provide (be-tontract capability to process wastes as necessary 10' satisfy all' app,licable transportation and disposal requiremefits. ./ / N's.N .. 's. N N. , l ( , 'l -500TH-1E X A$~~; Ut 115-1-1~T -~3/4 11 . . ~ . _ _ . . . . _ _ ATTACHMENT C. ST HL AE-37/l \. CAD 10AC41vH Ut 0DW PAGE _31 0F S/ / ~ 376.11.4 101 Al DD5[ [))jd_ OM ll109.IO M [fAl101 _ m m . y 3.11.4 The annual (calendar year) dose or dose commitment to any HEMBER,4r 1HE PUBLIC'Kue to releases of radioactivity and to radiation f rorn uranjom fuci cycle sourcety shall be limited to less than or equal to 25 mretts to the whole - body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mreih APPLICABILITY: At\q l tin.es. AC110N: a, With the calcu pted doses f rom the release of r ioactive inaterials in liquid or gaf+uus effluents exceeding twice/the limits of Specifi-c ati on 3.11.1. 2a. ,s 3.11.1. 2b. , 3.11. 2. 2a. , 3 J1. 2. ?b. , 3.11. 2. 3a . , or 3.11.2.3D. , calculdtions shall be made including direct radiation contributionsfromtheunitsandfromoutsfdestoragetanksitdeter-mine whether the above\ limits of Specification 3,11.4 have been ekceeded, if such is the case, prepare Mnd submit to the Commission within 30 days, pursuant to $recificati,on 6.9.2, a Special Report thatdefinesthecorrectivhactiontVbetakentoreducesubsequent releases to pruent ecurrer%e of e (eeding the above limits and includes the schedule for achievi j conformance with the above limits. ( This Special Report, as definea,)i 10 CFR 20.405(c), shall include an analysisthatestimatestherad/gtionexposure(dose)toaMEMBEROf 1HE PUEllC f rom uranium f uel %'clh sources, including all ef fluent (, for the calendar year that includes pathways the release and direct radiatto)is (s) covered by t/i repor\. It shall also describe levels of radiation and concentr .tions of radioactive material involved, and the cause of the exposur levels or corhentrations. If the estimated dose (s) edeeds the ab ee limits, and if\the release condition result-already been corrected, ing the in rialation $recial of 4<iall Report Cf R include Part 190 a has n6(for a variance in accor-request dance with the pro 1sions of 40 CFR Part 190\ Submittal of the report is considered a mely request, and a variance is granted until staff action on the travest is com;)lete. s \b. The provisiop/ > of Specification 3.0.3 are not appl icable.\ \ WIIWlMED fMMib________dp_-.- N 4.11.4.1 Comu otive dose contributions from liquid and gaseous eff)pents shallbedeter)minedinaccordancewithSpecifications 4.11.1.2, 4.11 1 2, and 4.11.2.3, a in accordance with the methodology and parameters ,n the'0DCM. N 4.11.4.2 Cumulative dose contributions f rom direct radiation f rorn the un$ts and f rom radwaste storage tanbs shall be determined in accordance with the 'N meth9 dology and pararreters in the ODCM. This requirement is applicable only\ unci /r conditions set forth in AC110N a. of Specification 3.11.4. N 50VlH-1 E XA5 - ~ UNH H- 6 ~?~-- -~ 3/4~ _ _ _ - _ _ _ - _ ____-_-____"5'ITActiMENT /4 l \ ST HL AE 3V//PAGE o 0F 57 3/4s12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.1 ,. MONITORING PROGRAM f' LIMITING C0t ITION FOR OPERATION ' 3.12 1 The Ra (o ical Environmental Manitoring Program (REMP shall be conducted as spe ed in the ODCH. /)APPLICABILITY: At il times., i' /ACTION: / ;a. With the Radiological invironmental Monitoring Program not being :conducted as's' ecified, prepare and submit'to the Commission, in the , AnnualRadiolo(cal.EnvironmentalOperatingReportrequiredby < Specification .j.1.3, a description of/the reasons for not conduct-ing the program a$ required and the plans for preventing a recurrence. ; U b. With the level of fadioactivity as,the result of plant effluents in an environmental sakpling medium at a specified location exceeding the reporting levels of \he REMP when' averaged over any calendar quarter, prepare and subtrit toithe Commjssion within 30 days, pursuant to > Specifiestion 6.9.2, a Specia) Report that identifies-the cause(s) forexceedingthelimiks)an'ddefinesthecorrectiveactionstobe taken -to reduce radioactive' effluents so that the potential annual dose" to a MEVdEH OF TiiE\f. 0BLIC is less than the calendar year limits of Speci fications . 3.11. ltR, 3.11. 2. 2, or 3.11. 2. 3. . When more than one of the radionuclides i V the,REMP are detected in the sampling medium, g thisreportshallbe,spbmittedif:\concen'. ration /(1)concentration (2) + . , Q 1. 0 reportTog levei (1) + recorting level (2)/ \WhenradionucligesotherthanthQselistedintheREMParedetected and are-the rejult of plant efflu'e.nts, this. report shall be submitted-if the potential annual doseto a'NEMBER OF THE PUBLIC from all radionuclid/sisequaltoorgreateor%than Specification 3.11.1.2, 3.11.2.2, the-calendar 3.11.2.3. This reportyearislimits not of required (f.the measured level of radioactivity was not the result of plant /effluents; however, in such an\ event, the condition shall berep/rtedanddescribedintheAnnual'RadiologicalEnvironmental-OperptingReportrequiredbySpecification6.9.1.3.[^f/N N g\ *T)dmethodologyandparametersusedtoestimatethepotential' annual'doseto a MEMBER OF THE PUBLIC shall be indicated in this report.J/ # SOUTH TEXAr ~ UNI 15~1' tc2 - -3/412 . . _ . _ _ ~_Mk A11 ACHMENT / ST HL AE 37// / RA {0 LOGICAL EWIRONMENTAL MDt010 RING , PAGE 33 . 0F R7 - t, ',- - - f_l lIMlH!i, .C0!(D111M_fMELFAIION ACTION ( niinued) .c. W i milk or fresh leafy vegetable sampics unavailable from one or l more of the sample locations required by the REMP, identif/ specific i llocat ns for obtaining replacement samples and add them within - 30 days to the Radiological Environmental Monitoring Program given in l the 0001- The specific locations from which samples ydre unavailable may then p deleted from the monitoring program. Pursuant to Spe-cificationy.14, submit in the next Semiannual Radidactive Effluent Release Rep t documentation for a change in the pDCM including a re-vised figure -) and table for the ODCM reflectip% the new location (s) l with supportin information identifying the cadse of the unavailabil- 1 ity of samples a sd justifying the selection i the new location (s) f or obtaining sampgs.d. The provisions of Sp) ification 3.0.3 ar > not applicable.i 11'Flll11AtKL3l0El3EMElil5_.._. . N / 4.12.1 The radiological environmentahponKoring samples shall be collected pursuant to the REMP from the specific lopations given in the table and figure (s) in the ODCM, and shall be analized pursuant to the requirements of and the detection capabilities require by\the REMP.\\l N\x Il rE 1- OUIM-TUAS-tttu TS-1+e -3/L12 __ ._ . . _ _ .. . . . _ _ _ . . .... _ _\ RAD [0 LOGICAL ENVIRONMENTAL MON 110R]NG lE INT [ENT A2 3/4.1 ** LAND USE CENSUS L10111811 %D1LLOlilDR DW?T12 ._ x ,_3.12.2 A Lan \Ise Census shall be conducted and sha'll identify wi in a distanceof8k(ntx(5 miles)thelocationineachofthe16 meteor 41ogical sectorsofthenearestmilkanimal,thenearestresidence,anddhenearest - gardenof greater' han 50 m2 (500 ftz) producing broad Icaf 'egetation.APPLICABILITY: At al times. ACT10N:a. With a Land Use Cqnsus identifying a locati n(s) that yields a calculated dose or'd being calculated in\ose committnent Specification greater 4.11.2 than the to, pursuant values currently Specifica-tion 6.9.1.4. identify the new location',s) in the next Semiannual Radioactive Effluent Fiqease Report.b. WithaLandUseCensusthentifying location (s) that yields a calculated dose or dose commitmen via the same exposure pathway) 20*i; greater than at a location fpom which samples are currently being obtained in accordance wi h Specification 3.12.1, add the new slocation (s) within 30 days to he Radiological Environmental Moni-toring Program given in the CM. The sampling location (s), exclud-ing the control station lot tion, having the lowest calculated dose 4 or dose commitment (s), vi the\same exposure pathway, may be deleted from this monitoring pro am af ter October 31 of the year in which this Land Use Census wa conduc t'ed. Pursuant to 5pecification 6.14, submit in the next Se. annual Radioactive Effluent Release Report documentation for a tangeinthe\0DCMincludingarevisedfigure(s) and table (s) for tb ODCM reflecti'ng the new location (s) with informa-tion supporting th. change in sampljng locations.\c. The provisions Specification 3.0.1 are not applicable. ,\ \ \ \ \ \ \ 's N!Broad 1IfvegetationsamplingofatleastthreedifferentLindsofvegetation \may be performed at the SITE BOUNDARY in each of two different direction ( secto s with the highest predicted D/Qs in lieu of the garden' census. Speci-fic fions for broad leaf vegetation sampling in the REMP shall be followed, in. uding analysis of control samples. l SOUHMOXA5+ UNLILL4 3/4--12 ./ \ A11ACHMENT A2 /RAD 161051 cat [fulPONMf N1 At IDN110r.1h(; SI*HL'AE 3s11 / ( \ PAGE 35__0F .67 m 1EYLluELJgl! Plt % _ _ -_ _ - - ._ _ _ _ m4 _\ /4.12.2 1he tar Ulk Census shall be conducted at least once per 12,Aonths 4 using to-door that inf ormatioh4 surve,c, hat will or aerial survey, provide the best results, by consulting such as/au)ythorities, local agriculturg a door-as described in the ODCM. '1be results of the Land Use Census s%11 be included in the Annual Rediologica*. Erivtronmental Operating Report pursuant to - Specification (,.9.1.3./ , /x '/ / / / / / /l/ / -.ONETEEA5vVil15T F F 3/4 12 /\ /I Rt,010to;1c At [NvlRONMf tn At Mas 110R1rg, s 3/4.1233 IN1[RLABORATORY COMPARISON pR00RAn ATTACHMENiM ST Hl. AE 37il PAGE 26 0F $4-[L]1111110 0.13J 0110 LE1ESILO!!,_ _.__ . ._ ___.__ m 3.12.3 Analyses shall be performed on all radioactive rnaterials, sd plied as part of an Inn rlaboratory Com;)arison Progran that has been approyfd by the Commission, thahcorrespond to sam;)les required by the REMP. N 7 - APPLICABILITY: At 'all times. ACTION: '\a. With analyses n$t,t>eing perf onned as required, ove, report the corrective actions \talen to prevent a recurrence to the Comission in the Annual Radiole>qical Environmental Op6 rating Report pursuant to 5pecification 6.9.Dg x b. 1hc provisions of Specification 3.0.3 re not applicable, .N l 1 MRVCL L6!iE_EE0!!1REMi.N14 - 4.12.3 The Interlaboratory Comparison Pr ram s)1all be descritied in the 00CM A summary of the results obtained as pa I of the allove required Interlaboratory I Con:parison Program shall be included i theAnnualR2QologicalEnvironmental Operating Report pursuant to Spec i f ic ti on f>. 9.1. 3. (i x N,\ N s. hq.i - JiilH-lf KA5~ -UNils -1 6 P 3/4 12 MihCt4 MENT n .;L l ST HL AE 37//INSTRUMENTATION 0F 57 _ MSD _ 3/4.3.3.9 (NotUsed)k (/Ur tc)s 3/4.3.3.10 .HADitMC-HW tiQuiD EfttttNMMiiORiriG insiRtMENTAHON'Ihe radioactive liquid effluent instrumentation is providi.Mnitor ~and control, as applicable, the releases of radioactivCmaterials in liquid effluents during actual or potential release do liquid effluents. The Alarm /lrip Setpoints for thesa instetnhents shall be calculated and adjusted in accordance with the mJet odelgand parameters in the ODCM to ensure that the! alarm / trip wil cor prior to exceeding the limits of 10 CFR Part 20 The E ; OPERAB ' 4 and use of this instrumentation is consistent with the requiremerjlts t - encral Design Criteria 60 M, and u nf Annendiv A to-40-GR-PerHF. Ego (99lpp 3/4.3.3.11 A0Asi,d GASEG96 FMLEMEMONITORING INSTRUMENTATION W adiesttive gascava effiveni im b wwntotier is provided-to-meester end- - cendral, n ppliceble,-the uivmr Uf radieeet4w-matechit in nassous-*f44eents- d;H n; actual vi putential-releases ef geeeess-eMbentc. 'M Alam/irip-Seipoints -for these insti mwois shall bc c&kuleted end-adittsted-i6 eccuid66ce 4%-the "ithedelvyy driij poivictCT3 in t M 00Cu te in;uTC iMt the c lorT.1/t ri p Wi i P v u m .n r i n e + n egading 19 t imit; cf ;cifige,i 20. This instrumentation.41 a.includes provisions for inonitoring (and controlling) the concentrations of potentially explosive gas rnixtures in the GASEOUS WASTE PROCESSING SYSTEM. -he 40E4ABR%nd-uu-of-t44+-4fsteumentatinn h enns.htent-with the+equ-i-H. _ 0f GenecabDes-ign-friteria--00, - O,1tnd-64-iof4ppendix A iv iO-ffR-1 art-bft--lhe -.sen&4-t4vitymfnny noble pet-eetivity monitors used-te-dow-comi4 4ance-wHbthe passous-ef 4eent-+elea:.e requirmts nf <nnef fication 3.11.2.2 shall he teh 4irai concentrations u ivw e> 1+MJ-pC4/ce-erc eeasuretrte --3/4.3.4 TURB1NE OVfRSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control. valves are OPERABLE and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is rtquired since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related components, equipment, or structures. SOUTH TEXAS - UN115 1 6 2 B 3/4 3-f> TTIACHMEsfM ST HL AE 3r/l PAGE W . OF W,- 3/4.11 RA010AC11VE EfftVENTS( EASES- _ _ _ _ __ - ____ 3/4.11.1 tlQUID EFFLUENTS , 3/4.11.1.1 00NCENTRA110N - % Cl active m{)terials released in liquid waste effluents to UNRESIRICIE0 AREAS willth be less thhn the concentration levels specified in 10 CFR Part 20, Appendix B, lable 11. Column 2. This limitation provides additional assurance that the levels of radi stive materials in bodies of water in UNRESTRICTED AREAS will result in exposurbss within: (1) the $cction ll. A design-objectives of Appendix 1,10 CFR Phrt 50, to a MEMBLR Of THE PUBLIC, and (2) the limits of 10 CFR Part 20.U6(e)sto the population. The concentration limit for dissolved or entrained nob'le sghes is based upon the assumption that Xe-135 is the controlling radioisotope cnd its MPC in air (submersion) was converted to an equivalent concentrath itnater using the methods described in Inter-national Commission on Radiological' Protection (ICRP) Publication 2. s This specification applies to the rslease of radioactive matericls in liquid offluents from all units at the site. N~The required detectNn capabilities f or radioactive materials in liquid waste samples are tabulated in terms of the lower limits- of detection (LLDs). Detailed discussion of the LLO, and other detection limits ~can be found in HASL ( Procedures Manual, HASL-300 (revised annually), Currie, L. A. ,'" Limits for Qualitative Detection and Quantitative Determination - Application-to Radio-chemistrf," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K. , " Detection Limij s' for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Congiany Report ARH-SA-215 (June 1975). 3/4.11.1.2 DOSE' wch ,. N'INpecification Th is provided to implement the requirements of-Sit The. Limiting Condi-tions tion forll.Operatio A, 'll-lJ'n'and IV. A of Appendix I,10 CFR Part 50. implements the guides se The ACTION statements }irovide the required operating flexibility and at the same rth in Section IV. A of Appendix ! to assure that~time implement the releases the guides set'fp?ial of radioactive mate in liquid effluents to UNRESTRICTED AREAS s will be kept "as low as is reasonably'aciievable." t The dose calculation metho-dology and parameters in the 00CM implemerit'the requirements in Section Ill. A of Appendix ! that conformance with the guides of' Appendix ! be shown by calcula-tional procedures based on models and data, such th'atmthe actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substan-tially underestimated. -The equations specified in the 00CM for. calculating the doses due to the actual release rates of radioactive materials in' liquid efflu-ents are consistent with the methodology provided in Regulatory Guide 1,109," Calculation of Annu~al Doses to Man from Routine Releases of Reactor Effluents for the Purpose-of Evaluating Compliance with 10 CFR Part 50, Appendix 1" Revi-sion 1, October 1977 and Regulatory Guide 1.113. " Estimating Aquatic Dispersion/ of Ef fluents from Accidental and Routine Reactor Releases for the Purpose of \ Implementing Appendix 1," April 1977. SOUTH IEXAS - UNITS 1 & 2 8 3/4 11-1 . E Ti d iimta d R ST HL AE 3Yll RA"10AC11VE EFF LUENTS PAGE 3't 0F 57 ( Q!$ES _ ,_ . _ _ _ . _ _ . m_ DOSE ~(Continued k This-specification applies to the release of radioactive materials in liquid effluents from each-unit-at the-site. - 3/4.11.1.3 LIQUID WASTE- PROCESSING-SYSTEM - U#b j TheJPERABILITY of the Liquid Waste Processing System ensures that this system will'be available for use whenever liquid ef fluents require treatment prior to releasc'to, the environment. The requirement that the appropriate portions of this system be usedqhen specified provides assurance that-the releases of radioactivr. materials in'liqaid effluents will be kept "as' low as is reasonably achievable". This specification. implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10'tfR Part 50 and the design objective gNen in Section 11.0 of Appendix 1 to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Waste Processing System were specified as a_ suit'able fraction'of the dose design objectives set forth in Section 11. A of Appendix 1,10 CFR Part 50, for liquid ef fluents. This spec'5fication applies to the release of radioa'ctive materials in liquid liffluents from each unit at the site../3/4.11.1.4 tlQUID HotDUP T ANKS { The tanks covered by this specification include all those outdoor l radwaste tanks that are not surrounded by liners, dikes, or walls capable of i holding the tank contents and that do not have tank overflows and surrounding I area drains connected to the liquid Waste Processing System. Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in 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 B, Table 11, Column 2, at the nearest potable water supply and the nearest surf ace water supply in an UNRESTRICIED AREA. 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOCE RATE- C+ This specification is provided to ensure that the dose.at any time at and beyond the ST1E-BOUNDARY from gaseous effluents from all" units on the site will be within the annual dose limits of 10 CFR_Part 20 to UNRESTRICIED AREAS. The annual dose limits are the' doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table ll7 Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a HEMBER OF 1HE PUBLIC'in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual' average concentrations exceeding the Aiiiiits specified in Appendix B, Table 11 of'10 CFR Part 20 (10 CFR Perf 20.106(b)). For MEMBERS OF THE PUBLIC who may at times be within [ / SOUlH TEXAS - UWITS 1 & 2 B 3/4 11-2 Unit 1 - Amendment No. 4 ATIACHMENT4 ST.HL AE-32// RAD 10AC11VE EfflUEN15 PAGE 40 0F 9 (- BASlk - _ _ _ _ _ - - , _ _ _ _ _ l-DOSE ~ RATE (Continued)-- .ttbSITE BOUNDARY, the occupancy of that MEMBER Of THE PUBLIC will usually be suf ficiently low to compensate for any increase in the atmospheric diffusionf actor aboilesthat for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE'PUDLIC, with the appropriate occupancy factors, shall be given in the 00CM. The'specified release rate limits restrict, at all times, the corresponding gamma'and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to-less thin or, equal to 500 mrems/ year to the whole body or to less than or equal to 3000 mrems/ year to the skin.These release rate limits also restrict, at all times the corresponding thyroid dose rate above bacicground to b child via the inhalation pathway to less than or equal to 1500 mrems/ year. This specification applies to (he(release of radioactive materials in gaseous effluents from all units at the site. The required detection capabilities for' radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection' limits can be found in HASL Procedures Mari,ual, HASL-300 (revised annually), Currie, L. A. , " Limits f or Qualitative' Detection and Quantitative Determination -- Application to Radio-chemistry,VAnal. Chem. 40, 586-93 (1968), and Hartwell, J.L , " Detection (- Limits-for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Compsny Report ARH-SA-215 (Jure 1975). 3/4.11.2.2 DOSE --NOBLE-GASES- hed du Mis specification is provided to implement the requirements ofJec'tions 11.0, IlhA and IV. A of Appendix I,10 CFR Part 50. The Limiting C6ndition for Operatior(implements the guides set forth in Section ll.B of Appendix 1. The AC110N statements provide the required operating flexibility and at the same time implemerit s the guides set forth in Section IV;A of Appendix 1 to assure that the releases of radioactive material inbsecas effluents to UNRESTRICTED AREAS will'be_ kept "as low as is .. reasonably achievable." The Surveillance Requirements implement the requirements in Section Ill. A of Appendix ! that confomance wlthsthe guides of Appendix I be shown by calcula-tional procedures based on models'apd data such that the actual exposure of a MEMBER OF THE PUBLIC through appropr' tate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parametert established in the ODCM for calculating the doses due tos the actual release rates of radioactive materials in liquid effluents are' consistent with the methodology provided in Regulatory Guide 1.109, " Calculation 'of Annual Doses to Man from Routine Releases of Reactor Ef fluents fr,r the Purpose'of Evaluating Compliance with 10 CFR Part.50, Appendix 1" Revision 1, October 1977 and Regulatory beide 1.111, 'l Methods for Estimating Atmospheric Transport'and Dispersion of Gaseous Ef fluents in Routine Releases f rom Light-Water Cooled' Reactors," Revisun,1'" July 1977. The ODCM equations provided for determining the air [ doses at' and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. SOUTH lEXA5 - UNITS 1 & 2 8 3/4 11-3 . EilAdiidETd ' Smit.AE 3M// RAD 10AC11VE EfftVEN15 L PAGE 1L._0F 57 -)( B AS EL_._.___ _ _ _ __.._.___- -- _-'lhirspecification-applies to the release of radioactive inaterials in gaseous effluents from each unit at the site.-( Uci &:<, & 3/4.11.2.3 DOSE - 10 DINE 131,-10 DINE-133,- TR111tlH,- AND RAD 10 ACTIVE MA1ERIAL - ' IN- PARTICUL ATE- FORM - l s / Thibsgecification is provided to implement the requirements of Sections ll.C. lli.A and IV.A of Appendix 1, 10 CfR Part ?O. The Liuiting Conditions for Operation' ate the guides set forth in Section ll.C of Appendix I/ The ACilDN statements' provide the required operating flexibility and at'the same time implement the guides set forth in Section IV. A of Appendix,l'to assure that the releases of radioactive materials in gaseous ef fluents' to UNRE51RIC1ED AREAS will be tept "as lows as is reasonably achievable." 1be'00CH calculational methods specified in the Surveillance Requirements implement the requirements in Section Ill. A of Appendix Isthat conformance with the' guides of Appe'idix ! be shown by calculational procedures based on nodels and data, such that the actual exposure of a HEMBER Of THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated, lho DDCH calculational methodology and parameters for calculating the doses due to'the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses'io Man f rom Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for (.. Estimating Atmospheric Transport and Dispersion.of Gaseous Ef fluents in Routine Releases f rom Light-Water-Cooled Reactors," Revision 1, July 1977. These equa-tions also provide for determining the actual doses based upon the historical average atmospheric conditions.' The release rate specifications for lodine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the 511E BOUNDARY. The pathways that were examined in the development of these calculations were: (1) individual inhalation of air-borne radionuclides .(2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat > producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure to man. This specification applies to the release of radioactive materials'ip gaseous effluents from each unit at the site. N\\3/4.11.2.4 GASEOUS-WASTE PROCESSING 5YSTEM dM j ThEOPERABILITY of the GASE0US WA51E PROCE551HG SYS1EM ensures that'the systems will be'available for use whenever gaseous effluents. require treatment prior to release to'the environment.s The requirement that the appropriate por-tions of these systems bPused, when specified, provides reasonable assurance that the releases of radioactTve materials ~ in gaseous effluents will b'e kept "as low as is reasonably achievablie"Alhis specification implements the re-quirements of 10 Cf R 50.36a, General Des @n-CrJterion 60 of Appendix A to 10/ CFR Part 50 and the design objectives given in Section 11.0 of Appendix ! to l( 10 CFR Part 50. The specified limits governirg the use'ofs appropriate portions SOUlH IEXA5 - UNil5 1 6 2 B 3/4 11-4 Unit 1 - Amendment No. 4 i i' 3FTACHM55fR ST HL AE- M //-- PAGE %? 0F 57 RA010ACllVE EFFLUEN15( , M 5E L_ _ .-____m____m______ m _ CASEOUS-WASTE PROCf 551NG SY51tM pntinued)- , of the system'verc.specified as a sdte'e 'raction of the dose design objec-tives set forth in Sectiortll.B and ll.C ci ' m ndix 1, 20 CfR Part 50, for ~ gaseous effluents. This specification applies to the release of r , '.G: a materials in gaseous effluents from each unit at the site. . 3/4.11.2.5 EXPl051VE GAS HlXTURE lhis specification is provided to ensure that the oncentration of poten-tially explosive gas mixtures contained in the CASE 0V5 V151E PROCESSING sis 1EM is maintained below the flammability limit of oxygen. lhe concentration of oxygen in the inlet header to the GASEOUS WA51L PROCE5*dNG SYSTEM is contin-uously monitored and a high level alarm isolates the GASEOUS WA51E PROCESSING SYSTEM. Provision is made to manually purge the system with nitrogen and/or isolate the source of oxygen. Maintaining the concentration of oxygen below its flammability limit (4% by volume) provides assurance that the releases of radioattive materials will be controlled in conformance with the requirementi of General Design Criterion 60 of Appendix A to 10 CFR Part 50. Because of analyzer variabilities, a safety margin of 1% by volume is applied. Therefore, the limiting condition for operation is maintaining oxygen concentration below 3% by volume. 3/4.11.2.6 GAS STORAGE TANKS i' The tant s included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification. Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled releace of the tank's contents, the resulting whole body exposure to a MEMBER Of THE i JBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem. This is consisters with Standard Review Plan 11.3, Branch Technical Position ETSB 11-5, "Postub.ted Radioactive Releases Due to a Waste Gas System teak or failure," in NUREG-0800, July 1981. Since only the gamma body dose factor (DFBg ) is used in the analysis, iba Xe-133 equivalent is determined from the DfB4 value for Xe-133 as compared to the composite OfB; for the actual mixture in the tank. ( 50U111 TEXA5 - UN.'TS 1 & 2 B 3/4 31-5 . 3 CHMENT R T ST HL A 3gn O RADIOACTIVE Efft0ENTS-- - 0F1S7 BMLS __3/4.11.3 40EiD-RAD 1DACTIVE-VA51ES- h) &^This specification i ents the requirements-of"10 CFR.50.36a and General' Design Criterion 60 of Appendix % to 10 CFR'Part 50. The process parameters ..included in. establishing the PROCESS (CONTROL PROGRAM may include, but are not limited to, waste type,-waste pH, wast)/ liquid / SOLIDIFICATION agent / catalyst , ratios,-wasteAll' content, vaste principaDchemical constituents, and mixing and, curing' times. \ MM 3/4.11.4 -TOTAL-DOSE- [D-This sMification is provided to meet the dose limitations of,40 CFR Part 190 that ha e been incorporated into 10 CFR Part 20 by 46 FR48525. The.specification. rcqt ires the preparation and submittal. of a- Speci Al Report when-ever the calculatedNoses due to releases of radioactivity-ahd to radiation from uranium fuel cycle soDrges exceed 25 mrems to the whole, body or any organ, except the thyroid, which shali\pe-limited.to less than or eqDal to 75 mrems. For sites containing up to four reactors, it is highlygu'nlikely that the resultant idose to a MEMBER OF THE PUB'llt will exceed the dose limits of 40 CFR Part 190-.if'the individual reactors rdmain~ within twice the dose design objectives of Appendix I, and -if-direct radi'dtion doses f1m the reactor units and outside storage tanks are kept small. The Special'keport will describe a course of =/ action that:should result in the lhnitation of the annual dose to a MEMBER OF '( THE PUBLIC to within the 40 CFR Pad \,190' limits. For the purposes of the ;Special Report, it may be assumed thatxthe dose commitment to the MEMBER of the PUBLIC from other uranium fueldyc1'e s sources 1s negligible, with the 1exception that dose contributionsf from other nuclear fuel cycle facilities at l~ the same site-or within a ;radiui of 8 km mUst be considered. If-the dose to.any MEMBER OF THE.PUBLIC is estimated to exc'eed x the requirements of 40 CFR - Part.190,Lthe Special Report' with a request foNa variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected),'in' accordance with the provisions \qf 40 CFR 190.11 and 10.CfR 20.405c, is considered to be 'a timely request and fulf, ills the requireiaents of 40 CFR Part 190 until NRC staff action is completed. The variance only. relates to the limits of,40 CfR Part 190, and does act apply in a'nysway to the other requirements fot! dose limitation of 10 CFR 1 art 20, as addressed in Specifi- -cations 3.11.1.1~ and 3.11.2.1. . An'indivi4a1 is 90t considere'd a MEMBER s OF THE PUBLIC during any period in which he/she is engaged in carrying out any operatio" that is;part of the nuclear fuel cycle. N t /}s SOUTH TEXAS - UNITi 1 & 2 83/411-6 I'\' _.3/h,12 RADIOLOGICAL ENVIRONMENTAL MONITORING ATTACHMENT A4 ST-HL-AE-3 [- \ PAGE ._% r // /.0F 57 MSi$ 3/4.12.1 NONITORINGPROGRAM x . The Radiological Environmental Monitoring Program required .by this specification provides representative measurements of radiation'and of radio-active materials ht those exposure pathways and for those radionuclides that ' lead to the highest' potential radiation exposure of HEMBERS OF THE PUBLIC resulting from the plant operation. This aionitoring program implements Sec-tion IV.B.2 of Appendik I to 10 CfR Part 50 and thereby supplements the Radio-logical Effluent MonitoHng Program by verifying'that the measurable concentra-tions of radioactive materials and levels of radiation /sre not higher than ! expected on the basis of the effluent measurements and the modeling of the ! environmental exposure pathkays. Guidance for this monitoring program is pro- I vided by the Radiological Assessment Branch Technical Position on Environmental j Monitoring. The initially specified monitoring program will be ef fective for ' at least the first 3 years of commercial operation. Following this period, ' program changes may be initiated based on operational experienca. The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by the ODCM are considered optimum for. routine environmental meat uren.ents in industrial laboratories. It should be' recognized that the LLD n defin7d as an a priori (before the fact) limit repr'esenting the capability of a measure-ment system and not as an a posteriori'(after the fact) limit for a particular measurement. Detailed discussion of the LLD, and oth r\ detection limits, can be found ' in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A. , " Limits l. for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K. , " Detection Limits for Radioanalytical Counting Yechniques" At'lantic Richfield Hanford Company Report ARH-SA-215 (June 1975). \ 3/4.12.2 LAND USE CENSUS This specification is provided to ensure that chanhes in the use of areas at and beyond the SITE B0UNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in thex00CM are made if required by the results of this census. The best informati'on from the door-to-door survey, from aerial survey or from consulting with local agricultural s authorities shall be used. This census satisfies the requirements of Sec-tion IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the sensus to gardens of greater than 50 s8 provides assurance that signifi~ ant c expo.ure pathways via leafy vegetables will be identified and monitored since a garden of this size is the m,inimum required to produce the quantity (26 kg/ year) of leafy vege-tables assumed in Regulatory Guide 1.109 for consumption by a child.1 To deter-mine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e. , similar 'to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2, (--SOUTH-TEXAS v UND S' & 2- -B 3/L 12-1 .\x RADIOLOGICAL ENVIRONMENTAL HONITORING Ai'fACFifdNi/1A ST HL AE 22/i PAGE 45 0Fd2._ (.x (;c y x BMis __ , 3/4.12.3 INTERLABORAT0iY' COMPARISON PROGRAM l The requirement for parti ipation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and . accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environ-mental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50. -,. 1 ll I _( ('~_5OUTH- TEXA5 - UN]TS 1 & 2 - B 3/4-12-2 Un i t 1 - AT,endmen t No . 4-e - ATTACHMENT A'L TMti1ELRAUVLCON1 ROLE _ _, _ PROCEDURES AND PROGRAMS (Eontinued)e. Accident Monitoring Instrumentation A program which will ensure the capability to inonitor plant variables and systems operating status during ano following an accident. This program shall include those instruments provided to indicate system .operating status and furnish information regarding the release of radioactive materials (Category 2 and 3 instrumentation as defined in Regulatory Guide 1.97, Revision 2) and provide the following:1) Preventive maintenance and periodic surveillance of instrumen-tation, 2) Pre plaaned operating procedures and backup instrumentation to be used if one or more monitoring instruments become inoperable, and 3) Administrative procedures for returning inoperable instruments lgg to OPERABLE status as soon as practicable. 3 6.9 REPORTING REO,UIREMENTS ROUTINE REPORTS e 6.9.1 In addi'. ion to the applicable reporting requirements of Title 10, Code y~~ of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted. STARTUP REF0El 6.9.1.1 A summary report of plant startup and power escalation testing shall be subnitted 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 manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit. The Startup Report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or che teristics obtained during the test program and a comparison of these values witn 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 condi-tions based on other commitments shall be included in this report. Startup Reports shall be submitted within: (3) 90 days following completion of the Startup Test Program, (2) 90 days following resumption or commencement of commercial 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 commencement of commercial operation), supplementary reports shall be sub-mitted at least every 3 months until all three events have been completed. SOUTH TEUS - UNITS 1 & 2 6-16 B -PROCiDURES-AND- PROGRAMS--- Z'A)SFA?T 3 ~ l l &871he following programs shall be established,-implemented. -and maintained: 4 Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive ef fluents and for maintaining the doses to MEMBERS Or THE PUBLIC from radioactive effluents as low as reasonably achievtLie. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall in-clude remedial actions to be taken whenever the program limits are exceeded, The program shall include the following elements:1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and set- 'point determination in accordance with the methodology in the ODCM,2) Limitations on the concentrations of radioactive material released in liquid ef fluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2, 3) Monitoring, sampling, and analysis of radioactive liquid and gaseous ef fluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM, 4) Limitations on the annual and quarterly doses or dose coemitment to a MEMBER Of THE PUBLIC from radioactive materials in liquid ef fluents released from each unit to UNRESTRICTED AREAS conform-ing to Appendix I to 10 CFR Part 50, 5) Determination of cumulative and projected dose contributions j f rom radioactive ef fluents for the current calendar quarter and i current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6) Limitations on the caerability and use of the liquid and gaseous ef fluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radio-activity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix 1 to 10 CFR Part 50, 7) Limitations on the dose rate resulting fro'm radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B Table II, Column 1, I ATTACHMENT A 1 ST HL- E-32/ /PAGE 7._ 0F G.y 51 ADMINISTRATIVE CONTROLS ATTACHMENT AR 6.8.4 Radioactive Ef fluent Controls Program (Cont. ) gq7 Hf E8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous ef fluents f rom each unit to areas beyond the SITE BOUNDARY conforming to Appendix 1 to 10 CFR Part 50, 9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC fr.s f odine-131, lodine-133, tritium, and all radio-nuclides in pac V,culate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix 1 to 10 CFR Part 50, 3ns mitot ,;z ca ;cnting m,d pui ging uf-y.c F,a i i 11 cuniarnmt7rt-e r c e g' t he--5 Lan uoy G a>-ire e me nt 5y> tem to mainiaii i c hmA + b n renonetdy achiedh (SWh w/ Mark !! c^^tain'ents), ~u.e .10 EI) OF Limitations on the annual dose or dose commitment to any MEMBER THE PUBLIC due to releases of radioactivity and to radiation frc uranium fuel cycle sources conforming to 40 CFR Part 190.];[.RadiologicalEnvironmentalMonitoringProgram A program shall be provided to monitor the radiation and radio-nuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental expo-sure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following: l1) Monitoring, sampling, analyhis, and reporting of radiation and radionuclides in the environment in accordance with the method-ology and parameters in the ODCM, 2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifica-tions to the monitoring program are made if required by tht results of this census, and i 3) Participation in a Interlaboratory Comparison' Program to ensure that independent .; hecks on the trecision and accuracy of the measurements ef radioactive materials in environmental sample matrices e e performed as part of the quality assurance pro-gram for environmental monitoring.V9 The n m T Au weW. we oes tmm em,LD Mw'% Pren,, & ek ,v.m,g*podec/y.r.<= M kgn Md bd 613 % A,M,'=mmedhuuht'v"*W' Jg u.,/6y g. Apgg ,g y , p ', 4 ekM.Aa cMid M M obc 4 MkL') hMe D', S,*2 j MI,$,3p@ U.C f /Q 1fg y ! lc>c pct ib & S o g L ADMINISTRAT1YLt0RTROLS i m % nmtNT E3 D I-M L- At- TP / / l ANNUAL REPORTS * - _ . PAGE_ W 0F S7 6.9.1.2 Annual Reports covering the adivities of the unit as described below for the previous calendar year shall be sebmitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality. Reports required on an annual basis shall include:a. A tabulation on an annual basis of the number of station, utility, and other personnsi (including contractors) receiving exposures greater than 100 mrem /yr and their associated man-rem exposure according to work ind job functions ** (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance [ describe mairitenance), waste processing, and refueling).The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. Small exposures totalling less than 20% of che individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole-body dose received from external sources should be assigned to specific major work functions; andb. The results of specific activity analyses in which the primary ,coolant exceeded the limits of Specification 3.4.8. The following l information shall be included: (1) Reactor power history starting l 48 hours prior to the first sample in which the limit was exceeded l (in graphic and tabular format); (2) Results of the last isotopic ' analysis for radiciodine performed prior to exceeding the limit, l results of analysis while limit was exceeded and results of one j analysis after the radioiodine activity was reduced to less than ' limit. Each result should include date and time of sampling and the radiciodine concentrations; (3) Clean-up flow history starting ! 48 hours prior to the first sample in which the limit was exceeded; ! (4) Graph of the I-131 concentration (pCi/gm) and one other radioidine isotope concentration (pCi/gm) as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant l exceeded the radiciodine limit. { ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORTl l6. 9.1. 3 Routine Annual Radiological Environmental Operating Reports covering i the operation of the unit during the previous calendar year shall be submitted prior to May 1 of.each year. gThehitiel iew i shell be smit 1.ea priv, to ~diay 1-OFthe 3eer fullv ing i i ici criticelitr. 3 MhsAnnual ram elegical En"irer.mer.t:1 Operating Repvrts shali incluae ~ summaric';, interpetetiom , cr.d an anol,ysis vi Li cie of the restdtt-ef-the - r.adiningical_envi rnnme nt al sur-ve4Mance-ac-tiv4t4es - f u r the report perivd,-*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. **This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.SOUTH TEXA5 - UNIT 51 & 2 6-17 as I l.. l l ATTACHMENT A3' REVISED OFFSITE DOSE CALCULATION-l. MANUAL INCORPORATING RETS-l.J l l I ', i I l r ,.: l .-!. A1/003.N13-~ AUACHMENT A 3 ST.HL-AE-31/I PAGE__l Op 100 0FF-SITE DOSE CALCULATION MANUAL (ODCM)SOUTil TEXAS PROJECT ELECTRIC GENERATING STATI0h Revision 4 NL.89.087.01.R4 Rev. 4 ATTACHMENI A 3 ST HL AE 3F// PAGE D OF /00 PREFACE The South Texas Project Electric Generating Station (STPEGS) Off-site Dose Calculation Manual (ODCM) is divided into two parts: (1) the in-plant radiological effluent monitoring program requirements for 11guld and gas sampling and analysis, along with the radiological environmental monitoring program requirements (PART A): and (2) approved methods to determine effluent monitor setpoint values and estimates of doses and radionuclide concentrations occurring beyond the boundaries of the etation resulting from noimal station operation (PART B). The Sampling and analysis programs in PART A provide the inputs for the models of PART B in order to calculate off-site doses and radionuclide concentrations necessary to determine compliance with the dose and concentration requirement of PART A of the ODCM. The radiological environmental monitoring required by PART A and outlined within the manual provides the means to determine that measurable concentrations of radioactive materials released as a result of the operation of STPEGS are not significantly higher than expected. Changes to the ODCM shall be performed in accordance with Technical Specifitation 6.14. NL.89.087.01.R4 i Rev. 4 ATTACHMENT 4 3 ST HLA, E-37 //~PAGE T OF /0 o l TABLE OF CONTENTS ?*E*PREFACE 1 LIST OF EFFECTIVE PAGES REFERENCES 89 LIST OF FIGURES LIST OF TABLES 6 FART As RADIOLOGICAL EFFLUENT MONITORING PROGRAMS Section 1.0 Definitions 11 2.0 Responsibilities for Part A 17 3.0 and 4.0 Controls and Surveillance Requirements 18 3/4.3.3.3.10 Radioactive Liquid Effluent Monitoring Instrumentation 21 3/4.3.3.3.11 Radioactive Gaseous Effluent Monitoring Instrumentation 27 3/4.11.1 Liquid Effluents 33 3/4.11.1.2 Dose 39 3/4.11.1.3 Liquid Vaste Processing System 41 3 /4. '.1. 2.1 Gaseous Effluents 43 3/4.11.2.2 Dose-Noble Gases 49 3/4.11.2.3 Dose-Iodine 131, 133, Tritium, and Radioactive Material in Particulate Form 51 NL.89.087.01.P4 2 Rev. 4~- ._- _ ~ATTACHMENT A3 ST HL-AE-M/ / I PAGE 4 0F 1Q10_ i TABLE OF CONTENTS (cont'd) M 53 3/4.11.2.4 Gaseous Waste Processing System 3/4.11.4 Total Dose 55 3/4.12.1 Radiological Environmental Monitoring 58 Land Use Census 73 3/4.12.2 77 3/4.12.3 Interlaboratory Comparison Program BASES For Section 3.0 and 4.0, Controls and Surveillance Requirements 79 5.0 Design Features 89 6.0 Administrative Controls 95 PART B RADIOLOGICAL CALCULATIONAL METHODS AND PARAMETERS Section 1.0 Introduction 1.1 Purpose B1-1 1.2 General Site Description B1-2 2.0 Summary of Release Points and Detector System 2.1 Gaseous Release Points B2-1 2.2 Liquid Release Points B2-1 2.3 Detector System and Inetrument Responses B2-2 3.0 Alarm Setpoint Adj us tmenti 3.1 Liquid Effluents B3-1 3.2 Gaseous Effluents B3-5 NL.89.087.01.R4 3 Rev. 4~ATTACHMENT 4'3 ST HL-AE 32// l PAGE As 0F /0 0 TABLE OF CONTENTS (cont'd) Page 4.0 Offsite Dose Calculations 4.1 Liquid Releases B4-1 4.2 Liquid Exposure Dose Model B4-1 4.3 Gaseous Releases B4-6 4.4 Gaseous Dose Models and Dose Formulas B4-8 4.5 Control 3.11.1.3 B4-13 4.6 Control 3.11.2.4 B4-14 4.7 Control 3.11.4 Dose Calculations B4-14 4.8 Dose to Hembers of the Public On-Site B4-15 Appendix to Part B, Section 4 Model of the Release of Radioactive Materials From the STPEGS Reservoir for Use in Off-Site Dose Calculations B4-26 5.0 Radiological Environmental Monitoring Program 5.1 Program Summary B5-1 5.2 Sampling Program Description B5-2 5.3 Sampling Frequency B5-4 5.4 Sample Station Locations B5-4 5.5 Quality Control B5-4 5.6 Analytical Sensitivity B5-4 5.7 Data Presentation B5-4 5.8 Routine Reporting Requirements B5-5 NL.89.087.01.R4 4 Rev. 4 ATTACHMENT 41 ST HL-AE-39// PAGE_ L OF /00 LIST OF FIGURES _ , _ _ ?*L*Figure B2-1: Unit Ventilation System B2-4 Figure 32-2: Turbine Building ventilation System B2-5 Figure B2-3: Energy Responses _ Curve for the RD-52 j Offlino Beta Detector Operating at 760 mm Hg and 25 C B2-6 Figure h2-4: RD-56 Particulate Detector Energy Response to Betas B2-7 Figure B2-5: Detector Energy Response to Gamma Radiation fer RD-53 Offline Gamma Detector B2-8 Figure Bo-1: Lower Colorado River Area B4-30 Figure B4-2: STPEGS Site B4-31 l l NL.89.087.01.R4 5 Rev. 4 _ . _ _ _ATTACHliENT'43 ST-HL-AE-32/ / PART A PAGE 7 0F loo -- LIST OF TAILES Number Pm Table 1.1: Frequency Notation 15 Table 1.2: Operational Modes 16 Table A3-1: Radioactive Liquid Varte Sampling & Analysis Program 36 Table A4-1: Radioactive Gaseous Vaste Sampling & Analysis Program 48 Table AS-1: Radiological Environmental Monitoring Program 62 Table A5-2: Detection Capabilities For Environmental Sample Analysis 69 Table A5-3: Reporting Levels For Radioactivity Concentration in Environmental Samples 72 PART B LIST OF TABLES Number Pm Table B3-1: Liquid Release Detector, RD-53, Response to I uCi/ml of Each Nuclide B3-11 Table B3-2: Noble Gas Detector, RD-52, Response to 1 uCi/cc of Each Nuclide B3-13 Table B3-3: Noble Gas Detector, RD-52, Response to Single Nuclide B3-16 Table B4-1: Radionuclide Fractions Leaving STPEGS Via Liquid Routes B4-16 Table B4-2: Liquid Dose Pathway Factor Description B4-18 Table B4-3: Liquid Parameter Values f or Equations 4.2a and 4.2b B4-19 NL.89.087.01.R4 6 Rev. 4 ATTACHMENT /13 ST-HL AE 37// i__-PAGE__9 __; op _-joo l List of Tables (cont'd) Page Table B4-4: Particle Depiction and Deposition Factors for Ground Level Releases B4-20 Table B4-5:~ Gaseous Dose Pathway Factor Description B4-21 Table B4-6: Gaseous Parameters Values for Equatione 4.4j to 4.40 B4-22 Table B4 Pathway Dose Factors B4-23 Table B5-1: Minimum Operational Radiological Environmental Monitoring Program B5-6 Table B5-2: Sample Station Locations B5-11 NL.89.087.01.R4 7 Rev. 4 i- ? ATTACHMENT A3 ST-HL AE 32// PAGE 9 0F / N REFERENCES r1. Curie, L. A., " Limits for Quantitative Detection and Quantitative- Determination-Application to Radiochemistry," Analytical Chem, 40, 1968.2. G. A. Technologies, " Calibration Report for Model RD-53 Offline Gamma Detector with 1.5-inch Diameter by 1-inch Thick Nal(TL) Crystal," G. A.Technologies Report E-115-904, June 1980.3. G. A. Technologies, " Calibration Report for Model RD-52 Offline Beta Detector," G. A. Technologies Report E-115-647, October 1984. 4. G. A. Technologies, " Calibration Report For Model RD-56 Moving-Filter Particulate Detector," G. A. Technolcgies Report E-115-789, Sept. 1980. 5. G. A. Technologies, "RM-21A Computational Models and Algorithms," G. A.Technologies Report E-115-1241, June 1984.6. Health and Safety Laboratory, "HASL Procedures Manual, "HASL-300, National Technical Information Service. 7. Houston Lighting and Power Company, " Updated Final Safety Analysis Report, South Texas Proj ect , Units 1 and 2, Rev. 1. 8. Houston Lighting and Power Company, " Environmental Report Operating License Stage, South Texas Proj ect, Units 1 and 2," Feb. 1979. 9. Houston Lighting and Power Company, " Operating Technical Specifications for the South Texas Project Electric Generating Station," June 1985. 10. Title 10 Code of Federal Regulations, Parts 20 and 50, Office of the Federal Register, Jan. 1984. 11. U. S. Nuclear Regulatory Commission, " Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents For the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," USNRC Regulatory Guido 1.109, Rev. 1, Oct. 1977. 12. U. S. Nuclear Regulatory Commission, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Vater-Cooled Reactors," USNRC Regulatory Guide 1.111, Rev. 1, July 1977. 13. U. S. Nuclear Regulatory Commission, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," USNRC Regulatory Guide 1.113, Rev. 1, April 1977.NL.89.087.01.R4 8 Rev. 4 1 d ATTACHMENT A3 ST-HL AE-39// PAGE lo 0F AJo14. .U. S Nuclear Regulatory Commission. " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," USNRC NUREG-0133, Oct. 1978. 15. U. S. Nuclear Regulatory Commission, " Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors," USNRC NUREG-0472, Rev. 3, Jan. 1983, 16. U. S. Nuclear Regulatory Commission, " User's Guide to GASPAR Code,"USNRC NUREG-0597, June 1980.17. Wyle Laboratories, " Ingestion Pathway Data to Support Annual Dose Calculations for the Scuth Texas Project Electric Generating Station,"Vyle Research Report VR 84-34, July 1984.18. U. S. Nuclear Regulatory Commission " Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controla Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual nr to the Process Control Program (Generic Letter 89-01).NL.89.087.01.R4 9 Rev. 4 ATTACHMENT A 3 ST-HL-AE 32// I' ART A l PME : / / OF /0 0 RADIOLOGICAL EFFLUENT MONITORING PROGRAMS1.0 INTRODUCTIONThe purpose of Part A of the ODCM (Off-Site Dose Calculation Manual) is to describe the sampling and analysis programs conducted by STPEGS which provide input _to the models in Part B for calculating liquid and gaseous effluent concentrations, monitor setpoints, and off-site doses. The results of Part B calculations are used to determine compliance with the concentration and dose requirements of Part A. The minimum Radiological Environmental Monitoring Program required is described in Part A. The. current sampling station locations as well as the details of the current sampling program implementation and philosophy appear in Part B. The.information obtained from the Radiological Environmental Monitoring Program provides data which may allow evaluation of the relationship between quantities of radioactive materials released in effluents and-resultant radiation doses to individuals from principal pathways of exposure. -The data developed in the surveillance and monitoring programs described in Part A to the ODCM provide a means to confirm that measurable ( concentrations of radioactive materials released as a result of STPEGS operations are not significantly higher than' expected based on the models in Part B. I' I l L NL.89.087.01.R4 10 Rev. 4 l- E ATTACHIAENT A3 ST-HL AE 37// - PAGE__/3 . 0F 100 i SECTION 1.0 DEFINITIONS NL.89.087.01.R4 11 Rev. 4 ATTACfDAENT A3 ST HL AE 3s// 1.0 DEFINITIONS PAGE_ n -- 0 F 1 0 0 _ l The defined terms of this section appear in capitalized type and are applicable through these Controls. ACTION 1.1 ACTION shall be that part of a Control that prescribes remedial measures required under designated conditions. ANALOG CHANNEL OPERATIONAL TEST 1.2 Ar. ANALOG CHANNEL OPERATION TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock and/or trip functions. The ANALOG CHANNEL OPERATIONAL TEST shall include adj us tment s , as necessary, of the alarm, interlock and/or Trip Setpoints so that the Setpoints are within the required range and accuracy. CHANNEL CALIBRATION 1.3 A CHANNEL CALIBRATION shall be the adj ustment , as necessary, of the channel so that it responda within the required range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock, and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated. CHANNEL CHECK 1.4 A CHANNEL CHECK shall be the qualitative assessment of channel behavier during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status witt other indication and/or status derived from independent instrument channels measuring the same parameter. DOSE EQUIVALENT I-131 1.5 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 of NRC Regulatory Guide 1.109, Revision 1, October 1977. FREQUENCY NOTATION 1.6 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1, NL.89.087.01.R4 12 Rev. 4 l ATT ACHIAENT A 3 ST-HL AE-3f D DEFINITIONS 0F _ /00 PAGE_14 GASEOUS WASTE PROCESSING SYSTEM 1.7 A GASEOUS VASTE PROCESSING SYSTEM shall be muy system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. MEMBER (S) OF THE PUBLIC 1.8 MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its' contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant. OFFSITE DOSE CALCULATION MANUAL 1.9 The OFFSITE DOSE CALCULATION MANUAL (ODCM) contains the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual' Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports re auired by Technical Specifications 6.9.1.3 and 6.9.1.4. OPERABLE - OPERABILITY 1.10 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s). OPERATIONAL MODE - MODE 1.11 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2. l NL.89.087.01.R4 13 Rev. 4 ATTACHMENT A3 ST HL Ag-32/l DEFINITIONS-- i PURCE - PURGING-1.12 FJRGE or PURGING shall be any controlled process of discharging . *a or go; from a confinement to maintain temperature, pressure, humidity, concent ;eava we other operating condition, in such a manner that replacement air or gas is required to purify the confinement.RATED THERMAL POWER 1.13 RATED-THERMAL POWER shall be a total reactor core heat transfer l rate to the reactor coolant of 3800 MWt. l REPORTABLE EVENT 1.14 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10CFR Part 50. SITE BOUNDARY 1.15 The SITE BOUNDARY ahall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. SOURCE CHECK 1.16 A SOURCE CHECK shall be the qualitative assessment of channel i response when the channel sensor is exposed to a source of increased radioactivity. THERMAL POWER 1.17 THERMAL POWER shall be the total reactor core heat transfer rate , -to the reactor coolant. l l UNRESTRICTED AREA l 1.18 An UNRESTRICTED AREA shall be any area at or beyond.the SITE p BOUNDARY access to which is not controlled by the licensee for L purposes of protection of individuals from exposure to radiation l- and radioactive materials, or any area within the SITE BOUNDARY l used for residential quarters or for industrial, commercial,. Institutional, and/or recreational purposes.VENTING 1.19 VERTING shall be the controlled process of discharging. air or gas l from a confinement to maintain temperature, pressure, humidity, l concentration, or other operating condition, in such a manner L that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process. L I NL.89.087.01.R4 14 Rev. 4 h ATTACHMENT A 3 ST-HL AE 37/I TABLE 1.1 ' - PAGE_lb - 0F ~100 FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours D At leact once per 24 hours W At least once per 7 days. H At least once per 31 days. Q At least once per 92 days. SA At least once per 184 days. R At least once per 18 months. S/U Prior to each reactor startup. N.A. Not applicable. P Completed prior to each release NL.89.087.01.R4 15 Rev. 4 i - e . ATTACHMENT A 3 ST HL-AE 3tli PAGE 17 0F 100 TABLE 1.2 OPERATIONAL MODES REACTIVITY I RATED AVERAGE COOLANT MODE CONDITION, K,gg THERMAL POWERTEMPERATURE1. POWER OPERATION >0.99 > 5% > 350 F 2. STARTUP >0.99 1 5% > 350 F 3. HOT STANDBY (0.99 0 > 350 F 4. HOT SHUTDOWN <0.99 0 350 F > T> 200 F #"E5. COLD SHUTDOWN <0.99 0 < 200 F 6. REFUELING ** 10.95 0 1 140 FExcluding decay heat** Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.NL.89.087.01.R4 16 Rev. 4 _: ATTACH 5ENTTi ST-HL.AE-Je// 2.0 RESPONSIBILITIES FOR PART A 0F /0o= - -All changes to Part A of the ODCM shall conform to the requirements of Technical Specification 6.14. l I i' I NL.89.087.01.R4 17 Rev. 4 r JJiscifijfNTT3 ST HL-AE-32/l PAGE __!9 0F _JO o - SECTIONS 3.0 and 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS I l NL.89.087.01.R4 18 Rev. 4 r4 ATTACHMENT A3 ST HL AE-3ru PAGE bo _ OF 100 _ 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY CONTROLS 3.0.1 Compliance with the Limiting conditions for Operation continued in the succeeding controls is required during the OPERATIONAL HODES or other conditions specified thereins except that upon failure to meet the Control, the associated ACTION requirements shall be met. 3.0.2 Noncompliance with a Control shall exist when the requirements of the Control and associated ACTION requirements are not met within the specified time intervals. If the Control is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required. 3.0.3 When a Control is not met, except as provided in the escociated ACTION requirements, within 1 hour action shall be initiated to , place the unit in a MODE in which the Control does not apply by placing it, as applicable, ina. At leami M'T J STANDBY within the next 6 hours, b. At least HOT SHUTDOWN within the following 6 hours, and c. At least COLD SHUTDOWN within the subsequent 24 hours.Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Control. Exceptions to these requirements are stated in the individual controls. This control is not applicable in HODE 5 or 6. 3.0.4 Entry into an OPERATIONAL MODE or cther specified condition shall not be made when the conditions for the Control are not met and the associated ACTION requires e shutdown if they are not met within a Specified time interval. Entry into an OPERATIONAL MODE or 3pecified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual Controls. NL.89.087.01.R4 19 Rev. 4~ 'r g Rifd3 ST HL AE 38/l APPLICABILITY OF 10a o PAGE_38 SUEVEILLANCE REQUIREMINTS, 4.0.1 Surveillance Requirements shall be set during the OPERATIONAL HODES or other conditions specified for individual Controls unless otherwise stated in an individual Surveillance Requirement. 4.0.2 Each Surveillance Requirement shall be performed within the speciflod time interval witha. A maximum allowable extensaon not to exceed 25% of the surveillance interval.4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by control 4.0.2, shall conctitute a f ailure to meet the OPERABILITY requirements for a Control. Tne time limits of the ACTIOJ requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours to permit the completion of the surveillance when thu allowed outage time limits of the ACTION requirements are less than 24 hours. Surveillance Requirements do not have to be performed on inoperable equipment. 4.0.4 Entry into an OPERATIONAL HODE or other specified condition shalt. not be made unless the Surveillance Requirement (s) associated with the Control has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL H0 DES as r.' quired to comply with ACTION requirements. t NL.89.087.01.R4 20 Rev. 4'IAY Ty rana wst a wckd- w ,a. a/r*%.?w ".s.. w$(u" saun % + 0 , ~9 .. 5 NiA0mem .w.ww. ,u a A IJs<h, eM>ed% +% cycm wD pci%ALD m cayn ,a m/j mcpq cc,m a,,4 ;gm g;,aa, cf $pped4 % 10 GR Puf"50, s 60!MlE*AUYL@lMLS ~ ^T T - 2"#L D*!Ol^C!CM ENm0EWi AL OSAMhG REF-GRT @;& "'dk int uding a comparison with preoperational studies, with operational co [ols, as appropriate, and with previous environmental surveillance reports nd an assessment of the observed impacts of the plant operation on the ,epv ronment. The reports shall also include the results of the Land Use Censu,s required by Sp,.?ification 3.12.2. ' i The Annual Radiological Environmental Operating Rep 3r s shall include the resultsofanalysisofallradiologicalenvironmentaljamplesandofall environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the'0ffsite Dose Calculation Manual, as well as summarized and tabulated resy ns of these analyses and measurements in the format of the table in thpVRadiological Assessment Branch TechnicalPosition, Revision 1,NovemberIp9. In the event that some indivi-dual results are not availabic for incluefon with the report, the report shall be submitted rioting and explaining the casons for the missing results. The missingdatashallbesubmittedasyonaspossibleinasupplementaryreport. Thereportsshallalsoinciddethefollowing: a summary description of theRadiologicalEnvironmenta}41onitoring program; at least two legible mapscovering all sampling locat ons keyed to a table giving distances and directions from the centerline of on reactor; the results of licensee participation in the Interlsboratory Co. rison Program and the corrective action taken if the specified program is t being performed as required by Specification 3.12,3; (reason for not co cting the Radiological Environmental Monitoring Program as i required by sp fication 3.12.1, ,:d discussion of all deviations from the sampling sc aule; discussion of environmental sample measurements that exceed , the repo ng levels but are not the result of plant effluents, pursuant to { ACTl . of Specification 3.12.1; and discussion of all analyses in which the } Lt 'equired was not achievable. SEMIAf4f4UAL RADI0 ACTIVE EFFLUENT RELEASE RfPORT** 6.9.1.4 Routine Semiannual Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year.fpihe ;:: Hod--et-the 'i r e t i wert 3hsil begie uith tha rh t e ^f-fu i i. ia i u it i 04&ty., s )L-4he-Semiennual-Radioact4ve--Mfhent "clease-Reports--shah-inehde e- strmmary--of--the-quant 414et-of radioact4+e-144 uM-and-gaseous-ef44uentt-end-solithraste---mieased4ron-the-tmit-es-cut 44ned in Raleterj Owide 1.21, "MenurtM, tvaiua- '.-44agr-and Reparting Radioactivity in Sol [d_hstes -and-Reimc:. +Redicaet4*e-- .41 ster 4als in Liquid end -Gaseous-E444uent&-from-tightWaterd.oolea nuc teer-Twer , 4tlants ," Revi sian 2,-- Ane IW4 -with-date-sttmmarized 7 cc e-quar 4erAy.-ba&4&-f*How---4eg-the-format-of Appendi A-B-ther+ofr-fm so1id vaiter, TWT 6F.at-for-1aole-4-%JLThi&4abulat4en supplement +-the-requirements-of-42&-407 Uf10-ef R-Part-20r~**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; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.SOUTH TEXA5 - UNil5 1 & 2 6-13 - ATTACHMENT A A ST HL AE 3M PAGE 50_0F D I ATTACHMENT ST HL AE M'/ !41 , (211Nii1MU1JORE0LS -_ _ __ J%GEdLOLS 7 '.$[M1 ANNUAL RAD 10ACllVE EfftU[NT RElfAS[ REPOR1 (Continued) in Appendix C shall be supplemented with three additional categories; clasy of solid wastes (as defined by 10 Cf R Part 61), type of container (e.g. , LSA/lype A, lype B, large Quantity) and 50L10lflCA110N agent or absorbent (e g. , cement, urea formaldehyde). The Semiannual Rad bactive Effluent Release Report to be submi ed within 60 days after January J of e3ch year shall include an annual summa of hourly meteorological data collet > over the previous year. This annu i summary may be either in the form of g %r-by-hour listing on magnetic t of wind if measured), speed,winddirection,atmosphericstability,andprecipitatiof,w(inddirection, or in the torm of joint frequency distributions of wind specc) and ataoscheric stability.* This same report shall include n assessment of the radLtion doses due to the radioactive liquid and gas us ef fluents released ea . This same report f rom sht t'a unit l '. also or station include during the an assessment previous of the calendar radiation dose y/f rom radioactive 114110 and gaseous effluents to MEMBERS Of 1HE PUBL1 ue to their activities insida the 511E BOUNDARY (figures 5.1-3 and 5.1-4) ring the report period. All assumptions used in making these assessments, i.e. Specific attivity, exposure time, and location, shall be included in these reports. The meteorological conditions concurrent with the time of, release pf radioactive materials in gaseous ef fluents, as determined by sampling equency and measurement, shall be used for determining the gaseous pathway 4 ses. The assessment of radiation doses shall be performed in accordance withAhc methodology and parameters in the Of f SilE DOSE CALCULA110N MANUAL (ODCM I 1he Semiannual Radioactive Efflue Release Report to be submitted within 60 days after January 1 of each year phall also include an assessment of radiation doses to the likely most efposed MEMBER Of THE PUBLIC from reactor releases and other nearby uranium K el cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CfR / art 190, " Environmental Radiation Protection StandardsforNuclearPowerOpdation." Acceptable methods for calculating the dose contribution from li 'uid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977. The Semiannual Radio ctive Effluent Release Reports shall include a list and description of unp1pf'ined releases f rom the site to UNRESTRICIED AREAS of radioactive materials i. gaseous and liquid effluents made during the reporting period. The Semiannua Radioactive Effluent Release Reports shall include any changes made durip)a the reporting period to the PROCESS CONTROL PROGRAM and the ODCM, pursupht to Specifications 6.13 and 6.14, respectively, as well as any major change to Liquid, Gaseous, or Solid Radwaste Treatment Systems pursuant to Specification 6.15. It shall also include a listing of new loca-tions for do.e calculations and/or environmental monitoring identified by the Land use C isus pursuant to Specification 3.12.2.*ln ligd of submission with the Semiannual Radioactive Ef fluent Release Report, the licensee has the option of retaining this summary of required meteoro-logical data on site in a file that shall be provided to the NRC upon request. /50bTH TEXAS - UNils 1 & 2 6-19 ___ __ _ -_ - -____-__-_- --- -- --^' ~M$ElllWIYLGMMLS-- fiACIiI5Uii~/Q.ST.HL-AE.J&4 -SIM1 ANNUAL RAD 10ACilVE_Elfl0ENT REtEASE-R[ PORT;(Continued) -s ( The Semiannual Radioactive Effluent Release Reports shall also in: 19de the fol',owing: an'emplanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Specification 3.3.3.10 or 3.3.3.11, respectively; and description of the events leading to 11guld holdup tanks or gas storage tanu exceeding the limits of Specification 3.11.1.4 or 3.11.2.6, respectively.- HONTHLY OPERATING REPORTS6. 9.1. 5 Routine reports of operaGng statistics and shutdown experierce including documentation of all challenges to the PORVs or safety valves ,shall be submitted on 6 monthly basis to the Director, Of fice of Resourc,e Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with e copy to the Ragional Administrator of the Regional Office of the NRC, no ,later than the 15th of each month following the calendar month covered by the report. CORE OPERATING LIM 115 REPORT 6.9.1.6 Core operating limits shall be established and docun,ented in the CORE OPERAllNG reload cycle.LIMITS REPOR1 before each reload cycle or any remaining part of a in the Control Room. The CORE OPERA.NG L1H115 REPORT shall be maintained available The analytical methods used to detennine the core operating limits shall be those previously reviewed and approved by NRC in WCAP-8403, " Power Distribution and Load following Procedures," 1974 and in WCAP-9273-A, " Westinghouse Reload Safety Evaluation Methodology," 1965 (for Control Bank Insertion Limits). The core operating limits shall be determined ( so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal hydraulic limits ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. The CORE OPERATING LIM:T5 REPORT, including any mid-cycle revisions or supplements thereto, shall be provided within 30 dt,ys of their implementation, for each reload cycle, to the NRC in accordance with 10 CFR 50.4. SPECIAL REPORTS i 6.9.2 Special reports shall be submitted to the Regional Administratoi of the Regional Office of the NRC within the time period specified for each report. ( SOUTH TEXA5 - UNITS 1 1. 2 6 20 Unit 1 - Amendment No.9 Unit 2 - Amendment No.1 g, Au.e. d n me. bd'eeb cLw,co .*mfc. h </d C/7:S / T1: D g,n c.oc c O LMa dMOU A Wb rns PM&st. Go rNec phM1 ADMitil5HAllYLCOR1ROLS _-f RECORD RE1[NTION (Continued)j. Records of reviews performed for changes made to procedures or e w pment or reviews of tests and experiments pursuant to 10 CFR 50.59; k. Records of meetings of the PORC and the NSRB; 1. Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.9 including the date atwhich the service life commences and associated installation and l maintenance records;m. Records of secondary water sampling and water quality; and n. Records of analyses required by the Radiological Environmental Honitoring Pr.ogram that would pemit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and QA records showing that these procedures were foilowed.9 6.11 RADIATION PR01[C110N PROGRAM 6.11.1 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 operations involving personnel radiation exposure. 6.12 HIGH RADIATION AREA 6.12.1 Pursuant to paragraph 20,203(c)(5) of 10 CfR Part 20, in lieu of the" control device" or " alarm signal" required by paragraph 20.203(c),cach high radiation area, as defined in 10 CFR Part 20, in which the intensity of radia-tion is equal to or less than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be barricarWd and conspicuously posted as a high radiation area and entrance thereto siull be controlled by requirin0 issuance of a Radiation Work Permit (RWP). Iruivibals qualified in radiation protection procedures (e.g., Health Physics hchn'cian) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement durinn the performance of their assigned duties in high radia-tion areas with exposure rates equal to or less than 1000 mR/h provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:a. A radiation monitoring device which continuously indicates the radiation dose rate in the area; or b. A radiation monitoring device which continuously integrates the rsdiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such arens with this monitoring device eav be made after the dose rate levels in the area have been establish'mi and personnel have been made knowledgeable of them; or c. An indiv(dual c;ualified in radiation protection procedures with a radiation dose rate u nitoring device, who is responsible for providing positivc control cver the activities within the area and shall perform periodic radiation surveillancc at the frequency specified by the licalth and Safety Servia s Manager in the RWP.ATIACHMENT 4.2 SOUTH TEXAS - LH1151 & 2 6-22 ST HL AE Ell PAGE.5 2 _ 0F.5 7 I ATTACHMENT /R ST ill AEcsl/ LD.2/iLSIEldlyLf0f0FOLL___. ___ _ _. _a PAGE.5L 0F-f/--..- n --a HIG4 RADIA110N AREA (Continued) 6.12,2 In addition to the requirements of Specification 6.32.3, areas accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be provided with locted doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shif t Supervisor on duty and/or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area, in lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being i performed within the area. I for individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h that are located within large areas, such as pWR containment, where no enclosure exists for purposes of lockin;. and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device. l 6.13 PROCESS CONTROL PROGRAM (PCP) l %t~4T Lq F 6.13.1 lhe PCP shall be approvedVITiFTommt5TTon prior to implerr3ntf6 Ton. 6.13.2 Licenser initiated changes to the PCP:a. Shall be submitted to the Commission in the aiannual Radioactive l Effluent Release Report for the period ,4 which the change (s) was made. This submittal shall conta.in( 1) Sufficiently detailedA mation to totally support the rationale for 1 supplementf)-47)3Wfbnge formation; without benefit of additional or 2) A detdination that the change did not reduce the overall {c- ormance of the solidified waste product to existing criteria for solid wastos; and3) Documentation of the fact that the change has been reviewed and found acceptable by the PORC.( b. Shall become ef fective upon review and acceptance by the PORC. _ 6.14 Of f 51_1E 00FE cat CUL ATION MANUAL (ODCH) lO.A- q7 7 6.K 1 The ODCM shall be approved by the Commission prior to implementation /\6.14.2 Iitensb4 itiated changes to the ODCH:a. Changes to Part A bal be su tod-to and approved by the NRC staff q prior to implementation.Changes to Pa,L # all be submitted'to~tjte Commission in theb. t SemiannudTadioactive Ef fluent Release Rep 31t-for_the period in v icti'the change (s) was made effective. This submitta M hall{ contain: Nw SOUTH TEXA5 - UNJ T51 & 2 6-23 Unit 1 - Amendment hc . 4 _ ~_ GiWCHMENT ^,'- ST-HL. AE- W I a Ws tct4 4, _ uPAG - E !E.-. 0F g-- - Changes to the PCP:a. Shall be documented and recorSs of reviews performed shall be retain -ed as required by Specification'6.10.Ao. This documentation shall contain: 1). Sufficient information to support the change together with the -- appropriate analyses or evaluations justifying the change (s) and _ 2) A determination that the change will maintain the overall *on- __ formance of the solidified waste product to existing rer *- ments of federal, State, or other applicable regulations. _. b, Shall become ef fective af ter review and acceptance by thellfRLj and _the approval of the Plant Manager. y _ I _._. _ __ t I fJs E.R T ~2_. Changes to he ODCM: - - - -a. Shari be documented and records of reviews performed shall be retain ~ ~ed as required by Specification-6.10.3p. This documentation shall contain: ~~. 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and = _2) A determination that the change will maintain the level of radioacthe ef fluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix 1 to 10 CFR Part 50 and ,not-adversely impact the accuracy or reliability of ef fluent, - dose, or setpoint calculations.~~~b. Shall become ef f ective af ter review and acceptance by theJURC[ and the approval of the Plant Manager. - c. Shall be submitted to the Commissioniin the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the --- report in which any change to the ODCM was made. Each change shall be identitied by markings in the margin of the af fected pages, -- clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented. -- - j. . . _ - . . _ , . . -__ _- .. .-.._ . ~ ~ . =&Nv'=-' -N .^O. -mmeni- m a wh app.- -emem = -owie gy .si- .naupse m. w onamNM &NJ ens g.u- w w e.w-3 -M mw .y a.-1==N -i 6W 66' -wi gyi.e.a&me A-m -*-*=M-"'B'h*4r' _eh-.y- -AlibrimtNT A '2 SNll AE 37// IElRli1PellyLC010ROLS - JA0F % J)F 9 7 Orf 511E DOSE CALCULATION _- MANUAL (ODCM) (Continued) .- s1)~ Sufficiently detailed information to totally support the /_rationale for the change without benefit of additional.er s pplemental information. Information submitted,540fild consist of a patkage of those pages of the ODCM to bp etianged with each page numberedsdated and containing the refision number, together with appropriate'amQyses or eval ati6'ns justifying the , change (s);2) A determination that th change will not reduce the accuracy or reliability of d,owcalculatiofihor Setpoint determinations; and 3) Docum fjfo n(entflion acceptable by ofthe the fact that the changNas been reviewed PORC.c. C)afges to Part 8 shall become elfective upon review and an c(tance f l 4y _t he PORC.~[ TI'5 MAJOR CHMPJ5 lD70E~GASE005, AND $0llD RADWASTE 1REATHENT SYSif)M 6.1$.1 Licensee-initiated major changes to the Radsaste Treatment Syctems / (liquid, gaseous, and solid):a. Shall be reported to the Commission in the Semiannual sadioactive f Effluent Release Report for the period in which the evaluation was reviewed by the PORC. The discussion of each ch ge shall contain: 1) A summary of the evaluation that led to . ie determination that >the change could be made in accordanc with 30 CFR 50.59;2) Sufficient detailed information t totally support the reason for the change without benefit additional or supplemental information; 3) A detailed description of he coulpment, components, and processes involved and the interf es with other plant systems; 4) An evaluation of tt change, which shows the predicted releases, of radioactive m3terials in liquid and gaseous effluents and/or quantity of so d waste that differ from those previously pre-dicted in th icense application and amendments thereto;5) An evaluption of the change, which shows the expected maximum exposur.s to a MEMBER OF 1ME PUBLIC in the UNRESTRICTED AREA and the general population that differ from those previously est'.ated in the License application and amendments thereto; 6) s comparison of the predicted releases of radioactive materials, in liquid and gaseous ef fluents and in solid waste, to the actual releases for the period prior to when the change is to be made;*Licer des may choose to submit the information called for in this Specification as art of the annual FSAR update.m 20VTH TEXA5 - UNITS 1 L 2 6-24 Unit 1 - Amendment No. 4 j a hDMIfflilEhllyL_ CONMQLi_ __ / t, MAJOR CHANGES 1011Q010, GASEOUS, AND SOLID RADWA51E TREATHEtd /, ' H 5 TEM 5 (Continued)1) An estimate of the exposure to pla 4 perating personnel as a result of the change; and 8) Documentation of theJ that the change was t'eviewed and foundacceptableb(thePORC. . b. Shall becorne fTective upon review and acceptance by the PORC. ,N m - t ATTACHMENT Q ~~~~^ SHiL AE 3E// PAGE_-J2___0F _5 7 - t 4 soqHTExAs-uni!sJ_A2) .i~ATf$CIii4ENf33 ST HL AE 3r/l PAGE Mn 0F /00 l l i SECTION 3/4.3.3.3.10 ' RADIOACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION NL.89.087.01.R4 21 Rev 4.-- _..,_..-.____._;.____.__.....;- iF'N ATTACHMEng p3-ST HL AE-L_ PAGE 23_3gll _ op _,n o ! INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUD4T HONITORING INSTRUMDJTATION CONTR03 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their Alarm / Trip Satpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in this document. APPLICABILITY: At all times. l l ACTION: la. With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the j above control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, b. With less than the minimum number of radioactive liquid effluent monitoring-instrumentation channi,is OPERABLE, take the ACTION shown in Table 3.3-12. Restore the inoperable instrumentation to ,OPERABLE status within the time specified in the ACTION, or ! explain in the next Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.4 why this inoperability was not corrected within the time specified,c. The provisions of Control 3.0.3 are not appilcable.SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive 11guld effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-8. > NL.89.087.01.R4 22 Rev. 4 TABLE 3.3-12 d RADIOACTIVE LIQUID EFFIUENT MONITORING INSTRUMENTATION MINIMLH CHANNELS INSTR'JMENT OPERAT,LE ACTION1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release 1Liquid Waste Processing Discharge Monitor 1 432. Flow Rate Measurement Devices Liquid Waste Processing Discharge Line 1 46 y tn >cWM mr>,rn bb1 4-m r AIS m-ON y tv O3 i NL.89.087.01.R4 23 Rev. 4 A1TACHMENT A3 ST HL AE 3Sil PAGE 3 5 0F _ mv _ TABLE 3.3-12 CONTINUED ACTION STATEMENTf ACTION 43 - With the number of channels OPERABLE less than required by the M*nimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided that prior to initiating a release A. At least two independent samples are analyzed in accordance with Control 4.11.1.1.1, andb. At least two technically qualified members of the facility staff independently verify the. release rate calculations and discharge line valving.Otherwise, suspend release of radioactive effluents via this pathway. ACTION 44 - (Not Used). ACTION 45 - (Not Used)ACTION 46 - 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 30 days provided the flow rate is estimated at least once per 4 hours during actual releases. Pump performance curves generated in place may be used to estimate flow. NL.89.087.01.R4 24 Rev. 4 y' 4 b TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATIC*i SURVEILLANCE REQUIREMENTS i 1 DIGITAL CHANNEL CHANNEL SOURCE CHANNEL OPERATIONA5-INST".UMENT CHECK CHECK CALIBRATION TEST i, 1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release iLiquid Waste Processing Discharge Monitor D F R(3) Q(1)I l 2. Flow Rate Measurement Devices i ! Liquid Waste Processing Dischar e Line D(4) N.A. R N.A. 1 i l i$1 mu1>d miEM iub5 sms h_E j NL.89.087.01.R4 25 Rev. 4 Q~> V2 s O O l~, ...n t -,.,. - s - ,. , - - - -. ,~ - --- , ,~~ .., AT . . , . . . . a. i d ST HL.AE 38II PAGE R1 - 0F 101 - _TABLE 4.3-8 CONTINUED TABLE NOTATIONS (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions eAlsts:-a. Inst rument indicates measured levels above the Alarm / Trip Setpoint, or -j b.- Monitor fallure. I (2) (Not Used) i (3) The initial CHANNEL CALIBRATION shall be performed using one or more of I the reference standards certi(led by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that I participate in measurement assurance ectivities with NBS. Thesti l standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAL BRATION, sources-that have been related to the initial calibration shall be used.(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours on days on which continuous, periodic, or batch releases are made. ' i l f l k l NL 69.087.01.R4 26 Rev. 4 l. . :.a ATTACHMEN11.F.ST HL AEO2ll l PAGE 39 0F loo I i SECTION 3/4.3.3.3.11 : RADI0 ACTIVE GASEOUS EFFLUENT HONITORING INSTRUMBJTATION b l-i { NL.89.087.01.R4 27 Rev. 4 1)FTKcliil55IA3 ST HL AE-3M. PAGE ?'l 0F J'o INSTRUMENTATION L---RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Controls 3.11.2.1 and 3.11.2.5 are not exceeded. The Alarm / Trip Setpoints of these channels sueeting Control 3.11.2.1 shall be determined and adjusted in accordance with the methodology and parameters in the ODCH. APPLICABILITY: As shown in Table 3.3-13 ACTION:a. With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseour effluents monitored by the affected channel, or declare the channel inoperable. b. With the number of OPERABLE radioactive gaceous affluent monitoring instrumentation channels less than the Minimum Channels OPERABLE, take the ACTION shown in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.4 why this inoperability was not corrected within the time specified. c. The provisions of Control 3.0.3 are not applicable.SURVEILLANCE REQUIREMENTS 4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and ANALOG' CHANNEL OPERATIONAL TEST or DIOITAL CHANNEL OPERATIONAL TEST, as applicable, at the frequencies shown in Table 4.3-9. i~NL.89.087.01.R4 28 Rev. 4 TABLE 3.3-13 4 . RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATICN-MINIMAL CHANNELS INSTRUMENT OPERABLE AFFLICABILITY ACTION i_1. Condenser Evscuation System, a. Condenser Air' Removal Systera Discharge Header Noble Gas Activity-Monitor 'l49-b. Flow Rate Monitor 148 i, c. Sampler Flow Rate Monitor I482. Unit vent i. a. Noble Gas Activity Monitor 149b. Iodine Monitor or Iodine Sampler 153 l c. Particulate. Monitor or Particulate Sampler 1 *. 53 44 , d. Flow Rate Monitor 148e. Sample Flow Rate Monitor 148 li l' l $$D ' onbh , O I OmK. b$e-%N uNL.89.087.01.R4 29 Rev. 4 3 a o i ATTACHMENT A3 ST HL AE-39 // PAGE 31 0F / 0 0 1 1 TABLE 3.3-13 CONTIN 1 FED TABLE NOTATIONS l lAt all times ACTION STATEMENTS ACTION 47 - (Not used)ACTION 48 - Vith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via . this pathway may continue for up to 30 days provided the flow ' rate is estimated at least_once per 4 hours. ACTION.49 - With the number of channels OPERABLE less tha.n required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the grab samples are taken at least'once per 12 hours and these samples are analyzed for radioactivity within 24 hours. ACTION 50 - (Not used) ACTION $1 - (Not used) ACTION 52 - (Not used) ACTION $3 - With the number of channels.0PERABLE loss than required by the Minimum Channels OPERABLE requirement, effluent releases via-the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment.NL.89.087.01.R4 30 Rev. 4TABII 4.3-9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS/.NALOG OR DIGITAL CHANNEL MODES FOR VHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE INSTRUMENT- CHECK CHECK CALIBRATION TEST IF REQUIRED1. Condenser Evacuation System a. Condenser Air Removal System Discharge Header Noble Gas Activity Monitor D- M R(3) Q(2) * b. Flow Rate Monitor D N.A. R N.A. * c. Sampler Flow Rate Monitor D N.A. R Q * 2. Unit Vent a. Noble Gas Activity Monitor D M R(3) Q(2) * b. Iodine Monitor or D M R(3) Q(2)Iodine Sampler W N.A. N.A. N.A.c. Partictlate Monitor D M R(3) Q(2)l or Farbcle Sampler V N.A. N.A. N.A. 3 %. al, c;2 mI>ld. Flow Rate Monitor D N. A. R N.A. *{ PT me. Sample Flow Rate Monitor D N.A. RWz Q gO (416 O 1 NL.89.087.01.R4 31 Rev. 4 ATTACHMENT A 3 ST HL AE-32/1 PAGE A3 0F /0o TABLE 4.3-9 CONTINUED TABLE tJOTATIONS At all times (1) (Not used) 1 (2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions existsa. Instrument indicates measured levels above the Alarm Setpoint, or b. Monitor failure.(3) The initial CHANNEL CALIBRATION shall be performed using one or more of l the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, l sources that have been related to the initial calibration shall be used. (4) (Not used) l NL.89.087.01.R4 32 Nev. 4 ATTACHMENT A3 ST HL-AE 3fil PAGE 3 4 0F __/no-i , SECTION 3/4,11,1 LIQUID EFFLUENTS NL,89.087.01.R4 33 gey, 4 ATTACHMENT A3 - ST HL AE 39// PAGE 3 5 0 F / d o__ LIQUID ETFLUENT SAMPLING AND ANALYSIS PROGRAM Radioactive liquid wastes shall be sampled and analyzed in accordance with the program specified in Table A3-1 for STPEGS. The results of the radioactive analysis shall be used as apprcpriate with the methodology of Part B of the ODCH to assure that the concentrations of liquid effluents from the cooling reservoir are maintained within the limits of Part A of the ODCH. l Radioactive effluent information for liquids obtained from sampling and analysis programs shall also be used in conjunction with the methodologies in Part B to demonstrate compliance with the dose objectives and surveillance requirements of Part A of the ODCH. l l NL.89.087.01.R4 34 Rev. 4 . - _ - - - _ - - _ . _ _ - - = - . . . . - . - . - - . - _ - - _ . - - - - . - 3/4.11 RADIOACTIVE EFFLUENTS 7TTACHMENT 4'3 ST-HL AE 32 Il 3/4.11.1 LIQUID EFFLUENTS 0F /0C) - PAGE % CONCENTRATION CONTROLS 3.11.1.1 The concentration of radioactive material released in 11guld effluenta to UNRESTRICTED AREAS (See Figure 5.1-4) shall be limited to the concentrations specified in 10CFR Part 20, Appendix B, 'lable 11. Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entraingd noble gases, the concentration shall be limited to 2 x 10 microcurle/ml total activity. APPLICABILITY: I.t all times. ACTION: Vith the concentration of radioactive material released in 11guld effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits. SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analyals program specified in Table A3-1. 4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1, NL.89.087.01.R4 35 Rev. 4 ATTACHMENT A3 ST HL-AE 37// PAGE X7 0F 100 TABLE A3-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOVER LIMIT HINIMUM OFDETEgON LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD) TYPE FREQUENCY FREQUENCY ANALYSIS (uC1/ml)~1. Batch Vaste P P Principa{3 gamma $x10 Release Each Eatch Each Batch Emittera 6I-131 IX10a. Vaste Monitor -5 Tanks P M Dissolved and 1x10 ! One Batch /H Entrained Gases (Gamma Emitters)b. Laundry __ .And Hot - 5 Shower P M H-3 lx10 Tank Each Bat.h Composite (4)~Gross Alpha 1x10c. Vaste Eva-porator Condensate P Q Sr-89, Sr-90 5x10 Tanks Each Batch Composite (4)Fe-55 1x10d. Any other tanks which discharge 11guld ,wastes past RT-8038 NL.89.087.01.R4 36 Rev. 4 Y r7m^ v- - y wwe-r--P-'s *++ w. a= , -4w 4-. :-- --wi- w----ia-----. a- - .v '7 -*,,m-*w --mw- *"-- _ - - , . . - . - - - _. -~ - _ _ - _ _ - - .AfTACHMENT A3 ST HL-AE-3P/l TABLE A3-1 39 0F /0 0 TABLE NOTATIONS ( }The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yict1 a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, wh'ch may include radiochemical separation: 4.66s b LLD = EV 2.22 x 10 6 , y , ,xp (,pg]Where LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume), o g- the standard deviation of the background ccunting rate or of the counting rate of a blank sample as appropr!. ate (counts per minute). E= the counting efficiency (counts per disint.egration), V= the sareple size (units of mass or volume), 6 2.22 x 10 = the number of disintegrations per minute per microcurie, Y= the fractional radiochemical yield, when applicable,~h= the radioactive. decay constant for the particular radionuclide (s ), A t = the elapsed time between the midpoint of s imple collection and the timo of counting (s).- ( Typical values of E. V, Y, and At should be used in the calculation. It should be recognized that the LLD is defined as an a, priori (before the fact) limit representing the capability of a measurement system and not as an a,posteriori (after the fact) limit for a particular measurement. l: A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling. for analyses, each batch shall be isolated, and then thoroughly mixed by methods described in plant operating procedures to assure representative sampling. NL.89.087.01.R4 37 Rev. 4 ; TTTACHMENT A3 ST HL AE-39 // TABLE A3-1 PAGE 3 9 __0F - 10 0- j TABLE NOTATIONS (Continued) l ( }The principal gamma emitters for which the LLD specification applies ! include the following radionuclides:- Mn-54, Fe-59, Co-58, Co-60, Zn-65, j Ho-99, Cs-134. Cs-137 Co-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together-with those of the above nuclides, shall also be analyzed and reported in the Semiannua!. Radioactive Effluent Release Report pursuant to Technical Specification 6.9.1.4 as outlined in Regulatory Guide 1.21, Appendix B. Revision 1, June 1974 ( 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 l method of sampling employed tesults in a specimen that is representative of j the liquids released. l l NL.89.087.01.R4 38 Rev. 4 Arl ACHMENT A3 ST HL AE-3t// /0 a PAGE'No 0F -_. J P k SECTION 3/4,33,3,g DOSE I NL,89,087.01.R4 39 Rev. 4 f l ... . -. , _ - , . . - - + - , . . - - . . . . . . . , _ . , , - , .AfiACHMENT A 3-RADIOACTIVE EFFLUENT ST-HL-AE-3P//DOSE CONTROLS 3.11.1.2 -The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-4) shall be limited: a.- During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any orgt.i, andb. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 m. ems to any organ.APPLICABILITY: At all times. ACTION:'a. vi 3 a calculated dose from the release of radiocetive a 1s i.7 liquid effluents exceeding any of the above b :ts prepara and submit to the Commission within 30 arye, rauant to Technical Specification 6.9.2, a Sp.u i A t ;eport that identifies the cause(s) for axceeJ as the limit (s) and defines the corrective ac; ..s that have been taken to reduce the releases and -the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the aoove limits. This Special Report shall also includes (1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40CFR Part 141, Safe Drinking Water Act.* b.. The provisions of Control 3.0.3 are not applicable. SURVEILLANCE REQUIREMENT; 4.11.1.2 Cumulative dose contributions f rom liquid ef fluents for the current calendar quarter and the current calender year shall te determined--in accordance with the methodology and parameters in the ODCM at least once per 31 days.*The requirements of. ACTION a.(1) and (2) are applicable only if drinking water supply is taken from the receivirg water Lody within 3 miles of the plant discharge. In the care of river-sited plants, this is 5 miles downstream only.NL.89.uB7.01.R4 40 Rev. 4 ATTACHMENT A3 . ST HL AE-39 // l PAGE_00 0F mn - l)SECTION 3/4.11.1.3 LIQUID WASTE PROCESSING CONTROLS l NL.89.087.01.P2 41 Fev. 4 ATTACHMENT A3 ST HL AE 3F// RAPIOACTIVE EFFLUENT -=- PAGE L!3 0F /oo LIQUID WASTE PROCESSING SYSTEM CONTROLS 3.11.1.3 The Liquid Waste Processing System shall be OPERABLE and appropriate portions of the system shall be used to reduce releasch of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-4) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period. APPLICABILITY: At all times. ACTION:a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Waste Processing System not in operation, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information: 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3. Summary description of action (s) taken to prevent a recurrence, b. The provisions of Control 3.0.3 are not applicable.SURVEILLANCE REQUIREMENTS 4,11.1.3.1 Doses due to liquid releases from each unit to i UNRESTRICTED AREAS shall be projected at least once per days in accordance with the methodology and parameters e the ODCM when Liquid Waste Processing Systems are not being fully utilized. 4.11.1.3.2 The installed Liquid Vaste Processing System shall be considered OPERABLF. by meeting Controls 3.11.1.1 and 3.11.1.2, b NL.89.087.01.P2 42 Rev. 4. la i..JnMLN1 A 3 ST HL-AE 32 /lPAGESI/ OF _ /od SECTION 3/4.11.2.1 GASEOUS EFFLUDITS il NL.89.087.01.P2 43 Rev. 4 ATTACHMENT /03 ST HL-AE-37// GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM Radioactive gaseous wastes shall be sampled and analyzed in accordance with the program specified in Table A4-1 for STPEGS. The results of the radioactive analyses shall be used as appropriate with the methodologies of Part B of the ODCM to assure that the dose rates due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary are within the limits of Control 3.11.2.1. ~ Radioactive effluent information for gaseous wastes obtained from sampling and analysis programs shall also be used in conjunction with the methodologies in Part 3 to demonstrate compliance with the dose objectives and surveillance requirements of Controls 3/4.11.2.1,.3/4.11.2.2, 3/4.11.2.3, 3/4.11.2.4, and 3/4.11.4. NL.89.087.01.P2 44 Rev. 4 4 RADIOACTIVE EFFLUENT g].gl.AE 3E ll 3/4.11.2 GASEOUS EFFLUENTS PAGE 4 0 & O - DOSE RATE CONTROLS 3.11.2.1 The dose rate due to radioactive materials released in gaseous effitints from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:a. For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and b, For Iodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.APPLICABILITY: At all times. ACTION: With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the abcVe limit (s). SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The done rato due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in this document. 4.11.2.1.2 The dose rate due to Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table A4-1. NL.89.087.01.P2 45 Rev. 4 TABLE A4-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM l , MINIMUM ' LOWER LIMIT OF l GASEOUS RELEASE _ SAMPLING AIMLYSIS TYPE OF jDETECTION (LLD)g') l. I TYPE FREQUENCY FREQUENCY. ACTIVITY ANALYSIS (uci/ml)1. Unit Vent g(3),(4) p , (2). -4 MO Grab Sample M H-3 (oxide). -6 l 2. Condenser Air g(3),(4). p (2)Removs1 System, 1x10 Discharge Header Grab Sample M H-3 (oxide) 1x103. All Release (6) (7) I-131 -Types as listed in 1x101. and 2. above Charcoal Sample I-133 -10 V( > Principal Gamma Emitters ( >Continuous 1x10 Particulate Sample g> Gr ss Alpha 1x10 ' Continuous ( , o Composite .Sr Particulate , a y: E r Sample U$ to -4 CN Continuous ( 0 Sr-89, Sr-90 - 1x10 ' Composite g (d Particulate g Sample NL.89.087.01.P2 46 Rev. 4 ATTACHMENT 4 3 ST-HL AE 3t// r TABLE A4-1 d ~= TABLE NOTATIONS ( The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 51 probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical / separations //4.66s b LLD = EV 2.22 x 10 Y exp (-hat)Where LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume), a = the standard deviation of the background counting rate or of the b-counting rate of a blank sample an appropriate. (counts per minute),E= the counting efficiency (counts per disintegration), V= the sample size (urits of mass or volume), 6 2.22 x 10 = the number of disintegrations per minute per microcurie, Y= the fractional radiochemical yield, when applicable,~ ?s = the radioactive decay constant for the particular radionuclide (s ~),At= the elapsed time between the midpoint of sample collection and tra time of counting (s). Typical values of E, V, Y, and ht should be used in the calculation. It should be recognized that the LLD is defined as an a priori (bef ore ':he fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. NL.89.087.01.P2 47 Rev. 4 ATTACHMENT /t 3 ST-HL-AE-37/I TABLE A4-1 PAGE 49 0F /00 TABLE NOTATIONS (Continued)- (2)The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87 Kr-88, Xe-133, Xe-133m, Ae-135, and Xe-138 in. noble gas releases and Mn-54, Fe-59, Co-58, Co-60, j Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141,'and Ce-144 in Iodine and particulate releases. This list does not mean that only these nuclides are to be cor.sidered. Other gamma peaks that are identifiable, together with those of the r.bove.nuclides, shall also be analyzed and reported in the l Semiannual Radioactive Effluent release Report pursuant to Technical ' Specification 6.9.1.4 as outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. ( ) Sampling-and analysis shall also be performed following shutdown, startup, or.a THERMAL POWER change exceeding-15% of RATED THERMAL POWER within a 1-hour period. Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded. Notiused.. (0}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 calculatian 'made in accordance with Controls 3.11.2.1, 3.11.2.2, and 3.11.2.3. ~( } Samples shall be changed-at l' east once per 7 days and analyses shall be completed within 48 hours after changing, or after removal from sampler.Sampling shall also be performed at least once per 24 hours for at least 7 days.following each shutdown, startup, or THERMAL POWER chance exceeding 15%.of RATED THERMAL. POWER within.a 1-hour period and analyses shall be completed within 48 hours of changing. _ When samples collected for 24 hours are analyzed, the corresponding LLDs may be. increased by a factor of 10..This requirement does not apply ifs .(1) analysis shows that the DOSE EQU1 VALENT I-131 concentration in the reactor coolant has not increased-more than a: factor of 3; and (2) the noble gas monitor shows that effluentactivity has not increased more than a factor of 3.L NL.89.087.01.P2 48 Rev. 4 ATTACHMENT A3 ST-HL-AE-3 E ll PAGE 5 0 0F /00 1 ; l-l SECTION 3/4.11.2.2 DOSE-NOBLE GASES NL.89.087.01.P2 49 Rev. 4 ATTACHMENT A 3 ST-HL-AE-39 /l RADIOACTIVE EFFLUENTS PAGE 5/ OF /00 DOSE - NOBLE GASES CONTROLS l-3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 )mrada for beta radiation, andb. During any. calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.APPLICABILITY: At all times.. ACTIONa. With the calculated air dose from radioactive nobic gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days., pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits, b. .The provisions of Control 3.0.3 are not applicable.SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in this document at least once per 31 days. NL.89.087.01.P2- 50 Rev. 4 ATTACHMENT 63 ST HL-AE 3P // PAGE Sa OF /N i-l iSECTION 3/4.11.2.3 : I DOSE - IODINE 131, 133, TRIT 2UH, and ! RADIOACTIVE MATERIAL IN PARTICULATE FORM- l h r f I t NL.89.087.01.P2 51 Rev. 4 1 (- '~ ATTACHMENT A 3 ST HL- AE- 32 / / . . PAGE _11__0F /00._. RADIOACTIVE EFFLUENTS DOSE - IODINE-131,' IODINE-133, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM CONTROLS 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from Iodine-131 Iodine-133, tritium, and all radionuelides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BDUNDARY (see Figure 5.1-3) shall be limited to the followingsa. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and b. During any calendar years Less than or equal to 15 mrems to any organ.APPLICABILITY . At all times.' , ACTIONa. With the calculated dose from release of Iodine-131 Iodine-133, tritium, and radionuclides in particulate form witt half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Techttical Specification 6.9.2, a Special-Report that identifies the-cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.-b. -The provisions of Control 3.0.3 are not applicable. -SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-131, Iodine-133, tritium and radionuclides'in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in this document.NL.89.087.01.P2- 52 Rev. 4 .~ - . . . . - - . - - - - - .- - . . - . . 4 e' ATTAc7 MENT A3 ST HL AE 3F//PAGE su 0F /00_- r a l)l l l SECTION 3/4.11.2.4 GASEOUS WASTE iR0 CESSING SYSTEM f f J.5 s{: NL.89.087.01.P2 -53 Rev.-4 l.- . , . . - ~ . . . , + . . , . .. .-..--,-_.n., ..r,,, . -~ ~ . . , , . ,,-....,.,.,.,n-n., .A_ m _. ITfTACHIENT A 3 ST HL AE3El/ PAGE_t L OF__lon- - RADI0 ACTIVE-EFFLUENTS GASEOUS VASTE PROCESSING-SYSTEM CONTROLS-3.11.2.4 The GASEOUS WASTE PROCESSING SYSTEM shall be OPERABLE and appropriate portions of this system shall be used to reduce releaser of radioactivity when the projected doses in 31 dayu due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUlDARY (see Figure 5.1-3) would exceedsa. 0.2 mred to air from gamma radiation, er 1 b. 0.4 mrad to air from beta radiation, or l I c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC APPLICABILITY: -At all times.ACTION , la. With radioactive gaseous waste being discharged without !treatment and in excess of the above limits, prepare and submit'to the Commission within 30 days, pursuant to Technical Specification 6.9.2,-a Special Report that includes the following information1. Identification of any inoperable equipment or subsystems, and the reason-for the inoperability. 2. Action (s) taken to restore the inoperable equipment to OPERABL2 status, and 3. Summary description of action (s) taken to prevent a recurrence, b. The provisions of Control 3.0.3 are not applicable.SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses-due to gaseous releases from each unit to areas at-and beyond the SITE BOUNDARY shall be projected at least once per 31 days-in accordance with the' methodology and parameters in the ODCM when the GASEQUS WASTE PROCESS SYSTEM is not being fully utilized. 4.11.2.4.2 The inctalled GASEOUS WASTF PROCESSING SYSTEM chall be considered OPERABLE by meeting Controls 3.11.2.1, and either 3.11.2.2 or 3.11.2.3. NL.89.087.01.P2 54 Rev. 4 i . . n!. ';;,U, Y A 3 ST HL AE 3t/ /- PAGE.S, OF /oo l l SECTION 3/4,11,4 l TOTAL DOSE NL.89.087.01.P2 55 Rev. 4 __ - 1 C EiEU__/d h 'nt-AE-Mll o RADIOACTIVE EFFIIENTS PAGE_ 5 1 0F_/0 4 3/4.11.4 TOTAL DOSE CONTROLS 3.11.4' The annual (calendar year) dose or dose commitment to any HEMBER OF THE PUBLIC d';e to releases of radioactivity and to radiation from uranium-fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited.to less than or ' equal to 75 mrems. l APPLICABILITY: At all times. ACTION \ 1a. With the calculated doses f rom the release of, radioactive. materials in liquid or gaseous ef fluents j exceeding twice the limits c Controls 3.11.1.2a, l- 3.11.1.2b, 3.11.2.2a, 3.11.2 2b, 3.11.2.3a, or 3.11,2.3b, calculations shal be made including direct radiation contributions 7 on ;he units and from outside storage tanks to determine whether the above limits of Control 3.11.4 have been. exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specificationo6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. Thie Special Report, as defined in 10CFR20.405(c), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources,-including all effluent pathways and direct-radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levtis of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.- If the estimated dose (s) oxceeds the above limits, and if the release condition resulting in viniation of 40CFR Part 190 has not_already been corrected, the Special Report shall include a request for a variance in accordance with the provisione of 40CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.2. The provisions of Control 3.0.3 are not applicable.l l hL.89.087.01.P2 56 Rev. 4.. a _- , - _ . _ . _ _ _ _ _ _ __ __ ___ ._ , , - . ._,Til ACHMENT A3 ST HL-AE 3t// PAGE 5 9 0F /00 , 1'3/4.11.4-TOTAL-DOSE Continued i SURVEILLANCE REQUIREMENTS 4.11.4.I' Cumulative dose contributions from liquid and gaseous )ef fluents shall be determined in accordance with Controls - ! 4.-11.1.2, 4.11.2.2, and 4.11.2.3 and in accordance with the methodology and parameters in this document.]4.11.4.2 Cumulative dose contributions from direct radiation from the units and from radwaste storage tanks shall be determined in j accordance with the methodology and parameters in this document. This requirement is applicable only under conditions set forth in ACTION a. of Control 3.11.4. NL.89.087.01.P2 57 Rev. 4 ATTACHMENT A 3 ST-HL-AE 3 g11 PAGE 's9 0F100 l i SECTION 3/4.12.1 l RADIOLOGICAL ENVIRONMENTAL MONITORING ?NL.89.f97.01 P2 58 Rev. 4. . . . . . - - . 1 l t i f, a , ,. . '.In V ST HL AE-3F//PAGE_&n 0F /d O RADIOLOGICAL ENVIRONMENTAL MONITORING _S_AMPLING AliD ANALYSIS PROGRAM The Radiot- '1 cal Environmental Monitoring Program (REMP) provides representative .lasurements of radiation and radioactive materials in those exposure pathi r a and for those radionuclides that lead to the highest i potential rad!.. tion exposure of members of the public resulting frors station : operation. 1 a monitoring program is. required by Control 3.12.1. The monitoring pr;. ram implements Section IV.B.2 of Appendix I to 10CFR Part 50,_ and thereby s,/plements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and' levels of radiation are not higher than expected on the basis of effluent measurements and-the modeling of the environmental exposure pathways which have been incorporated into Part B of the ODCM.The monitoring program as specified at fuel load shall remain in effect for at-least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience. In accordance with Control Surveillance Requirement 4.12.1 a sampling and analyses program shall be conducted. _The implemented Radiological Environmental-Monitoring Program as described in Part B to Section 5 of this document shall asla minimum satisfy the requirements of Table A5-1. Detection capability requirements, and reporting levels for radioactivity concentrations in environmental samples are shown on Tables A5-2 and A5-3, respectively. NL.89.087.01.P2 59 Rev 4 L _ _ _ . . .un A 3 bl-H L- AE- 32 /1 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS 3.12.1 The Radiological Environmental Monitoring Program (REMP) shall be conducted as specified in Table AS-1 and Table A5-2. APPLICABILITY: At all times. ACTIONa. With the Radiological Environmental Monitoring Program not being conducted as specified, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Technical Specificatior 6.9.1.3, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence, b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of the REMP when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9,2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual doseto a l' EMBER OF THE PUBLIC is less than the calendar year limit s of Controls 3.11.1.2, 3.11.2.2, or 3.11.2.3.When more than one of the radionuclides in the REMP are detected in the sampling medium, this report shall be submitted if concentration (1) reporting level (1) , concentration reporting level (2)(2) = '> - 1.0 When radionuclides other than those listed in the REMP are detected and are the result of plant effluents, this report shall be submitted if the potential annual doseto a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Controls 3.11.1.2, 3.11.2.2 or 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 required by Technical Specification 6.9.1.3 The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.NL.89.087.01.P2 60 Rev. 4 ATTACHMENT A3 ST HL AE-3f// ACTION (Continued)~c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by the REMP, identify specific locations for obtaining replacement samples and add them within 30. days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specification 6.14, submit the next Semiannual Radioactive Ef fluent Release Report documentation for a change.in the ODCM including a revised figure (s) and table to the ODCM reflecting the new location (s) with supporting information identitying_the cause of the unavailability of samples and justifying the selection of the new location (s) for obtaining asmples,d. The provisions of Control 3.0.3 are not applicable.SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be. collected pursuant to the REMP from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of and the detection capabilities required by the REMP.NL.89.087.01.P2 61 Rev. 4 l' i" TABLE A5-1 sRADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l IDER OF REHEDTIATn'E EXFOSURE FA W AY StHPLES #0 StFELEG #0 *1YFE #O EEEQUEICT tm/m S/MPLE TMPIE IU'ATIOS CIlETIW FMUBCY OF #MLYSIS1. - Direct Radiatim Forty routine rxnitoring stations either with Quarterly. Gama dose quarterly.two or core Josineters or with one instrumnt for measuring and recording dose rate cmtinuously, placed as folicws: 1 An inner ring of stations, one in each meteorolcgical sector in the general area of the SFIE BOLMMRY, An outer ring of stations, one in each neteorological sector in the' 6- to 8-len rarge fran the site, and'Ihe balance of the ststims to be placed in special interest areas such as population centers, nearby residences, schools, and in one c,r two areas to serve as ccutrol stations.7 T 3 Co4 d. c3 mx l' f 70I t- > I ' (AME m i te) Z eo -i o rr ' b k W O O i NL.89.087.01.F2 62 aev, 4 L , TABLE A5-1 (Continued),' RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NLHEER T..REPRESENIATIVE utu.iutt PANW SAMPLES AND SAMPLIIG AND - TIFE AND PEEQUEICY I AND/01 SAMPLE S/HEiE IDCATIQG( (TYIMTICH I?$lDCY & # MLYSIS2. Airbome Radiolodine ani Smples frun five locations: . Continuous smpler opera- Radiolodine Canister:Particulates tions with smple collec- I-131 analysis i'Ihree smples frun close to the three STIE ticn weekly, or nore weekly.BOtrMY locations in different sectors of frequently if required by the highest calculated annual average dust loadirg. Particulate Samler: ground-level D/Q. Gross Beta radioactivity analysi change;gollowingfilter and ganna isotopic analysis of cmposite (by location) quarterly. One smple frun the vicinity of a ccrmunity - , having the highest calculated anrual average I ground-level D/Q; and One smple frun a control location, as for l exmple 15 to 30 len distant and in a minimal t wLvl direction. l3. Watertorne a. Surface One smple frun the Colorado River upstrean of the main cooling reservoir spillway.Cmposite Smp1 gar a 1-nonth period Gauna isotopic analysis monthly. Ccrgnsite for h mT2>- trithrn analysis quarterly.([Q One smple frun the Colorado Rfver dcunstrean h " *E of the main cooling reservoir spillway. ; gn-r ~ 2>Che smple frun the min c< :., ling reservoe. s N l 3 NL.89.087.01.P2 63 Rev. 4 J 3 TABLE A5-1 (Continued) RADI:) LOGICAL ENVIRONMENTAL MONITORING PROGRAM ITd E R & RETRES M IATIVE NEE S/PELI!G de TYPE #O FREQUEICT NE FANY & # eLYSIS#D/OR S/MPE SA M N OU(1) (YYIFTTICN EEQUEICY3. Waterborne (Cont.)Smple fran the shallow aquifer.I ) Quarterly. G ana isotopic andb. Ground trititra analysis qmrterly.One smple ci each of one to three of the Mmthly. Gross beta ard ggc. Drinking isotopic analysis nearest wate ; supplies that could le affected by its d'A harge.nrxithly. Trititra analysis q w er1 7. One smple frun a control location. Che smple frun a site deep :vpifer well. One smple fecn upstrean and downstrean of the Seniannually Gmma isotopic analysisd. Sedirmnt seniannually.Fran cooling reservoir spillway area. Store 11nc One smple fran main cooling reservoir.> -t a=m mx>1 TQ ex-MTh 45 c := > r OJ w 8 NL.89.087.01.P2 l TABLE A5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM IU".EER & Kt.tvialfIATIVE SAMPLDG #D DTE #O HTQUE2CY EXIOSURE FATIMAY SNEU3 #D T # M.TSIS SNME IDCATIOS CCUJrITOi FREQ D CT NC/m S,WPIE4. Ingestim Smtunanthly when animals Ganna isotcpic and a. tillk Samles frun milk animals in three locatims are on pasture; crothly I-131 analysis within 5 km distance having the highest dose smumanthly when aniraals potential. If tiere are rme fran which smples at other tines. are en pasture; conthly can be obtained, then me smple frun milk at other tices.animals in each of three areas between 5 to 8 kn distance vien doses are projected gjaMaum to be greater than 1 mrun Mr year Che smple fran milk animals at a ccntrol locacim greater than 30 kn distant in a minimal wird direction. Ib smples are required if trere are no milk animals frun which smples can be obtained within tie 8 kn distance. Smple saniannually. Gana isotopic analysisb. Fish ard One smple representing each camercially and m edible portions.Invertebrates recreatimally inportant species in vicinity of plant discharge area. l One smple representing each carcreially arx! recreationally inportant species axi within the main ecoling reservoir. One smple representing the sme species in areas not influenced by plant discharge. @> c3 ' mZ> 7 C)~>1 "r am mE' YZ 4 O > -r:W O 65 Rev. 4 NL.89.087.01.P2 l TABLE AS-1 (Continued)' RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER &EEPRESSTAT1YE EXEOSURE PATIMAY SMPIES #O SAMPLDU RO TITE RO FREQUEICT ne/m smrIE stuu locATIos cinLTIai mEQUEILT T #ULYSISc. Food (be smple of each principal class of food At time of harvest . Gama isotcpic analysis Products products frm any area that -is irrigated by. on edible portion, water that receives the min cooling reservoir discharges.Sxples of three different kinds of broadleaf timthly. Ger.n Isotopic and vegetrtion grwn nearest each of two different I-131 analysis. offsite locatim s of highest predf:ted annual average ground level D/Q if milk smpling is not perfomed. One smple each of the similar broadleaf timthly. Gama Isotopic and vegetatico grown 15 to 30 km distant in a I-131 analysis. minicni virri direction if milk smpling is not perfomed. t h :- ,*@t i@ @tb{v s k NL.89.087.01.P2 66 Rev. 4 E (O-q_ ~~inTEseHT A3 ST HL AEG H TABLE AS-1 PAGE c 9 0F/o Ct TABLE NOTATIONS( ) Specific parameters of distance and direction sector f rom the centerline of one reactor, and additional descriptioa where pertinent, shall be provided for each and every sample location in Table B5-3 la a table and figure (s) in this document. Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specification For Nuclear Power Plants," October 1978 and to Radiological Assessment Branch Technical Position, Revision 1 November 1979. Deviations are permitted f rom the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automat.c sampling equipment. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.3. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and , locations may be chosen for the particular pathway in question and l appropriate substitutions made within 30 days in the Radiological ) Environmental Monitoring Program given in this document. Pursuant to Technical Specification 6.14, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in this document including a revised figure (s) and table for this document reflecting the-new location (s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifying the selection for the new location (s) for obtain samples.(2)One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuour.y may be used in place of, or in addition to, integrating dosime.ers. For the purposes of this table, a thermoluminescent dosimeter /iLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for. measuring direct radiation. The 40 stations are not an absolute number. The number of direct monitoring stations may be reduce, according-to geographical limitations. TLD's may be located at nonpressribed distances from the plant due to access limitations. ( Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean ci control samples, gamma isotopic analysis shall be performed on the individual samples, NL.89.087.01.P2 67 Rev. 4 i l k 2 L_ PI. A ntWFOAEN1 A 3 ST HL AE-321/PAGE I?1 0F / CC' TAB 1.E A5-1 TABLE NOTATIONS CONTINUED ('}Ganna isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be att ributable t o the ef f1t ent a f rom the facialty. ( }The " upstream sample" shall be taken at a distance beyond significant=influence of the discharge. The " downstream" sample shall be taken in an area beyond but near the mixing zone. " Upstream" samples in an estuary must be taken f ar enough upstream to be beyond the plant influence. Salt water shall be sampled only when the receiving water is utillred for recreational activities. l (6)A composite sample is one in which the genntity (aliquot) of liquid sampled j is proportional to the quantity of flowing 11guld and in which the methot of sampling employed results in a specimen that la reprimentative of the liquid flow. In this program composite sample aliquota shall be collectedat time intervals that are very short. (e.g., hourly's relative to the compositing period (e.g., monthly) in order to assuro ebtaining a representative sample.( Groundwater samples s'.all be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge propertins are suitable for contamination. ( The dose shall be calculated for the maximum organ and age group, uaing the methodology and parameters in the ODCH. If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvent occurs continually, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products. NL.89.087.01.P2 60 Rev. 4 TABLE AS-2 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS ., LOWER LIMIT OF DETECTION WATER FISH MILK FOOD FRODUCTS SEDIMENT ANALYSIS (pC1/1) AIRBORNE PARTICg)TE OR GASES (pC1/m (pC1/kg, wet) (pC1/1) (pC1/kg, wet) (pCi/kg, dry) Gross Beta 4 0.01 H-3 3000Mn-54 15 130' Fe-59 30 260' Co-58,60 15 130 Zn-65 30 260 iZr-Nb-95 15 I-131 1 0.07 1 60 Cs-134 15 0.05 '30 15 60 150 Cs-137 18 0.06 150 18 60 180 Ba- La-140 15 15 $$Daid, co id>5 j ~ 4 2 o n b ( W f l O j i G l NL.89.087.01.P2 69 Rev. ,* k _ _ _ _ _ . _ e.- .. . . ,. _ -..__...._....._.m_ _ _ _ _ _ _ _ _ _ _ _________.__.___..__..m _ _ . _ _ _ . _~IfiECiiEENT A3 ST HL AE 35'//TABLE A5-2 PAGE -7/ ~ OF ~ /U() TABLE NOTATIONS ( This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.19.1.3. I ) Required detection capabilities for thermoluminescent dosimeteers used for environmental measurements shall be in accordance with the recommendations of Regulatory Guido 4.13. ( }The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactiva material in a sample that will yield a not count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation LLD ='D EV 2.22 x Y a exp (-7(6t)Where: LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume), s = the standard deviation of the background counting rate or of the b counting rate of a blank sample as appropriate. (counts per minute). E= the counting efficiency (counts per disintegration), V= the sample size; (units of mass or volume), 2.22 = the number of disintegrations per minute per picocurie, Y= the fractional radiochemical yield, when applicable, 9L= the,{adioactive decay constant for the particular radionuclide (s ), and 6t a the elapsed time between environmental collection, or end of the sample collection period, and the time of counting (s). Typical values of E, V, Y, and t should be used in the calculation. NL.89.087.01.P2 70 Rev. 4-~~l _.. g g 3 3-l ST HL AE STH~PAGE '1 ~3 0F M l TABLE AB;2 TABLE NOTATIONS (CONTINUEDJ It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (af ter the f act) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample. sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unschievable. In such cases, the contributing factors shall be identified and described in the Annual Radiolegical Environmental Operating Report pursuant to Technical Specification 6.9.1.3. ( LLD for drinking water samples. If no drinking water pathway exista, the LLD of gamma isotopic analysis may be used. l 5 l NL.89.087.01.P2 71 pey, 4 L' ATIACHMENT A 3 ST HL AE 3gl/PAGE ~23 0F lo A 1^'>v .lf >v O O O 8 d# -o. 9 M n d N 8% Nv 4 M^N m O O w* c n t. o I E M 6b A.g 4J -H g -M g =. 88 8 8 8 g g 5 - seaeg O o p A& g cm o M o M o o N o' n-_ ]m I 4 V sn A Z (3 N 5 8 E k a$ H o N a H m M* b h V p=C : .b M O g g e M ll a ' fa O .g O N NN wO M Y u on. O O O O O O O. N O O O.D ug. O- O o o o O O m m O % .% o, O, 4 o, m .m 4 N ~ ~ @ g s, R ;y v N r'. N N Ao.'O N -M m 4 W M4 m T 4 % e o e b m m md m i i #T T $W "..* Tm Tm }s 7 *d E eE a N e U b U o N a N H I U U e se d a p- . _ . . . . . . . . ~ . _ . . . . . . , _ _ . - , . - , _ _ . _ . . _ . , , , , . _ . _ _ _ _ _ _ _ _ . _ . , _ . _ . _ . . _ . _ _ _ _ _ _ _ _ _ _ _ -. .r ATTACHMENT /43 ST HL AE39if i_ PAGE n u opyoQ J SECTION 3/4.12.2 LAND USE CENSUS NL.89.087.01.P2 73 Rev. 4- , . . - _ - , . _ _ . _ _ . _ - _ . _ _ . ~ . _ . _. . - . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ ATI ACHMENi~h 3 ST-HL AE 3c/l PAGEJ75 0F h7(1 hisND USE CF.NSUS As part of the Hsdiological Environmental Monitoring Program, Control 3/4.12.2 requires that a land use census be conducted annually during the growing season to identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest the nearest realdence, and the nearest garden of greater than 50 mmjlkanimag,) (500 ft producing broad leaf vegetation. The land census ensures that changes in the use of area beyond the site boundary are identified, and appropriate modification to the monitoring program and dose assessment models are made, if necessary. This census satisfies the requirements of Section IV.B.3 of Appendix 1 to 10CFR Part 50. For the pu, pose of conducting the land use census as required by Control Surveillance Requirement 4.12.2, station personnel should determine what survey methods will provide the necessary results considering the type of information to be collected and its ute. For example land use census resultu shall be obtained by using a survey method, or combination of methods, which may include, but are not limited to, door-to-door surveys (i.e., roadside identification of locations), aerial surveys, or by consulting local agricultural authoritien. Control 3.12.2.b requires that new locations identified from the census that yield a calculated done or dose commitment 20 percent greater than at a location from which samples are currently being obtained be added within 30 days to the REMP. These new locations shall be added to the Sampling program only if reliable sampling of the affected pathway (n) can be devised. NL.89.087.01.P2 74 Rev. 4 gITC3Ed5Ili A3 . 1 ST HL AEGEH RADIOLOGICAL ENVIRONMENTAL MONITORING PAGE.34 0F _f a o- - 3/4.12.2 LAND USE CENSUS CONTROLS 3.12.2 A Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the gearest residenge, and the nearest gardena of greater than 50 m (500 ft ) producing broad leaf vegetation. APPLICABILITY: At all times. ACTIONa. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Control 4.11.2.3, purauant to Technical Specification c.9.1.4, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report. b. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Control 3.12.1, add the new location (s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCH. The sampling location (s) excluding the control station location, having the lowest calculated done or dose commitment (s),via the same exposure pathway, may be deleted from this monitoring program after 0ctober 31 of the year in which this Land Use Census was conducted. Pursuant to Technical Specificatien 6.14, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with information supporting the change in sampling locations.c. The provisions of Control 3.0.3 are not applicable.Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Controls for broad leaf vegetation sampling in the REMP shall be followed including analysis of control samples.NL.89.087.01.P2 75 Rev. 4 i' l'Ai1ACHMENT A3 ST HL-AE-35'// PAGE 'T7 0F lo n-- a i l RADIOLOGICAL ENVIRONMENTAL MONITORING [ SURVEILLANCE REQUIREMENTS 4.12.2 The Land Use Census shall be conducted at least once per 12 months using that information that vill provide the best reeults, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities, as described in the ODCH. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3. 1 NL.89.087.01.P2 76 Rev. 4 l ATTACHMENT A3 ST HL AE 321/ PAGE 7 9 0F /n A]i 1 I SECTION 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM t (+h NL.89.087.01.P3 77 Rev. 4 . a. . c .. . . . _ . . _ . _ . . _ , - ~ .. _ , . , _ ____ _. _ _._. __..._,..._._, . . . _ . . - _ .. - - _ m AT1ACH_ MENT ST HL AE-PAGE M 9-- 0F # &RADIOLOGICAL ENVIROI: MENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Connission, that correspond to samples required by the REMP. APPLIC/iBI LITY : At all times. ACTIONa. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Connission in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3. b. The provisions of Control 3.0.3 are not applicable.SURVEILLANCE REQUIREMENTS 4.11.3 The Interlaboratory Comparison Program is described in the ODCM. A summary of the results obtained an part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.3. NL.89.087.01.P3 78 Rev. 4-s. x ..: . . s A 3 6( nL AE 3r//PAGE 90 0F /0 o I i l BASES FOR l SECTIONS 3.0 AND 4.0 l CONTROLS AND^SURVEILLANCE REQUIREMENTS 5 i k I P.NL.89.087.01.P3 79 pey, 4ATTACHMENT A.3 ST+HL AE Mll INSTRUMENTATION PAGE 971 0F /0o ! PASES 1/4.3.3.9 (Not Used) 3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the teleases of radioactive materials in 11guld effluents during actual or potential releases of liquid effluents. The Alarm / Trip' Setpoints for these instruments. shall be calculated and adjusted in accordance with the methodology and parameters in this document to ensure that the alarm / trip will occur prior to exceeding the limits of 10CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10CTR Part 50. , 3/4.3.3.!! RADICAFTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioective materials in gaseous effluent during actual or potential raleases of gaseous effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordence with the methodology and parameters in this document to ensure that the alarm / trip will occur prior to exceeding the limits of 10CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10CTR , Part 50. The sensitivity of any noble gas activity monitors used to show compliance with the gaseous effluent' release requirgments of Control 3.11.2.2.shall be such that concentrations as low as 1 x 10 pC1/cc are measurable.(t l L l 1 l i l l NL.89.087.01.P3 80 Rev. 4.- - -. - .a__ _.-....a.. -.-_ .- . . _ _ - . - - - _ . . . - . , , , _ - , - ~ ,, a-_/d fACHMENT A3 ST HL AE 3f //3/4.11 RADIOACTIVE EFFLUENTF PAGE R A 0F /0 o BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATIO!J This Control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10CFR Part 20, Appendix B. Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section II. A design objectives of Appendix I, 10CFR Part 50, to a HEMBER OF THE PUBLIC, and (2) the limits of 10CFR Part 20.106(e) to-the population. The concent rat ion limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its HPC in air (suometsion) was converted to an equivalent concentration in water using the methode described in International Commission on Radiological Protection (ICRP) Puslication 2. This Control applies to the release ci radioactive materials in liquid~effluents from all units at the site. The required detection capabilities for radioactive materirls In liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). 6 Detailed discussion of the LLD, and other detection limits can be found in ' NASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal . Chem. 40, 586-93 (1968), and Hartwell, J. K.," Detection Limits for Radioanalytical Count ing Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).3/4.1J2 1.2 DOSE i Control is provided to implement the requirements of Sections II.A. 10 J IV.A of Appendix I, 10CFR Part 50. The Control implements the auidet set forth 14 Section II.A of Appendix I. The ACTION statements provide the reanired operating flexibility and at the same time implement the guides-66t for.a in Section IV.A. of Appendix I to_ assure that the releases of tr41oactive materla! In liquid effluents to UNRESTRICTED AREAS will be kept "aa low.as is reasonably achievable." The dose calculation methodology and parameters in this documeni implement the requiremente in Section III. A of Appendix I.that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a HEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in thic document for calculating-the doses due to the actual release rates of radioactive materials in liquid' effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50 Appendix I" Revision 1 October 1977 and Regulatory Guide 1.113, " Estimating i Aquatic Dispersion of Effluenta from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I" April 1977.NL.89.087.01.P3 81 Rev. 4 i I L,Dh,i.,t[IT3 ' Sbbl AE 32/1 PAGE 3 3 0F / oq 3/4.11 RADI0 ACTIVE EFT 1.UENTS BASES 3/4.11.1.2 DOSE (Continuedl This Control applies to the release of radioactive materials in liquid effluents from each unit at the site. l 3/4.11.1.3 LIQUID WASTE PROCESSING SYSTEM i The OPERABILITY of the Liquid Waste Processing System ensures that this system will be available for use whenever liquid effluents require treatment 4. prior to release to the environment. The requirement that the appropriate portions of this system be used when speelfled provides assurance that the releases of radioactive materials in liquid effluents will be kept 'as low as is reasonably achievable." This control implements the requirements of 10CFR50.36a, General Design Criterion 60 of Appendix A to 10CFR Part 50 and the design objective given in Section II.D of Appendix 1 to 10CFR Part 50. .The specified limits governing the use of appropriate portions of the Liquid Waste Processing System were specified as a soltable fraction of the dose l design objectives set forth in Section II. A of Appendix I, 10CFR Part 50, for , liquid effluents. This Control applies to the release of radioactive materials in liquid : effluents from each unit at the site. 3/4.11.1.4 LIQUID HOLDUP TANKS The tanks covered by this Control include all those outdoor radwaste tanks . that are not surrounded by liners, dikes, or valla capable of holding the tank , contents and that do not have tank overflows and surrounding area drains connected to the Liquid Vaste Processing System. Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water s sly and the nearest surf ace water supply in an UNRESTRICTED AREA. . 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This Control is provided to ensure that the done at any time at and - beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10CTR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous ef fluents will not resalt in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of NL.89.087.01.P3 82 Rev. 4~gG6f63 ST. w AE 3 dl 3/4.11 RADIOACTIVE EFTLUENTS PAGE J2 4 = 0F =u-u BASES 3/4.11.2.1 DOSE RATE (Continued) 10CFR Part 20 (10CTR Part 20.106(b)). For HEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that HEMBER OF THE PUBLIC will usually be suffleiently low to compensate for any increase in the atmospheric dif f usion f actor above that f or the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in this document. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a HEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the whole body or to less than or equal to 3000 mrems/ year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/ year.This Control applies to the release of radioactive materials in gaseous affluents from all units at the site. The required detection capabilities for radioactive materials in gaseous vaste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Proceoures Manual, HASL-300 (revised annually), Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., ' Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). 3/4.11.2.2 DOSE - NOBLE GASES This Control is provided to implement the requirements of Sections II.B. III.A and IV.A of Appendix I, 10CFR Part 50. The Control implements the guides set forth in Section !!.B of Appendix I. The ACTION statements provide the required operation flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guidea of Appendix 1 be shown by calculational procedures based on models and data such that the actual exposure of a HEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in this document for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are-consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Relvases of Reactor Effluents for the Purpr2e of Evaluating Compliance with 10CFR Part 50, Appendix I" Revision 1, Octucer 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmosnheric Transport and Dispersion of Gaseous Effluents in Routive Releases f rom Light-Water Cooled Reactors". Revision 1, July 1977. The ODCH equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. NL.89.087.01.P3 83 key. 4 -. _ _ . _ _ _ _ _ . _ _ . _ _ ~_ - _ . .. ~.. _ . . _ . F~KiiACHMENT 43 ST HL AE-M 'I 3/4.I1 RADIOACTIVE EFFLUENTS PAGE y 0F_ M BASES This Control applies to the release of radioactive materials in gaseous effluents from each unit at the site. 3/4.11.2.3 DOSE - 10 DINE-131, IODINE-133 TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM This Control is provided to implement the requirements of Sections II.C. III.A and IV.A of Appendix I, 10CFR Part 50. The Controls are the guides set forth in Section II.C. of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guidea set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous ef fluents to UNRESTRICTED AREAS will be kept "as low as . is reasonably achievable." The ODCM calculational methods specified in the l Surveillance Requirements implement the requirements in Section III.A of ' Appendix I:that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual l exposure of a member of the public through appropriete pathways is unlikely to ' be substantially underestinated. The ODCM calculational methodology and parameters for calculating the doses due to the actual releass rates of the subject materials are consistent with the methodology provided in Regulatory l Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I" Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in l Routine Releases from Light-Water Cooled Reactors", Revision 1, July 1977. ' These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man,.in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure to man. This Control applies to the release of radioactive materials in gaseous effluents from each unit at the site. 3/4.11.2.'4 GASEOUS VASTE PROCESSING SYSTEM The OPERABILITY of the GASEOUS WASTE PROCESSING SYSTEM ensures that the systems will be available for use v'enever gaseous effluents require treatment prior to release to the environment. The requirement-that the appropriate portions of this system be used when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This Control implements the NL.89.087.01.P3 84 Rev. 4 A All ACHMENT A 3 SDHL AE s'r/ I PAGE _.21_0F _ /na 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.2.4 GASEOUS WAS!EP ,]CpESSING SYSTEM (Contir aed) requirements of 10CFR50.56a, Ge.'er =1 Design Criterion 60 of Appendix A to 10CFR Part 50 and the design obj verive given in Section II.D of Appendix I to 10CFR Part 50. The specified lit. its go retning the use of appropriate portions of the system were specified as a suitatle fraction of the dose design objectives set for th in Se tion II.B of Appendix I, 10CTR Part 50, for gaseous effluents. This Control applios to the release of radioactive material in gaseous effluents from each unit at the site. 3/4.11.4 ?OTAL DOSE This Control la provided to meet the doae limitation of 40 CFR Part 190 that have been incorporated into 10CFR Part 10 by 46 FR 18525. The Control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactisity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to itse than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design obj ectives of Appendix I, and if direct radiat ion doses f rom the reactor units and outside storage tanks are kept small. The Spe:ial Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear Iuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the reouirements of NL.89.087.01.P3 8b Rev. 4 ATTACHMENT 43 3/4.11 RADIOACTIVE EFILUENTS pg t BASES 3/4.11.4 TOTAL DOSE (Continued) 40CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40CFR Part 190 and does not apply in any way to the other requirements for dose limitation of 10CFR Part 20, as addressed in Csatrols 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. NL.89.087.01.P3 86 Rev. 4 1 AITACHMENT A3 ST HL AE-3F// PAGE 5)R OF /00 3/4.12 RADIOLOGICAL ENVIRONMENTAL HONITORING BASES 3/4.12.1 HONITORING PROGRAM The-Radiological Environmental Monitoring Program required by this Control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to i the highest potential radiation exposure of HEMBERS OF THE PUBLIC resulting from the plant operation. This monitoring program implements Section IV.B.2 i of Appendix I to 10CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental , exposure pathways. Guidance for this monitoring program is provided by the l Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience. l The' required detection capabilities for environmental sample analyses are , tabulated in terms of the lower limits of detection (LLDs). The LLDs required by this document are considered optimum for routine environmental measurements industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual. HASL-300 (revised annually), Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company-Report ARH-SA-215 (June 1975). 3/4.12.2 LAND USE CENSUS , This Control is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Honitoring Program given in the ODCH are made if required by the results'of this census. The best information from the door-to-door survey,-from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I t 10CFR Part 50. Restricting 2 the census to gardens of greater than 50 m 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 child. To determine this minimum garden size, the ; following assumptions were made: (1) 20% of the garden was used for Frowing -l board leaf vegetation (i.e , similar to lettuce and cabbage), and (2) a 2 vegetation yield of 2 kg/ml Il: I l 1. NL.89.087.01.P3 87 Rev. 4 I~TTACHMENT A 43 ST HL AE 33//PAGE 7'T OF 100 __ 3/4.12 RADIOLOGICAL ENVIRONMENTAL HONITORING BASES 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurement of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix ! to 10CFR Part 50. 1 ( 1 i NL.89.087.01.P3 88 Rev. 4 ATTACHMEt1T A2 ST HL AE 3F// PAGE M n L. 0FJoo- t a I i 1 SECTION 5.0 2 DESIGN FEATURES , f t t 3 Y F i 1- NL;89.0B' 01.P3 89 Rev. 4 -~ . . . _, ...__ - . , . - . _ . . . _ . , _ _ . - . . . . _ _ _ _ _ _ _ . _ , - . _ . - . . _ . . . _ _ , . . . . . . . - - . - , . - _ _ _ _ . , . . . . _ - . . -ATTACHMENTA3 ST HL AE 3 ell PAGE o / OF 10 0 5.0 DESIGN FEATURES 5.1 SITE HAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADI0 ACTIVE GASEOUS AND-LIQUID EFFLUENTS 5.1.3 Information regarding radioactive gaseous and liquid effluents, which will allow identification of structures and release points as well as definition of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to HEMBERS OF THE FUBLIC, cha11 be as shown in Figures $.1-3 and 5.1-4.The definition of UNRESTRICTED AREA used in implementing these Controls has been expanded over that in 10CFR 20.3(a)(17). The UNRESTRICTED AREA boundary may coincide with the Exclusion (fenced) Area boundary, as defined in 10CFR 100.3(a), but the. UNRESTRICTED AREA does not include areas over water bodies. The concept of UNRESTRICTED AREAS, established at or beyond the SITE BOUNDARY, is utillr.ed in the Controls to keep levels of radioactive materials in liquid and gaseous effluents as low as is reasonably achievable, pursuant to 10CFR50.36a. l I I D NL.89.087.01.P3 90 Rev. 4 s TTTADRMENT7i? a a L r ST HL AE-33// 5 6 h fi PAGE 9't 0F lo o I c e !O . 3 h;86@v" W g; n$ s m, e$8'f a t "5!E eG"/e I y ....N 4 re*-. N 9be 3yg CW ts Uh hl / / -mj / 7 W$'_ ! r-il ! / *( .: N s up,i s wa 5 -po f, I Jg,, ' 8 S L _ m xg. ._~ g=m c nw i< i g,u [ n 1. ' I,,1 [ m W R 5.: y ,E I o g E c 5 0 ' f E E N' .!5 a B Um / '4.11 t I t - 5 m E 5 8 5 ( SOUTH TEXA$ - UNITS 1 & 2 I ATTACHMENT A 3 ST HL AE-37il ( PAGE 112__0F / O n i I^- :y o . ( / 1 ,S / ~' ) Nic i,x~M ,$g. ,3 l M lf i'f 4{Fl; :,M 5 . /f'\ '\ .) ' .- ~7- ^ l y, l _ E/I h ; E( l ,g l ~, , W$ [ 8 8$ (--( ^: J . 11 E A 7 E hi b" E .l i0 m p ( SOUT H T E X AS - UN115 1 & 2 92 I.___._.._~_.____-_._._..__.__.___.--__._ .. AlTACHMENT. A3 ST HL AE 39// ,.]}GF %__ ____ 0F J C O _U $#W -99 g - O su.g 18a ba 2" n o E E / wanw a'8n g g =2 " >,G y s a o a !. - No$o B $ c .,a 5 e u s e MMMM E Et% N RG H in H W'{W M 119 4 RI 7 o;;g mQ s f!O $/N' Il $ 9 . s. sc B?E *) U O pe* ~-Y14 OD A*CO Ob ws 4 yd $8 j Nt" 22 % b. 6 O!"k /, ? ? aM (*b2 w -9 m Eno M w ( m - g; / m Eu a : 9 li _- og y E na- , J/EE 5";5 8 [~ lit o E E. :i so ,. . Z $*' 5 ;_ :;th L_J( o l-s _ g- r _ mw mI - 2 %f o$ u - E Es' a- 0 3 . E, fl! $" n' !a! ! ge u . \ m w 3 n 13 m G E G" 5o b e 59$ W 5, hO / i n un# y1 ll- s N I i m 50VIH TEXA5 - UN!151 L 2 93 v. O -.r S ! = ~4_. s . 4x. . ~ . . . . . . . . . . . . . .3 !. -. N % / i ,i ' t~- P . j ' E ! C - 3 l g U O p-ghhc[) Ns : .- .. . ,,~ ~ .. . ? -- ' / ; .I / % ~x ! '7: ijl i ;j' N -.)- - - - ~ ' .. ,t ;( .... . 3 'h 1,. f/~ ~ ~ ~ ,c F 3 il i \ f' 1 l5 i l i ,~~ i {- - . . ~ . ,l - ,- 3 .u, m >. i.. ,i -~ (.~. c {I - ~. . : ._. Ak t %[m. '5d/ *The UNRESTRICTED AREA consists of ,jsf the FH 521 right-of-way and the A b. r area beyond the SITE BOUNDAPY. / A*Edf'I SOUTH TEXAS PROJECT {Q q '<$UNITS 1 & 2 'I hy~)FIGURE 5.1-4 - UNRESTRICTED AREf* AND SITE BOUNDARY FOR RADICACTIVE LIQUID EFFLUENTS L 1 U iS bifidEiiT l 3 ST HL AE 37// \ PAGE CIA OF /0 v SECTION 6.0 ADMINSTRATIVE CONTROLS NL.89.087.01.P3 95 Rev. 4 ST HL AE 3s/l PAGE cr7 0F 10 C3 I ADMINISTRATIVE CONTROLS SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTq 6.9.1.3 Routine Annual Radiological Environmental Operating Peports covering _the operation of the unit during the previous calendar yest 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 and shall include copiew of reports of tbc preoperational nadiological Environmental Monitoring Program of the unit for at least two years prior to initial criticality. The annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies and with operational controls, as appropriate, and with previous environmental surv1111ance 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 Census required by Control 3.12.2, The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the Offsite Dose Calculation Manual as well as summarized and tabulated results of these analysea and measurements in the format af the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion wiih the report, the report shall be subraitted noting and explainit.g the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following a summary description of the Radiological Environmental Monitoring Programs at least two legibla mapscovering all sampling locations keyed to a table giving distances and directions from the centerline of one reactors the results of licensee participation in the Interlaboratory Comparison Program and the corrective action taken if the specified program is not being performed as required by Control 3.12.31 reasons for not conducting the Radiological Environmental Monitoring Program as required by Control 3.12.1, and discussion of all deviations from the sampling schedule of Table 3.12-1; discussion of environmental sample measurements that exceed the reporting levels of Table 3.12-2 but are not the result of plant effluents, pursuant to ACTION b. of Control 3.12.1; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.*A single rubmittal may be made for a multiple unit station. **0ne map shall cover stations near the SITE BOUNDARY: a second shall include the more distant station =.NL.89.087.01.P3 96 Rev. 4 FA h M u mAf -.fACHMENT K3 ST HL AE-3sn PAGE ITV _0Fl oo i_a i ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT6.9.1.4 Routine Semiannual Radioactive Effluent Release Reports covering the operation of the uni' during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality.The Semiannual Radioactive Effluent Release Reports shall include a s2mmary of the quantities of radioactive 11guld and gaseous effluent 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," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. For solid wastes, the format for Table 3 in Appeadix B shal1 be supplemented with three additional categories: class of solid wastes (as defined by 10CFR Part 61), type of container (e.g., LSA, Type A. Type B, Large Quantity) and SOLIDITICATION agent or absorbent (e.g., cement, urea formaldehyde). The Semiannual Radioactive Effluent Release Report to be arbmitted within 60 days af ter January 1 of each year shall include an annual summary of hourly, meteorological dat a collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric etability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and xtmospheric stability.* This same report shall include an assessment of the radiation deses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous efflusn.s to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure (5.1-3}) during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time, and location, . hall be included in these reports. The meteorological conditions cots 2rrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in this document.*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; however, for units with separate radwaste nystems, the submittal shall specify the releases of radioactive material from each unit. **In lieu of submission with the Semiennual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of reqaired meteorological data on site in a file that shall be provided to the NRC upon request.NL.89.087.01.P3 97 Rev. 4 r------.- _, ATTACHMENT A ?S1 HL-AE 3g n PAGE M et- 0F__/n n=ADMINISTRATIVE CONTROLS SEMIANNUA1. RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) The Semiannual Radioactive Effluent Release Report to be submitted aithin 60 days af ter January 1 of each year shall also include an assessment of radiation doses to.the likely most exposed MEMBER OF THE PUBLIC f rom reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direr.t radiation, far the previous calendar-year to show conformance with 40CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the_ _ dose contribution f rom liquid and gaseous ef fluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.The Semiannual Radioactive Effluent Release Reports shall include a list and. description of unplanned releases f rom the site to UNRESTRICTED AREAS of radioactive-materials in gaseous and liquid efflucnts made during the reporting period.'The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to this document, pursuant to Technical Specifications 6.13 and 6.14 as well as any major change to Liquid, Gaseous, or Solid Radwaste Treatment Systems. It shall also include a listing of new locations for dose calculations and/or environmenta! monitoring identified by the Land Use Census pursuant to Control 3.12.2.The Semiannual Radioact!ve Ef fluent Release Reports shall clso include the following an explanation.as to why the inoperabilit, of liquid or gaseous effluent monitoring instrumentation was not cortcuted within the time specified in-Control,3.3.3.10 or 3.3.3.11, respectively; and description of the events leading to liquid _ holdup tanks or gas stora ge tanks exceeding the limits ofjTechnical Specification 3.11.1.4 or 3.11.2.f respectively, f NL.89.087.01.P3 98 Rev. 4 Aa.S ATTACHMENT q3 ST-HL AE-37/t ; PAGE la n _ op j o o -ADMINISTRATIVE CONTROLS 6.15 MAJOR CHANGES TO LIQUID AND GASEOUS RADWASTE TREATMENT SYSTEMS6.15.1 - Licensee-initiated major changes to the Radwaste Treatment Systems ,(11guld and gaseous):a. Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the PORC. The discussion of each change shall contain: 1) A_ summary of the evaluation that led to the determination that the change could be made in accordance with 10CFR50.59; 2) Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental.information; 3)~ A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;4) An evaluation of the change, which shows the predicted r61 eases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the License application anc amendments-thereto; 5) An evaluation of the change, which shows the expected maximum ,exposures to-a HEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the License application and amendments thereto6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents to the actual relea3as for the period prior to when the change is to be made 7) An estimate of the exposure to plant operating personnel as a result of the changes and ll8) Documentation of the' fact that the change was reviewed and found acceptable by the PORC.lb. Shall become effective after review and acceptance by the FORC.Licensees may chovao to submit the ir; formation called for in this Specification as part of the annual FSAR update.NL.89.087.01.P3 99 Rev. 4-}}

ML20081M621

Text

1.0 INTRODUCTION

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