ML20126B871

Proposed TS Bases 3/4.11.1.3 Deleting Liquid Waste Treatment & TS Bases 3/4.11.2.1 Deleting Dose Rates & Moving Info to ODCM

ML20126B871
Person / Time
Site:	Farley
Issue date:	12/17/1992
From:	SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20126B870	List: ML20126B866 ML20126B871
References
NUDOCS 9212220256
Download: ML20126B871 (25)

Text

_

ATTACIIMENT 2 Revised Proposed Changes to the Farley Units 1 and 2 Technical Specifications jg2220256921217 p ADOCK 05000348 PDR

Farley Unit 1 Revised Proposed Changed Technical Specification Pages i

i '

EmiledEEC B 3/411-2*

6-15a*

6-15b" 6-22*

i R

d I

• Supersedes proposed changed technical specification page submitted by Southern Nuclear Operating Company letter dated August 24,1992.

Supersedes proposed changed technical specification page submitted by Southern Nuclear Operating Company letter dated June 23,1992,

i is I

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Unit 1 Marked Pages 4

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2 RADI0 ACTIVE EFFLUENTS BASES i

i l 3/4.11.1.3 LIQUID tA5TE TtEATMENT Thl6 sPet tft C At10h 0,eldted, Refer Mht ObfW DogMCM0:1 MaM e

{' The OPERABILITY f the liquid r sta treatment sy ensures thaC is'

! system will be avai able for use r liquid eff1 require trpa j prior to release the environment The requirement t the appespria i portions of this ystem be used specified provi , assurance that releases of r osctive materials n liquid effluen will be kept " law as

is reasonably hievable". This ification imp ements the requi nts of j 10 CFR Part .36a, General De gn Critarion 60 Appendix A to 10 R Part 50

and the des en objective giv in Section 11.0 Appendix ! to 1 CFR Part 50.

l The specif ed limita governi the use of app riata portions o the liquid i radwesta reatment system specified as a suitable fraction f the dose design jectives set fo in Section II.A f Appendix 1, 10 R Part 50, for liquipeffluents. OELgrgD l 3/4.11.1.4 LIQUID HOLDUP TANKS fen time.G l Restricting the quantity of radioactive material contained i specified i tanks provides assurance that in the event of an uncontrolled rol e of the

! tanks' contents, the resulting concentrations would be less than .' limits of l 10 CFP, P:n _'", .Zd: C, idi: !!, C:1 r. *, at the nearest potab,e water l

supplyandthenearestsurfacewatersupply/inanunrestrictedarea. -

/ 10 CM Part20; APPCndil 3 3/4.11.2 GASE005 EFFLUENTS s 20@0W.M 3 No Tabie. pcum3ra@htmn 7 3C.o 23 3/4.11.2.1 DOSE RATE TNs sm hcotion dektel. ReYeridhe Ottdte Dese Ca ktA-lcttion Ma ntu l.

This specific ion is providad ensure that the se at any t1ae a ,the site boundary f gaseous effluent from all units on sit.e will be ithin the annual dose inits of 10 CFR P 20 for unrestri areas. The 1 dose limits a the doses associa with the conce rations of 10 CF Part 20 Appandix 8. T le II, Column 1. hose limits prov reasonable ass ance that radios ive material disc rged in gaseous e luonts will not suit in the exposu of an individual n an unrestric area, either wi n or outside the site undary, to annual average concentra ons exceeding t limits specifie in Appendix 8 T le II of 10 CFR P t 20 (10 CFR Par 20.106(b)).

For i viduals who may a times be within site boundary, occupancy of the i ividual will be s ficiently low to ompensate for any increase in the ateo heric diffusion f ctor above that f the site bounda . The specified rol ase rate limits trict, at all ti , the correspond gamma and beta d a rates above bac round to an indiv dual at or beyond site boundary ss than or equal 500 ares / year i, the. total body or to less than or 1 o 3000 ares / year the skin. Thes release rate lie s also restrict, all times, the co responding thyroi dose rate above ckground to an i ant via '.he cow-mil infant pathway,to ess than or equa to 1500 aren/ yea for the nearest c to the plant. OE4.tTED FARLEY-UNIT 1 L 3/4 11-2 AfEMBENT IE). 96" l

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4 ADMINISTRATIVE CONTROLS i

i b. In Plant Radiation Monitorine

! A program which will ensure the capability to accurately determine the airborne iodine concentration in certain plant areas where

{

personnel may be present under accident conditions. This program

! shall include the following:

{ (1) Training of personnel, t

(ii) Procedures for monitoring, and j (iii) Provisions for maintenance of sampling and analyses equipment.

1 i c. Secondary Water Chemistry i A program for monitoring of secondary water chemistry ta inhibit j steam generator tube degradation. This program shall include:

l (1) Identification of a samp?ing schedule for the critical j variables and the control points for these-variables, i

j (ii) Identification of the procedures used to meas wa the values of i the critical variables, (iii) Identification of process sampling points, including monitoring ,

j the condenser hotwells for evidence of condenser in-leakage. 1 (iv) Procedures for the recording and management of data,  !

l (v) Procedures defining corrective actions for off-control point-chemistry conditions, and  ;

(vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiata corrective action,

d. Post-accident Samplina A program which will ensure the capability to obtain and analyze l reactor coolant, radioactive iodines and particulates in plant l gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the training of personnel, the procedures for sampling and analysis and the provisions for maintenance of sampling and analysis equipment.

2.)t *s- Insect 3 i

FARLEY-UNIT 1 6-15 #ENOMDIT N0. :

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=

INSERT 3

e. Radioactive Effluent Controls Proaram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the shall be implemented by operating procedures, and (3)

ODCM, shall inc(2)lude remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

i) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCH, at 4 t'tme.s

11) Limitations /on the concentrations of radioactive material released in liquid effluents to unrestricted areas conforming to 10 Cin P.;rt 20, Appendix B, T:h': !!, C h , 2,q gg tii) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.100 and with the methodology and parameters in the ODCH, L . 20.13 02, iv) Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive mater'als in liquid effluents released from each unit to unrestricted areas conforming to Appeadix I to 10 CFR Part 50, v) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, vi) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity 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 !

to 10 CFR Part 50, at all kg; cenc.cnt<wtt'ons of vii) LimitationsAon the doce r:te^re:ulting 're: radioactive material released in gaseous effluents to areas beyond the i site boundary conforming to the deses-asseehted with 10 CFP, het-20r-Appendix B, T Me-14, Cel'ra 1,

% Inse/t 3B 1

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! ten times the concentrations stated in 10 CFR Part 20, ,

1 Appendix B (to paragraphs 20.1001 2042401), Table 2,  !

! Column 2, ,

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i l_ INSERT 38 i

ten times the concentrations stated in 10 CFR Part 20, 3 Appendix l(toparagraphs 20.1001 --20.2401), Table 2,

Column 1, i

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At any time, ten times the concentrations-stated in 10 CFR-t i

Part 20,_ Appendix B (to paragraphs 20.1001 - 20.2401), Table 2, i

Column 1, corresponds to a dose rate of 500 mrem / year total effective dose equivalent.

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), ADMINISTRATIVE CONTROLS 3

j 6.12 HIGH RADIATION AREA

20. n b ot W)

6.12.1 I ieu of the " control device" or "alam signal" . required by paragrapn 20.20Mc)[J)- of 10 CFR 20, each high radiation area in which the int radiation is greater than 100 mrera/hr but less than 1000 mrem /hr shall be j barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit.' Any t

individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

1

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

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alams when a preset integrated dose i is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.

1 l c. A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perfom periodic radiation surveillance at the frequency specified by the facility Health Physics Supervisor.

6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved Radiation Work Pemit which shall specify the. dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose'in excess of 1000 mrem" that are located within large areas, such as PWR containment, where i no enclosure exists for purposes of locking, and no enclosure can be reasonably l ccnstructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning )

device. In lieu of the stay time specification o# the RWP, direct or remote (such as use of closed circuit TV cameras) cont'suous. surveillance may be made by personnel _ qualified in radiation protection prc.edures to provide positive exposure control over the activities within the area.

• Healtn. Physics personnel or personnel escorted by Health Physics personnel I shall be exempt frem the RWP issuance requirement during the perfomance of their assigned radiation protection duties, provided they are following plant radiation protection procedures for entry into high radiation areas, the mdiation

" Measurement made at 182 30cm from^ source th+ :f r:dh::t'"'idiaWn h r PeMhtes.t". of tecrn FARLEY-UNIT 1 6-22 #1END4ENT No. 5 7

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Unit 1 Typed Pages i

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i B&(110 ACTIVE EFFLUENTS BASES l

! 3/4.11.1.3 LIOUID WASTE TREATMENT This specification deleted. Refer to the Offsite Dose Calculation Manual.

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! 3/4.11.1.4 LIOUID HOLDUP TANKS i

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the i

tanks' contents, the resulting concentrations would be less than ten times the limits of 10 CFR Part 20, Appendix B (to paragraphs 20.1001 - 20.2401), Table 2 Column 2, at the nearest potable water supply and the nearest surface water y supply in an unrestricted area.

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification deleted. Refer to the Offsite Dose Calculation Manual.

1 5

FARLEY-UNIT 1 B 3/4 11-2 AMENDMENT NO.

. - -. -- - _ . . . . -  :.=. . .. - - - - _

' ADMINISTRATIVE CONTROLS reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

i) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,

11) Limitations at all times on the concentrations of radioactive material released in liquid effluents to unrestricted areas conforming to ten times the concentrations stated in 10 CFR Part 20, Appendix B (to paragraphs 20.1001 - 20.2401),

Table 2, Column 2, iii) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the 00CM, iv) Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas conforming to Appendix ! to 10 CFR Part 50, v) Determination of cumulative and arojected dose contributions from radioactive effluents for t1e current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, vi) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity 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 I to 10 CFR Part 50, vii) Limitations at all times on the concentrations of radioactive material released in gaseous effluents to areas beyond the site boundary conforming to ten times the concentrations stated in 10 CFR Part 20, Ap 20.2401), Table 2, Column 1,gendix B (to paragraphs20.1001 -

• At any time, ten times the concentrations stated in 10 CFR Part 20, Appendix B (to paragraphs 20.1001 - 20.2401), Table 2, Column 1, corresponds to a dose rate of 500 mrem / year total effective dose equivalent.

FARLEY-UNIT 1 6-15a AMENDMENT NO.

b - . . -

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[ ADMINISTRATIVE CONTROLS viii) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary conforming to Appendix I to 10 CFR Part 50, ix) Limitations on the annual and cuarterly doses to a member of the public from lodine-131, locine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaceous effluents released from each unit to areas beyond the site boundary conforming to Appendix 1 to 10 CFR Part 50, and x) Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

f. Radioloaical Environmental Monitorina Proaram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall arovide (1) representative measurements of radioactivity in the lighest potential exposure pathways, and (2) verification of the ,

accuracy of the effluent monitoring program and modeling of 1 environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix ! to 10 CFR Part 50, and (3) include the following:

i) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,

11) A Land Use Census to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the monitoring program are made if required by the results of this census, and lii) Participation in a Interlaboratory Comparison Program 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 environmental monitoring.

g. Solid Radioactive Wastes Control Proaram The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes l

based on demonstrated processing of actual or simulated wet solid l wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71; State regulations; burial ground requirements; and other requirements governing the disposal of solid radioactive waste.

FARLEY-UNIT 1 6-15b AMENDMENT NO.

ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.1601(a) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto i

shall be controlled by requiring issuance of a Radiation Work Permit.* 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.

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable cf them,

c. A health physics qualifieo individual (i.e., qualified in radiation protection )rocedures) with a radiation dose rate monitoring device who l is responsi)le for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physics Supervisor.

6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels suct, that a major portion of the body could receive in one hour a dose greater than 1000 mrem shall be provided witii locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved Radiation Work Permit which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 mrem ** that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device. in lieu of the stay time specification of the RWP, direct or remate (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are following plant radiation protection procedures for entry into high radiation areas.

• • Measurement made at 30 cm from the radiation source or from any surface that the radiation penetrates.

l

FARLEYrVNIT 1 6-22 AMENDMENT N0.

Farley Unit 2 Revised Proposed Changed Technical Specification Pages Revised Pagg B 3/411-2*

6-15a*

6-15b'* I 6 22*

Supersedes proposed changed technical specification page submitted by Southern Nuclear Operating Company letter dated August 24,1992.

" Supersedes proposed changed technical specification page submitted by Southern Nuclear Operating Company letter dated June 23,1992.

Unit 2 Marked Pages

RADIOACTIVE EFFLUENTS BASES 3/4.11.1.3 LIQUID WASTE TREATMENT Th% specthention deleted. Referf.othe 04.h Dose CalcuMon % dual-The OPERABILITY f the 11guld ra aste treatment system ensures that his system will be avai ble for use when er liquid efflu ts require trea ent prior to release t the environment. The requirement hat the appropri e portions of this stem be used whe specified provi s assurance that the releases of radi etive materials n liquid effluen will be kept "a low as is reasonably a levable". This ecification imp ments the requir ments of 10 CFR Part 50 6a, General Desi n Criterion 60 o Appendix A to 10 CFR Part 50 and the desig objective given n Section II.D o Appendix I to 10 CFR Part 50.

The specifie limits governing the use of appro inte portions of the liquid radwaste tr atment system wer ,specified as a itable fraction f the dose design obj ctives set forth n Section II.A o Appendix I, 10 R Part 50, for liquid ef luents, pge g7go 3/4.11.1.4 LIQUID HOLDUP TANKS YenEimes Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled rel ase of the tanks' contents, the resulting concentrations would be less thankhe limits of

-10 CIR Part CC, Apper. dix S, T21- !!, Cci r 3, at the nearest potable water supplyandthenearestsurfacewatersupply[nanunrestrictedarea.

/ /O CFR Part 20, A PPendiX 6 3/4.11.2 GASEOUS EFFLUENTS (to Parayaphs 20.1001- 20.240 th Table 2, C olumn 2, 3/4.11.2.1 DOSE RATE This spec #icotion c/cldeM. ReYe(%-the Ohh Dc5q ddcu(dloA (bMql.

This specification is providedjto ensure that the dose at any time 't tne site boundary f m gaseour effluent's from all units o the site will be within the annual dos limits of 10 CFR art 20 for unrestr cted areas. The nnual dose limits a ? the doses associ ted with the conc trations of 10 CF. Part 20, Appendix B, able II, Cole:mn 1. These limits pro de reasonable as rance that radio tive material dis arged in gaseous ffluents will not result in the expos e of an indhidua in an unrestricte area, either wi in or outsi:1e the site oundary, to annue average concentr ions exceeding t limits specifidinAppendixB,T/bleIIof10CFR rt 20 (10 CFR Pa 20.106(b)).

For i ividuals who may times be within e site boundary, he occupancy of the dividual will be fficiently 16w to compensate for an increase in the atm pheric diffusion actor above that f r the site bound y. The specified re ease rate limits r strict, at all ti s, the correspon ng gamma and bet i se rates above ba ground to an indi dual at or beyon the site boundar to ess than or equal o 500 mrem / year t the total body o to less than or qual to 3000 mrem / year o the skin. Thesc' release rate lim ts also restrict, at all times, the c rresponding thyro dose rate above a:.Kgrounct to an i fant via the cow-mil -infant pathway t less than or equ to 1500 mrem /ye for to the plant. DELETED l the nearest c i

FARLEY-UNIT 2 B 3/4 11-2 AMEMDrnEMT fJO.

l

e ADMINISTRATTVE CONTROLS

b. In-Plant Radiatitm Monitorino A program which will ensure the capability to accurately determine

, the airborne iodine concentration in certain plant areas wheta i personnel may be present under accident conditions. Thi) program j shall include the following:

j (1) Training of personnel, (ii) Procedures for monitoring, and

{

(iii) Provisions for maintenance of sampling and analyses equipment.

c. Secondary Water Ch mistry A program for monitoring of secondary water chemistry to inhibit

steam generator tube degradation. This program shall include

(1) Identification of a sampling schedule for the critical j variables and the control points for these variables, (ii) Identification of the procedures used to sensure the values of

the critical variables, I

(iii) Identification of process sampling points, including monitoring the condenser hotwells for evidance of condenser in-leakage.

(iv) Procedures for the recording and management of data, 4

(v) Procedures defining corrective actions for off-control point-chemistry conditions, and

(vi) A procedure identifying (a) the authority responsible for the l interpretation of the data, and (b) the sequence and timing of i

administrative events required to initiate corrective action.

d. Post-accident Samplina l A program which will ensure the capability to obtain and analyze i reactor coolant, radioactive iodines and particulates in plant gaseous affluents, and containment atmosphere samples under accident-conditions. The program shall include ts. training of personnel.

the procedures for sampling and analysis and the provisions for-maintena3ce of sampling and analysis equipment.

e.,4. 43 Iqsect 3 2

k FARLEY-UNIT 2 6-15 Amendment No. W 6

. - - , - ,- , - ,,,e -

i.

INSERT 3 -

e. Radioactive Effluent Controls Proaram &

A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to +

. members of the public from radioactive effluents as low as reasonably achievable. The program (1) shall- be contained in the ODCM, (2) shall be implemented by operating procedures, and.(3)

shall include remedial actions to be taken whenever the program-limits are exceeded. The program shall-include the following elements:

I i) Limitations-on the operability of radioactive liquid and 4

gaseous-monitoring instrumentation; including surveillance-

_ tests-and setpoint determination in accordance with the 4- methodology in the 00CM, i

od AR twAe.s-ii) Limitationsnon the concentrations of radioactive material 3 released in liquid effluents to unrestricted areas conforming to:10 Of: P:rt 20, ".;;=d5 S, Tel: !!, teler- ? .- %

i iii) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR-iHb446 and with j -the methodology and parameters in the 00CM, t20 f 302.

! iv) Limitations on the annual and quarterly doses or dose l commitment to a member of the public from radioactive

! materials in liquid effluents released from each unit to i unrestricted areas cor. 3 ming to-Appendix I to 10 CFR-Part 50, v) Determination of cumulative and projected dose contributions fro:n radioactive effluents for the current-calendar. quarter and current calendar year in accordance_ with the methodology 7 and parameters in the ODCM at-least every 31 days,

!; vi) Limitations on the operability and-use of the liquid and:

i gaseous effluent treatmentLsystems to-ensure that the-appropriate portions of these: systems are used to reduce- -

releases t,f radioactivity when the projected do~ses.in a 31-day period would exceed!2 percent of the guidelines for the annual dose or. dose commitment

conforming to ~ Appendix I to 10 CFR Part 50,-

at all ttm ede:onc.ejtcAthns vii) LimitationsAon-t c

n _^reculti ; gi r= radioactive

-material-released in gaseous offluents;to areas-beyond the site-boundary onforming to;th: d:::: :=:: ht:d with 10 OfR Pert 10, App =d u ::, T c k !!, 0:1:n 1,- -

Esect 3B

t 1

4 -INSERT 3A j ten times the concentrations stated in 10 CFR Part 20, i Appendix B (to paragraphs 20.1001 - 20.2401), Table 2, i Column 2, 1

e INSERT 3B i ten times the concentrations stated in 10'CFR Part 20, Appendix B (to paragraphs 20.1001 - 20.2401), Table 2, 4

Column 1,*

A T

4

• At any time, ten times the concentrations stated in 10 CFR Part 20, Appendix B (to paragraphs 20.1001 - 20.2401), Table 2,

! Column 1, corresponds to a-dose rate of 500 mrem / year total

- effective dose equivalent.

I 1

Y l

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

1 O L ,

)

ADMINISTRATIVE CONTROLS l 6.12 HIGH RADIATION AREA

2D.UoOK4 -

l 6.12.1 Indieu of.the " control device" or " alarm signal" required by paragraph i l- 20,202(:)(2) of 10 CFR 20, each high radiation area in which the intensity of-i radiation is greater than 100 mram/hr but less than 1000 mram/hr shall be a

barricaded and conspicuously posted as a high radiation area and entran;e.thereto shall be controlled by requiring issuance of a Radiation Work Permit.* Any individual or group of individuals permitted _to enter such areas-shall be l provided with or accompanied by one or more of the following:

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

b. A radiation monitoring device.which continuously integrates-the -

l mdiation dose rate in the area and alams when a preset integrated dose j is received. Entry into such areas with this monitoring device may be i made after the dose rate level in the area has been established and

, personnel have been made knowledgeable of them.

e. A health physics qualified individual (i.e., qualified in radiation

, protection procedures) with a radiation. dose rate monitoring device who I

is responsible for providing positive control' over the activities within

, the area and shall perform periodic radiation surveillance at the l - frequency specified by the facility Health Physics Supervisor.

i 6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one i

hour a dose greater than 1000 mrem shall;be provided _with locked doors to prevent l unauthorized entry, and the keys shall: be maintained under the administrative control of the Shift Foreman on duty and/or health physics supervision. Doors shall remain locked except during periods of access by personnel under an-approved Radiation Work Permit which shall'specify the -dose rate levels in ~the i _immediate work area and the maximum allowable stay time for individuals in-that l area. For. individual areas accessible to personnel;with radiation levels such

, that a major portion of the body _ could receive _ in one hour a dose in excess of L 1000-mrem ** that are located within large areas, such as< PWR containment, where i no enclosure exists for purposes of locking, and-no enclosure can be reasonably t

constructed around the individual areas,- then that area shall be roped off, I

conspicuously posted and a _ flashing light- shall be activated as a warning device. In lieu of- the stay time specification of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by i personnel qualified in radiation protection procedures to provide positive f exposure control over the activities within the' area.

• Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of L their assigned radiation protection duties, provided they are following plant radiation protection procedures for entry into high radiation areas.

- thst radio,tton "Measurt-ment made at W from^ source cf r:d:::tM ty. or fcom any 6tArbC4 30c.m that the raMationpenetmtes.

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o RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1.3 LIOUID WASTE TREATMENT This specification deleted. Refer to the Offsite Dose Calculation Manual.

W 3/4.11.1.4 LIOUID HOLDUP TANKS 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 ten times the limits of 10 CFR Part 20, Appendix B (to paragraphs 20.1001 - 20.2401), Table 2, Column 2 at the nearest potable water supply and the nearest surface water supply in an~ unrestricted area.

3/4.11.2 GASE0US EFFLUENTS 3/4.11.2.1 DOSE RATE This specification deleted. Refer to the Offsite Dose Calculation Manual.

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reasonably achievable. The program (1) shall be contained in the 00CM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program sha'i include the following elements:

1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, ii) Limitations at all times on the concentrations of radioactive material released in liquid effluents to unrestricted areas conforming to ten times the concentrations stated in 10 CFR Part 20, Appendix B (to paragraphs 20.1001 - 20.2401),

Table 2, Column 2, iii) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM, iv) Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas conforming to Appendix I to 10 CFR Part 50, v) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, i

vi) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce l releases of radioactivity when the projected doses in a i

31-day period would exceed 2 percent of the guidelines for l the annual dose or dose commitment conforming to Appendix I l to 10 CFR Part 50, 1

l vii) Limitations at all times on the concentrations of radioactive l material released in gaseous effluents to areas beyond the site boundary conforming to ten times the concentrations

stated in 10 CFR Part 20, Ap 20.1001 -

t 20.2401), Table 2, Column 1,gendix B (to paragraphs

• At any time, ten times the concentrations stated in 10 CFR Part 20, Appendix B (to paragraphs 20.1001 - 20.2401), Table 2, Column 1, I

I corresponds to a dose rate of 500 mrem / year total effective dose equivalent.

l FARLEY-UNIT 2 6-15a AMENDMENT N0.

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s ADMINISTRATIVE CONTROLS viii) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary conforming to Appendix I to 10 CFR Part 50, ix) Limitations on the annual and quarterly doses to a member of the public from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the site boundary conforming to Appendix I to 10 CFR Part 50, and x) Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

f. Radioloaical Environmental Monitorina Proaram A program shall be provided to monitor the radiation and radionuclides 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 exposure 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:

i) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,

11) A Land Use Census to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the monitoring program are made if required by the results of this census, and iii) Participation in a Interlaboratory Comparison Program 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 environmental monitoring,

g. Solid Radioactive Wastes Control Procram The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that 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 Parts 20, 61, and 71; State regulations; burial ground requirements; and other requirements governing the disposal of solid radioactive waste.

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6.12 HIGH R M j0N AREA ,

6.12.1 In iieu cf the " control device" or " alarm signal" required by paragraph 20.1601(a) of 10 CFR 20, each high radiation area in which the intensity of l radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be l barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit.* 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.

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.

c. A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physics Supervisor.

6.12.2 In addition to the requiremeni.s of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved Radiation Work Permit which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such I

that a major portion of the body could receive in one hour a dose in excess of

' 1000 mrem ** that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the RWP, direct or remote.

(such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are following plant radiation protection procedures for entry into high radiation areas.

• • Measurement made at 30 cm from the radiation source or from any surface that the radiation penetrates.

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