ML20127L506

Revised Proposed TS Re Implementation of New 10CFR20 Requirements

ML20127L506
Person / Time
Site:	Vogtle
Issue date:	01/22/1993
From:	GEORGIA POWER CO.
To:
Shared Package
ML20127L496	List: ELV-05102, Forwards Responses to NRC 921203 RAI Re Util 920917 License Amend Request Associated W/Implementation of New 10CFR20 Requirements & Revised Proposed TS Associated W/Responses ML20127L506
References
NUDOCS 9301270182
Download: ML20127L506 (7)

Text

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I ENCLOSURE 2 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECilNICAL SPECIFICATIONS IMPLEMENTATION OF TIIE NEW 10 CFR 20 REOUIREMENTS REVISED PRQPOSED TECHNICAL SPECIFICKTION CliANGES 9301270182.930122 PDR ADOCK 05000424 P

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n rnean s cAn 'incliu'ic{ual in ct ccanbollec( argo, Or UMfM6TRIC'IED NTA. HoweveG avl i 1di 3

l OEFINITIONS vidual is n6L A 14EMBEROF THE PuBLld.

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duh no o ng pectOc( in u;Nch -the, raivlaa,i l

' EMBERI M OF THE PUBLIC eqcciv)C5 an occu pational cAost.

1.18 MEMBER OF THE PUBLIC sAall %:!ude 21' percen: ~50 are 90t occupa-

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ticnally -eno@ciated with th; plcnt.'Si category de:: not S:1ude empl y ::

ef the 'icen:ce, it: centrccter:, or sender:.

^1:0 ^xcluded 'rce thic cc.tegeey are per:On: g o-e ter the cite to : r" ice equipment Or te m:ke del %:ric;.

This category 4ee+ include persons who use portions of the site for recre-ational, occupational, or other purposes not associated with the plant.

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OFFSITE DOSE CALCULATION MANUAL pgglhq Storyt 1.19 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contai the methodology and parameters used in the calculation of offsite doses det t. radioactive gaseous and liquid effluents. in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environ-mental Radiological Monitoring Program. <

INSERT 1 OPERABLE - OPERABILITY 1.20 A system, subsystem, train, component or device shall be OPERABLE or l

have OPERABILITY when it is cf.*,able of performing its specified function (s),

and when all necessary attendant instrumentation, controis, electrical power, cooling or seal vater, lubrication or other auxiliary equipment that are required for the system, tuosystem, train, component, or device to perform its function (s) are also capable of performing their related suppor'. function (s).

OPERATIONAL MODE - MODE 1.21 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive l

comoination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.

PHYSICS TESTS 1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental I

nuclear characteristics of the reactor core and related instrumentation:

(1) described in Chr.pter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE 1.23 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube l

leakage) through a nonisolable fault in a Reactor Coolant System comconent body, pipe wall, or vessel wall.

PROCESS CONTROL PROGRAM 1.24 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, l

h samoling, analyses, tests, and determinations to be mace to ensure that process-Dngandpackagingofsolidradioactivewastesbasedondemonstratedprocessing 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)n; %d m l nd State 1

V0GTLE UNITS - 1 & 2 1-4 Amenoment No. 32 (Unit 1)

Amendment No. 12 (Unit 2)

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DEFINITIONS S_0LIDIFICATION D c.l c't e.d.

1.33 A 00LIDITICATIOi,' :h:11 b: th; ::nn r:icn f wet.:::te: %te r fer-that

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• ens-sMppin; :nd buri:1 ground -requirce:nt;.

E SOURCE CHECK 1.34 A SOURCE CHECK shall be the qualitative assessment of channel response l

when the channel sensor is exposed to a r,curce of increased radioactivity.

STAGGERE.D TEST BASIS 1.35 A STAGGERED TEST BASIS shall consist of:

l A test schedule for n systems, subsystems, trains, or other a.

designated components obtained by dividing the specified test interval into n equal subintervals, and b.

The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.

THERMAL POWER 1.36 THERMAL POWER shall be the total reactor core heat transfer rate to the l

reactor coolant.

TRIP ACTUATING DEVICE OPERATIONAL TEST 1.37 A TRIP ACTUATING DEVICE OPERA'TIONAL TEST shall consist of operating the l

Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or trip functions.

The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy.

UNIDENTIFIED LEAKAGE 1.38 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE l

or CONTROLLED LEAKAGE.

NNRESTRICTED AR h #

Nr 1.39 h--UNRESTRICTED AREA :h:1' b: any cr : at-cr bcycad-the SITE COUt$ARV-N l

este:: te '*ich it not centre!!ed by +he 'icette: '

perpe::: of protectier of T M di idu:1: <r:

ex;;;;ur t: radictic.. and radic:: tin :::ari:1:, er :ny cree-with", the $!TE SOUN0fRV u.ed f or residenti:1 quer-ter: cr for i ndustri:1,

/ccaserci:1, in:titutional, and/or recreational purposes.

utMESTR10.TED AAE/t meus an erm; acces s to u;hich is ne i.ther \\irniter) r\\or c.ontrolkd % %e hC"See or any r

area unthm the s iTE 60u.4 DARy Mied ior resicAend prters or for inchstrial,cornrnercial) irisbYt(H onal) and/or recrc G lenalpeposeg V0GTil.yNITS - 1 & 2 1-6 Amen _g:nant-16.kh--(h i 7 C

7 Amendment No. 12 (Unit 2)

RADI0 ACTIVE EFFLUENTS BASES DO5E (Continu

)

/

Reactor Ef uents for the Purpo,se of Evaluating C f pliance with 10 CF art 50, Appendi

" Revision 1, Oc dber 1977 and Regul ory Guide 1.113. "

timating Aquat' Dispersion of Ef uents from Acciden and Routine Reactor Releases 5

for he Purpose of Imp menting Appendix I April 1977.

This specific gion applies to the D EWW D elease of radioactiye materials in liquid effluents from eadh unit at the site used by more p (an one unit on a s' When shared Radwast4 Treatment Systems a shared trea

, the wastes from 3FI units are mixed for ascribed,t6.tdent; by such mixin, the effluent relea s cannot accurately a specific unit.

n estimate should b made of the contribu ons from epch unit based on input conditions, e.g.,

ow rates and radioa vity concentrations, or, if rpt practic.able, the tr ted effluent releas may be aMocated equally to ch of the radioactiv aste producing uni sharing the R

/ adwaste Treatment stem.

For determini conformance to LCO, these alloca-tions from share adwaste Treatment Sy ems are to be added o the releases specifically a ributed to each unit o obtain the total r eases per unit.

3/4.11.1.3 LIOUID RADWASTE TREATMENT SYSTEM tJot used. he OPPSILI" et the Liquid hee :tc 7 :t.ent Sy te ent re that th E ill be available for ose wnenever liquid p luents require treat syste j

pr' to release to the environment.

nL The requir nt that the appropr' te portions this system be used wh1En specified proside o

assurance that the r eases of adioactive materials tn liquid effluents w) 1 be kept "as low as y

achievable."

This ppecification implemerKs the requirements of s reasonably 4.erion 60 of Appendi/A to 10 CFR Part 50 0 CFR 50.36a, General Design C d the design objective give n Section II.D of limits goverp ng the use of appropr{iate portions of the,ppendixIto10CFRPar 50.

The specified quid Radwaste Treatment /

System wer(specified as a suitatsle fraction of the do forth i Section II.A of App ndix I, 10 CFR Part 50 design objectives set /

orliquidefflug his specification a lies to the release o radioactive materials in g

li id effluents from pa6h unit at the site.

en shared Radwaste Treatinent j6ystems are used by re than one unit on a te, the wastes from al / units treatment;bysuchm,ing,theeffluentrelease)scannot are mixed for snar accurately be ascribed to a specific un'.

contributions <f' rom each unit based on An estimate should be/made of the nput conditions, e.g., ffow rates and radioactivijfconcentrations,or, i not practicable, the trpeted effluent releases gay be allocated equall o each of the radioactiv4 waste producin units pn,aring the Radwaste Trep.ent System.

• For determifIing conformance LCOs/ these allocations from, $ hared Radwaste Treatment 4ystems are to b - added o

tvthe releases specifica)) y attributed to each unityto obtain the tota'l

/eleases per unit.

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3/4.11.1.4 LIOUID HOLDUP TANKS The tanks listec in this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.

den times

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Resti1cting the qualitity of raoicactive mater I contained in/ the specified\\

tanks provides assurance that in the event of an uncontrolled release of the

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tank's contents, the resulting concentrations would be less thansthe limits of 10 CFR Part 20, Appendix B T2'c!!,4olumn2,atthenearestpotablewater i

sucolyandthenearestsurIacewatersu"lyinanUNRESTRICTEDAREA.

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J (to parac3 9h5 20.1001-20 2401)I V m rti TS - 1 & 2 B 3/4 11-2 l

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ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRANS (Continued) 1)

Identification of a sampling schedule for the critical variables and control points for these variables, 2)

Identification of the procedures used to measure the values of the critical variables, 3)

Identification of process sampling points, 4)

Procedures for the recording and management of data, 5)

Procedures defining corrective actions for all off control point chemistry conditions, and j

6)

A procedure identifying:

(a) the authority responsible for the interpretation of the data,,and (b) tha sequence and timing of administrative events required to initiata corrective action.

d.

Post-Accident Sampling A program which will. ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and conttinment atmosphere samples under accident conditions.

The program shall include the following:

1)

Training of personnel, 2)

Procedures for sampling and analysis, and 3)

Provisions for maintenance of sampling and analysis equipment.

A program which will ensure the capability to monitor plant variables e.

and systems operating status during and 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 instrumentation.

2) pre planned operating procedures and back-up instrumentation to be used if one or more monitoring-instruments become inoperable.

3) administrative procedures for returning inoperable instruments to OPERABLE status as.soon as practicable.

f. T 3 Lsect 2.

V0GTLE UNITS - 1 & 2 6-16

INSERT 2 f.

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 ODCH, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever tne 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 setpoint determination in accordance with the methodology in y nnrg, 2) dnth centrations of radioactive erial released in liquid effluents to UNRESTRICTED AREAS conforming N

to 10 CF" "crt 20 f,ppendix ", Tcble II, Column 2 ten times %e d$^$oT,"Dff.htgfrt lor FRP.O; Apfendh 8(to Paf**rophs 7.0.1001- )

3)

Monitorina, sam /l-mgsWanalvsWafsaaina"4ue l'tquia ana a

s gaseous effluents in accordance with 10 CFR 20.105-and with the methodology and parameters in the ODCH, N

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4)

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, 5)

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, 6)

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 a

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ations 7)

Limitationston the dcsc rate resulting fra uradioactive N

material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the-doses cssocicted with 10 CF",

hrt 20, t,ppendix ", Tcbic II, Column 1, ten times the conce rttoq-tions staked in lour Part 20 Appendix B hto Fom 90afhs 20.1001-Zo.Zttot), Tab \\e a,)colurnn 1*J Cs

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At ang tirne, ten times the con centrations SYQied M LOW Pg2 fj M

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(to pa c4 9 co p hs 2.0 1001 - 2.0 2.+0D Taiot e 2, Cd ote 04 Cao enrem /uear totql eMec-tive,(ose qufy D

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4 ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) h.

Records of inservice inspections performed pursuant to these Technical Specifications; i.

Records of quality assurance activities required by the Final Safety Analysis Report; j.

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

Records of meetings of the PRB and the SRB; 1.

Records of the service lives of all hydraulic. and mechanical snubbers required by Specification 3.7.8 including the date at which the service life commentes and associated installation and maintenance records; Records of secondary water sampling and water quality; and m.

Records of analyses required by the Radiological Environmental n.

Monitoring Program that would permit 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 followed.

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II:nsart fil 6.10 RADIATION PR0ftCTION PROGRAM 6.10.1 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, fr 3

E.11 HIGH RADIATION AREA 20.1 l(c) )-

( 220,1b O((c0 s

W 6.11.1 Pursuant to paragraph 20. 03(c)(54-of 10 CFR Part 20, ig/ lieu of the

" control device" or " alarm signal" required by paragraph 20.203(-),each high radiation area, as defined in 10 CFR Part 20, in which the intensity of..radia> --sg tion is greater than 100 mrem /hr but less than 1000 mR/h at t5 cr (19 i from the radiation source or from any surface which the radiation penetrate SOcudt20n))-

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shali be barricaded and conspicuously posted as a high radiation area and tr. rance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).

Individuals qualified in radiation protection procedures (e.g.,

Health Physics Technician) or personnel continuously escorted by such individuals

.nay be exempt from the RWP issuance requirement'during the performance of their assigneo duties in high radiation areas with exposure rates _ greater than 100 mrem /hr but 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

,covided with or accompanied by one or more of the following

A radiation monitoring device which continuously indicates the a.

radiation dose rate in tne area; or iCGTLE UNIT 5 - 1 & 2 6-23 l

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