ML20115D662

Proposed Tech Spec Page 3/4 3-80 Re Explosive Gas Monitoring Instrumentation & Selected Revised RETS Selected Licensee Commitment Pages

ML20115D662
Person / Time
Site:	Catawba
Issue date:	10/08/1992
From:	DUKE POWER CO.
To:
Shared Package
ML20115D653	List: ML20115D649 ML20115D662
References
NUDOCS 9210210078
Download: ML20115D662 (26)

Text

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i ATTACHMENT 1 PROPOSED CATAW13A TECHNICAL- SPECIFICATIONS CHANGES .

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INS 1RUMENTATION EAPLot t V5 "t0!O.t0TP!5 GA! 0": L""'_'jD:5. MONITORING INSTRUMENTATION

)'r LIMITING CONDITION FOR OPERATION 4

80 actios.tav 3.3.3.ht The r:df:::ti": gaseew: :f'!uent-monitoring instrumentation channels shown in Table 3.3-tt;ghall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limitrof Specificatf ora 3.11.2.1 :nd-3.11.2.5 are not exceeded.

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j APPLICABILITY: As shown in Table 3.3-12.

i ACTION:

sn uplo5o

a. With e redi;;;tive- gas:: i :f'luen4 monitoring instrumentation channel.

a Alarm / Trip Setpoint less# conservative than required by the above specification, i;;;dietely ;u; pend th; rel;;;; ;f redi;;;tive--

4

-g;;;;;; ;f fluente eenitered by the effi;ted channel, er declare the .

channel inoperable 4an2. ta= tk Actiov skw le Taue.3,3-/A

exdotMs With less than the minir.um number of r:di ::tiv; ga::::: :ff1;;nt b.

i monitoring instrumentation channels OPERABLE,, take the ACTION shown in Taole 3.3-t&PL Restore the inoperable instrumentation to OPERABLE pr stetus withintthe tis.i specified 'n th. ACTIO",- er :xpi:in in th;

• xt S;;i;nrg;l 0;di;;;tive Offigent Releese Repes t, pursuant t1 30 Jhyr/ Specification 6.9. Q. 4ty_,this inoperability was not corrected ~

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within the time specffied. 5stv eAPh.in

c. The provisions of Specification 3.0.3 are not applicable, of d' unrec :Fv ?ctnisaA N O

- a. .Qec.it Rmet ,n %c, Cw.ed tim SURVEILLANCE REQUIREMENTS 3

10 expordas

4. 3. 3.44- Each r:df,; :t!v: gas ++w+-+"luent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK,449AeC-Cl: CYy CHANNEL CALIBRATION, and ANALO3 CHANNEL OPERATIONAL TEST operations at -

the frequ'encies shown in Table 4.3-9.

8 4

20 CATAWBA - UNITS 1 & 2 -3/4 3 Amendment'No. . (Unit 1)  ;

Ameidment No.' (Unit 2) 4

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k i NITACHMENT 2 CATAWBA SELECTED LICENSEE COMMITMENTS FOR

, RAI' .* OGICAL EFFLUENT CONTROLS 4~

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) TABLE 16.11-1 (page 3 of 3) i TABLE NQTAJJ10N5fContinued).

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(3) .The principal gamma emitters for which the LLO specification applies l

j include the following radionuclides: Mn-54, fe-59, Co-58, Co-60, 2n-65, The LLD for Ce-144 is 5x10~' pC1/ml.

i Mo-99, Cs-134, Cs-137, and Ce-141.

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 J r .nuclides, shall diso be anaijzed and reported in the Semiannual Radio-

, active Effluent Release Report pursuant to Technical Specification 6.9.1.7 in the format outlined in Regulatory Guide 1.21, Appendix B,

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j- Revision 1. June 1974 (4) A conposite sample is one in which the quantity of liquid samoled is  !

l proportional to the quantity of liquid = waste discharged and in which the. t i method of sampling employed results in a specimen that is representative

( of.the liquids. released.- .

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! (5) A continuous release it the discharge of liquid wastes'of alr,ondiscrete ,

i volume, e.g., from a volume of a system that has an input flow during the

!= continuous release. [

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{. (6). To be representative of the' quantities and concentrations of radioactivo. r i materials in liquid effluents, samples shall be collected continuously in proportion to the rate-of flow-of the offluent stream, Prior to g analyses,. all samples taken for the composite thall be thoroughly mixed j in order for the compc11te sami,le to be representative of the effluent

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16.11 RADIOLOGICAL EFFLUENT CONTROLS  !

l LNSLROMNTA110N l 16.11-2 RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION i i=

i c0MMITMENT _ __ __

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! The radioactive liquid effluent monitoring instrumentation channels shown in

[ Table 16.11-2 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure ,

i that the limits of SLC 16.11-1 are not exceeded. The Alarm / Trip Setpoints of L these channels shall be determined and adjusted in accordance with the j methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM)._  ;

APPLICABILITY

At all times. l E t

!- REM_ _EDI AL_AC_TIO_N: -

! a. With a radioaccive liquid effiuent monitoring instrumentation f channel Alarm / Trip Setpoint less conservative than required by t.hc j above specification, immediately suspend the release of radioactive liquid effluents monitored by the affectec' channel, or declare the l- channel inoperable, i

l b. With less than_the minimum number of radioactive liquid effluent j monitoring instrumentation channels OPERARLE, take the ACTION shown

, in Table 16.11-2. Restore the inoperable instrumentation to OPER- ,

j ABLE status within the time specified in the ACTION, or explain in j the next Semiannual Radioactive Effluent Release Report pursuant to

Technical Specification 6.9.-1.7 why this -inoperability was not f

corrected within the tic.e specified.. '

l- TESTING REQUIREMENTS:

l ' Each radicactive liquid effluent monitoring instrumentation channel shall be-  !

i demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK,

! CHANNEL CAllBRATION and ANALOG CllANNEL OPERATIONAL TEST operations at the 1 j .. , frequencies shown'in Table 16.11-3.

i

REFERENCES:

p 1. . Catawba Offsite Dose Calculation Manual

2. 10 CFR Part 20

_' 3 . -10_CFR_Part 50,' Appendix A-I BASES: i l - The radioactive liquid ef fluent instrumenthuon is provided to monitor and ,

i. control, as applicable, the releases of radioactive materials.in liquid ef fluents during actual. or potential releases of- 11guld . effluents. The j, q 16.11 , +

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i BASES: (cont.) 1' 1 Ala"m/ Trio Setpoints for these instruments shall be calculated and adjusted in I accordance with the methodology and parameters-in'the ODCM to ensure that the 1 Alarm / Trip will occur prior to exceeding the limits of 10 CFR Part 20. The

! OPERABILITY and use.of this' instrumentation is consistent with the reauire-

! ments of General-Design Criteria 60, 63, and (4 of Appendix A to 10 CFR Part

50.

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16.11 _ RADIOLOGICAL EFFLUENT CONTROLS f RADIDACTIVE EFFLUENTS t^

l 16.11-3 OOSE

_COMMLTMENT _

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! The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive i materials in liquid effluents released, from each unit, to UNRESTRICTED 'REAS (see Figura 26.11-1) shall be limited: )

a. During any calendar quarter to less than or equal to 1.5 mrem to the

} whole body and to less than or equal to 5 mrem to any organ, and i

j b. During any calendar year to less- than or equal to 3 1 rem to the whole body and to less-than or equal _to 10 mrem to any organ.

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APPLICAB!LITY

At all times.

4 i MMEDIAL ACTION:

l l With the calculated dose from che release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the '

Commissier within 30 days, pem uant to Technical Specification 6.9.2, a

! Spetla1._ k1 ort that identifies the cause(s) for exceeding the limit (s) ard

{_ defines ti< corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases l will be in compliance with the above limits. This Special Report shall also E include: (1) the results of radiological analyses of the drinking' water

, source, and (2) the radiological impact on finished drinking water supplies l with regard to the requirements of 40 CFR Part 141, Safe Drinking Water Act

• 2:

l lESTING_ REQUIREMENTS:

! Cumulative dose contributions from liquid effluents for the current calendar l' quarter and the current calendar year shall be determined in accordance w6th i the methodology and parameters in the ODCM at-least once per 31 days.

i j *The requirements of. REMEDIAL ACTION (1) and (2) are applicable only if f drinking water supply is taken from.the receiving water body within 3 miles

. downstream of the-plant-discharge.

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, RAD 10ACllyE_EFMENIS l

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16.11 4 I l LIQUID RADWASTE 1REATMENT SYSTEM

l COMMITMENT

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i l The liquiri P.adwaste Treatment System shall be OPERABLE and appropriate por-4 tions of the system shall be used to reduce releases of radioactivity when the

! projecteo doses due to the liquid effluent, from each unit, to UNRESTRICTED

{ AREAS (see Figure 16.11-1) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.

AP_P_LICABLLITY

At all times. o ~

i REMEDIAL ACTION:

l With radioactive liquid waste being discharged without treatment and in excess

of the above limits and any portion of.the Liquid Radwaste Treatment System-i not in operation, prepare and submit to the Commission within 30 days,

i. pursuant te 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 0PERABLE.

j status, and i

3. Su

; nary description of action (s). taken to prevent a recurrence.

I l IESJJNG REQUIREMENfS:

l Dosns due to liquid releases 3.om each unit to UNRESTRICTED AREAS shall be-

! projected at least once per 31 days in accordance with the methodology and l parameters in the ODCM when Liquid Radwaste Treatment , Systems. are not being

! fully utilized.

L . .

i The Installed Liquid Radwaste Treatment System shall be considered OPERABLE by

[. meeting SLC 16.11-1-and 16.11-3.

, BEFERENCES:

E

. 1. Catawba Offsite Dose. Calculation' Manual.

. 2. 10 CFR Part 50, Appendix A i

3. 10 CFR Part 50, Appendix I F .-16.11-15 1

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! .TABLL16dl-4 (Page 4 of 4) i TABLE.A0TADONS_(C.onjinued).  ;

j (2) The principsi gamma emitters f or which the LLD specification.apriies i include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133si, i Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60,

Zn-65, Mo-99, I-131, Cs-134, C5-137, and Ce-141 in lodine and particulate j releases. The LLD for Ce-144 is 5x10~' pC1/ml. This list.does not mean 2 that unly these nuclides are to be considered. Other gamma peaks that

! are identifiable, 'ogether ulth those of the above nuclides, shall also  :

be analyzed and reported in the Semiannual Radioacthe-Effluent Release i Report, pursuantito Technical Specification-6,9.1.7, in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. ,

l i '( 3) Sampling and analysis shall also be pe-formed following shutdown, j startup, or a THERMAL p0WER stabilization (power level constant- at

desired power level) af ter a THERMAL- POWER change exceeding 15% of RAfED '

! 1HERMAL p0WER within a 1-hour period, for at least one of tN three l

gaseous release types with this notation.

(4) Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> w.ien the

refueling canal is flooded. r (5) Required sampling and analysis frequency during effluent releare via 'hir f j pathway.

1

! (6) The ratio of the sample flow volume to'the sampled stream flow volume i shall be known for the time period covered by' enh dose or dose rate-calculation made in accordance with OLCs 16.11-6, 16.11-8, and 16.11-9.

4 (7) Samples shall be changed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and analyses shall be o

completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter changing, or af ter removal from sampler.

l (8) The composite filter (s) will be analyzed.for alpha activity by analyzing i one filter per week to ensure that at least four filters are analyzed per-colle tion period.

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j . COMMITMENT _ _ _ _ _

4 i The radioactive gaseous effluent monitoring instrumentation channels shown in

Table 16.11-5 shall be OPERABLE with their Alarm / Trip Setpoints set to Ansure i that. the limits of SLC 16.11-6 are not exceeded. The Alarm / Trip Setpoints ot

these channels meeting SLC 16.11-6 shall be determined and adjusted in

cord-

! ance with the methodology _and parameters in the 00CM.

l .

APPLICABILIT_Y: As shown in Table 16.11-5. ,

t_

BEMEDIAL AC110N:

I a. With a racioactive gaseous effluent monitoring instrumentation ,

channel Alarm / Trip Setpoint less conservative than required by tho

above specification, immediately suspend the release of radioactive '

gaseous effluents monitored by the affected channel, or declare the i channel inoperable,

b. With less than the minimum number of radioactive gaseous ef fluent monitoring instrumentation channels OPERABLE, take the ACTION shown i

] in Table 16.11-5. Restore the inoperable instrumentation to i OPERABLE status within the time specified in the ACTION, or explain >

l in the next Semiarnual Radioactive Effluent Release Report pursuant L to Technical-Specification 6.9.1.7 why-this inoperibility was not l

corrected within the time specifled.

! TESTINGJEQUIREMENTS:

I' Each radioactive gaseous effluent monitoring instrumentation channel shall be  !

l demonstrated OPERACLE by performance of the CHANNEL CHECK, SOURCE CHECK, i CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST operations at the i' 4- frequencies shown in Table 16.11-6.

l REF_ERENCES:

i

1. Catawba Offsite-Dose Calculation Manual.. ,

2. 10 CFR Part 20

. BAS _ES.:

The radioactive-gaseous effluent instrumentation is provided to-monitor and

' control,_ as applicable, .the releases of-radioactive materials in gaseous t effluents.during actual or potential releases of gaseous effluents. The i Alarm / Trip Setpoints for these instruments shall be c.a!culated and_ adjusted in

[ accordar.ce with the methodology and parameters in the ODCM to ensure that the F

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! alarm / trip v 'l occur prior to exceeding the limits of 10 CFR Part 20. The  !

OPERABILITY and use of this instrumentation is consistent with the j requirements of General Design Criterio 60, 63, and 64 of Appendix A to 10 CFR l Part 50. The sensitivity of any noble gas activity monitor used to show

! compliance with the gaseous effluent release requirements of SLC 16.31-8 shall

]

be such that concentrations as low as 1~x 10-6 pCi/cc are measurable.

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16.11 RADIOLOGICAL EFFL1)ENT_ CONTROLS-RAD 106ClllE.. EFFLUENTS 16.11-8 DOSE - N0BLE GASES

_C0hMJ1 MEN 1 _

The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 16.11-1) shall be limited to the following:

a. During any calendar quarter: Less than er equal to 5 mrads for gamma radiation and less than or equal to 10-mrad for beta radiation; and,

b. During any calendar year

• Less than or equal to 10 mrad for gamma-radiation and less than o' equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

REMEDIAL ACTION:

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission w ahin 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 sub:equent releases will be in -

compliance with the above limits.

lESilNG_ REQQLREMENIS:

Cumulative dose contributions for the current calendar quar.ter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

REFEM KES:

1. Catawba Offsite Dose-Calculation Manual.

2, 10 CFR Part 50, Appendix 1 BASES:

This commitment is provided to implement the requirements'of Sections II.B.

III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition.for Operation implements the guides set forth in Section.II.B of Appendix 1. The-

-REMEDIAL ACTION statement provides the required operating- flexibility and at the same time implement the guides set forth in Section..IV,A;of Appendix I to-assure that the releases of radioactive material in gaseous effluents .to UNRESTRICTED AREAS will beikept "as;1ow as is reasonably achievable". Tne

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Testing Requirements implement the requirements in Section III.A of Appendix 1 l

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that conformance with the guides of Appendix 1 be shown by calculational

procedures based on models and data such that the actual exposure of a MEMBER

0F THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established

! in the ODCM for calculating the doses due_to the actual releast rates of  !

i radioactive noble gases .n gaseous ef fluents are consistent with the method-- l 4 ology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man l from Routine Releases of Reactor Effluents for the Purpose of Evaluating A

Compliance with 10 CFR part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and-

Dispersion of Gaseous Effluents in Routine' Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining

!_ -the air doses at and beyond the SITE BOUNDARY are based upon the historical

!_ average atmospheric conditions.

] -

l This commitment applies to the release of radioactive materials in gaseous-

< effluents from each unit at the site. When shared Radwaste Treatment Systems

! are used by more than one ; nit on a site, the wastes from all units are mixed j for shared treatment; by such mixing, the effluent-releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contribu-

! tions from each unit based on input conditions, e.g., flow rates and radio-activity concentrations, or, if not practicable, the t reated effluent releases 3

may be allocated equally to each of the radioactives waste producing units sharing the Radwaste Treatment System. For determining conformance to commit-

} ments, these allocations from sha.ed Radwaste' Treatment Systems are to be.

. added to the releases specifically attributed to each unit to obtain the total releases per unit.

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1 4 RADI0 ACTIVE EFFLUENTS ,

! 16.11-9 DOSE - 10 DINE-131, 10 DINE-133, TRITIUM, AND RADIDACTIVE MATERIAL IN

! PARTICULATE FORM ,

j COMfitTMENT _ __

! i

) The dose to a MEMBER OF THE PUBLIC from Iodine-131, lodine-133, tritium, and

} all radionuclides in particuiate form with half-11ves greater than_8 days in  :

i gaseous effluents released, from each unit, to areas at and beyond the 511E j BOUNDARY (see Figure 16.11-1) shall be limited to the following:

j a. During any calendar quarter: -Less than or equal to 7.5 mrem to any

[ organ; and,  ;

! b. During any calendar year: Less than or equal to 15 mrem to any ,

organ.

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. APPLICABILITY: At.all times.

! REMEDIAL ACTION:

i With the calculated dose from she release of Iodine-131. Iodine-133, tritium,

and radionuclides in particulate form with 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 Technical Specification 6.9.2, a i Special Report that identifies the cause(s) for exceeding the limit 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

~

L s will be in compliance with the above limits. ~

lESlLNG._REQU1RDiF.N.lS:

Cumulative dose contributions for the current calendar. quarter ano current i: calendar year fer Todice-131, lodine-133, tritium'and radionuclides in -

r particulate form with half-lives greater than 8 days shall be determined in '

accordance with the methodology and parameters in the ODCM at'least once per 31 days. 3 i  ;

l,, REfERE.NIES: .

1. Catawba Offsite Dose Calculation Manual. >

l 2. 10 CFR Part 50, Appendix I

- BASES

This commitment is provided to-implement the requirements of Sections II.C,

! III. A, _ and IV. A of Appendix 1,10 CFR Part 50, and are the guides set forth in l'

Section II.C of Appendix 1. The REMEDIAL ACTION statements provide the 6

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BASES: (cont'd) required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive mator'als in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is re> tonaSly achievable". . The 00CM calculational methods specified in the  ;

Surve 11ance Requirements implement the requirements in Section III.A of '

Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual  ;

exposure of a MEMBER OF THE PUBLIC -through appropriate pathways is unlikely to be substantially underestimated. The ODCM 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 to Man from 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 Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, ~ July 1977.

These equations also provide for determining the actual doses based upon the historical average atmospherie conditions. The release rate commitments for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclido pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways ~

that were examined in the development of the calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radio- l nuclides onto green leafy vegetation with subsequent consumption by man, (3) i deposition onto grassy areas where milk animals and meat producing animals graze wit'i consumption of the milk and meat by man, and-(4) deposition on the ground with subsequent exposure of man.

This commitment applies to the release of radioactive materials in gaseous effluents from each unit at the site. - When-shared Radwaste Treatment Systems are used by more than one unit on a site,;the wastes from all: units _are mixed

for shared treatment; by such mixing, the ef fluent

releases cannot accurately ,

i be ascribed to a specific unit, An estimate should be made of the contribo- ,

! tions from each unit based on input conditions, e.g., flow rai s 3nd radio- .

L activity concentrations, or, if not practicable,Lthe treated eti,uent releases

!- may be allocated equally to each of the radioactive waste producing units-sharing the Radwaste Treatment System. For determining conformance to commit-ments, these allocations from shared Radwaste-Treatment Systems are to be added to the releases specifically attributed to each' unit to'obtain the total i releases per unit.

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). 16.11 MDIOLOGICAL EFFLUENT CONTROLS RADIDACTIVE EFFLUENTS 16.11-10 GASEOUS RADWASTE TREATM NT SYSTEM COMMITMENT _

The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31' days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 16.11-1) would exceed either:

a. 0.2 mrad to air from gamma radiation; or, ,

b. 0.4 mrad to air from beta radiation; or-,

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At all times.

REMEDIAL ACTION:

With radioactive gaseous waste baing discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Tech iical Specification 6.9.2, a Special Report that includes the following information:

-1. 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.

TESTING REQUIREMENTSi (

Doses due to gaseous releases from each unit to arass 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 Gaseous Radwaste. Treatment Systems  !

-are not being fully utilized.

The installed VENTILATION EXliAUST TREATMENT SYSTEM and WASTE GAS HOLG, YSTEM shall be considered OPERABLE by meeting SLCs. 16.11-6, 16.11-8, or 16.11-9.

REFERENCES:

1. Catawba Offsite Dose Calculation Manual.

2. 1.0 CFR Part 50, Appendix I 16.11-39

L

' 1 9 a

PROCESS CONTROL PROGRAM shall be modified as required, as provided in Technical Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste; and,

c. With the installed equipment. incapable of meeting SLC 16.11-11 or declared inoperable, restore the equipment to OPERABLE status or provide for contract capability to process wastes as necessary to satisfy all applicable transportation and disposal requirements.

REFERENCES:

1. Catawba Offsite Dose Calculation Manual.

2. 10 CFR Part 50, Appendix A

3. 10 CFR Part 50-BASES:

This commitment implements the requirements of 10 CFR 50.36a and General Design Criterion 60 of Appendix A 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, waste / liquid / SOLIDIFICATION agent / catalyst ratios, waste oil content, waste principal chemical constituents and mixing and curing times.

)

16.11 '^ '

i . . .

16,11 RA_D_10_L_0G1 CAL _EELUENT CONIROMi RA0__10ACT_lJE_ EFFt.UEMS 16.11-12 TOTAL DOSE COMMITMENT The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to-75 mrem.

APPLICABIllT1: At all times.

REMEDIAL ACTION:

With the calculated A ses from the release of radioactive materials in liquid or gaseous effluents .xceeding twice the limits of SLCs 16.11-3a, 16.11-3b, 16.11-8a, 16.11-8b, 16.11-9a, or 16.11-9b, calculations shall be made including direct radiation contributions.from the units and from outside storage tanks to determine whether the above limits of this commitment have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, 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. This Special Report, e defined in 10 CFR 20.405c, 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 t eport. It shall also describe levels of radiation and concentratious of radioactive material involved, and the cause of the exposure levels or concentrations. If the

~

estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered-a timely request, and a variance is granted until staff action on the request is complete.

TESTING REQUIREMENTS:

Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with SLCs 16.11-3, 16.11-8 and 16.11-9, and.in accordance with the methodology and parameters in-the ODCM.

Cumulative dose contributions from direct radiation from the units and from ra uaste storage-tanks shall-be determined in accordance with the methodology and parameters in the ODCM.- This m uirement is applicable only under conditions set forth in the REMED 4 ACTION of this commitment.

16.11-43

t 16.11 RADIOL.0GICAL EFFLUENT _ CONTROLS 5 -JIOLOGICAL ENVIRONMEN1; MONITORING O

'6.11-13

. MONITORIL PROGRAM QT.

y COMMITMENT

'n The Radiologi ai Environmental Monitcrine Provam shall be conducted as

.c<~ified in Taole 16.11-7.

ABILITY. At all times.

3* . lIAl,ACT10N:

a. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 16.11-7, prepare and wbmit tc the Commission, in fu Annual Radiological Envirenmental Operating Report required by Technical Specification 6.9.1.6, a description of 5 .Y;

• ~

the reasons for not conducting the program as required and the plans Y

for preventing a recurrente.

o. With the level of radioactiv'ty as the result of plant effluents an environmental s the reporting leve

~1ng medium at a nerified location exceedin, Table 16.11-7 n averaged over any h)

?

calendar quarter, - , are ard suLn !t +: tre Commission within 30 days, pursuant to Technical Specific ti*n 9.2, a Special Report tha+ identifies the caue(s) fo, excc m a; the limit (s) and defines active actions to be taken to reduce radioactive effluents at the potential annual de# to a MEMBER OF THE PUBLIC is less that, the calendar year limits of SLC 16,11-3, 16.11-8, ed 16.11-9.

When more than one of the radionuclides in Table 16.11-7 ere c..tected in the sampling medium, this report shll be submitted if:

concentration _(1.)_ c once n trati on_(_2_)-

reporting level (1) . reporting level (2) + * > 1.0 Wher radionuclides other than those in Table 16.11-7 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose

• to A MEM3ER OF THE ouBLIC from all radionuclides is equal tc. or greater than the calandar year i limits of SLC 16.11-3, 16.11-8 and 16.11-9. This rer -t ;. not required if the measured level of radioactivity was not the reruit of plant effluents; however, in such an event, the conditio shall be reportal and described in the Annual Radiological Environmental Operating Report required by Technical Specification 6.9.1.6.

• The methodology and parameters used to estimate the potential annual dose to a MEMBER Oi THE PUBLIC shall be indicated in this report c

16.11-45

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REMEDIAL ACTION: (cont'd)

c. With milk or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 16.11-7, 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 lacations from which samples were unavailable may then be deleted from the monitoring program.

Pursuant to Technical Specification 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 for the ODCM reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location (s) for obtaining samples.

TESTING REQUIREMENTS:

The radiological environmental monitoring samples shall be collected pursuant to Table 16.11-7 from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 16.11-7 and the detection capabilities required by Table 16.11-8. -

REFERENCES:

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/

Catawba Offsite Dose Calculation Manual.

1.

2. 10 CFR Part 50 Appendix I BASES: 2 The Radioingical Environmental Monitoring Program required by this commitment provides represenative measurements of radiation and of radioactive materials in those exposure pathways and for those rcdionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the plant operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological effluent Monitoring Program by verifying that the measurable con;ertratio" of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the enviro vental exposure pathways. Guidance for this monitoring program is providec: oy the Radiological Assessment Branch Technical Position on Environmental Monitoring.

The initial'y specif:ed 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.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 16.11-8 are considered optimum for routine-environmental measurements ir industrial laboratories. It should be recognized that the LLD is defined

.s an a priori (before the fact) limit representing the capability of a measurement system and not as an _a. posteriori (af ter the fact) limit for a particular measurement.

16.11-46

t'e . .!

,1 I TABLE 16.11-7 (Page 5 of- 7) i j IABLE NOTATIONS i l p 1. Specific parameters of distance and direction sector frrm the centeiline

[ of the station, and additional description where pertinent, shall be-

piovided for each and every sample location in Table 16.11-7 in a table _!

~ and figure (s) in the ODCM. Refer to NUREG-0133, " Preparation of 4

Radiological Effluent Technical 3pecifications for Nucelar Power 01 ants,"

' October 1978, and -to Radiologh al Assessment Branch Technical Po 3 tion, j Revision 1, November 1979. Deviations are permitted from the required ~

sampling schedule if specimens 8re unobtainable due to circumstances such

as hazardous conditions, seasonal enavailabil a'and malfunction of

automatic sampling ec;uipment. If specimens ars 'nobtainable due i.c

sampling equipment malfunction, effort shall be made to complete 4

corrective action prior to the end of the next sampling- period. All aeviations from the sampling schedule shall be documented in the Annual j

Radiological _ Environmental Operating Report pu suant to Technical

• Specification 6.9.1 6. It is recognized that, at times, it may not be i

possible or practicabic to continue to obtain samples of the_ media of choice at the most desired location-or timc. 'In these instances suitable-

alternative media and locations may be chosen for the particular pathway in quertion and' appropriate substitutions made within 30 days in the t Radiological Environmental Monitoring program. In lieu of any Licensee i Event Report required by Technical Specificction 6.9.1-and pursuant to l Technical Specification 6.9.1.7, identify the cause of the unavailability i- of samples fo_r that pathway and identify the naw location (s) for 4 obtaining replacement samples in-the next Semiannual Radioactive Effluent i Rele tse Report and also include in the report a revised. figure (s) and table for the ODCM reflecting'the 'ew 1mation(s).

l 4

2. One or ma-e inniements, such as a' pressurizeo ior, chamba , i or measuring 4

and recording dose rete continuously may be used in place of,~ or-in i addition to, integrating dosimeters. For the purpose.5 of this table, a thermoluminescent dosim'ter (TLD) is considered'to be one phcsphor; two or more phosphors in.a ;ccket are. considered as two or more dosimeters.

[ Film badges shall not *.+ used as' dosimeters'for measuring. direct j radiation. (The 40 stations is not an absolute number. . The number of

! direct radiation monitoring stations may be reduced according to geographical limitations; e.gt,- at an ocean site, some sectors will be -

over water so-that the .iumber of dosimeters may be reduced accordingly.

The frequency of analysis or readout for TLD systems will depend upon the characteristics of~the specific system used and should be selected to e obtain optimum dose information within minimal fading )

'3. Airborne particulate sample filters shall'be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 of control samples, gamma

isotopic analysis shall be performed-on the individual-samples.

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16.11-52 m

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i 4 . TABLE 16.11-8 (Page 2 of 3)

L TABLE NOTATIONS 4

?

! 1. This list does not mean that only these nuclides are to be considered.

4 Other peaks that are identifiable, together with those of the above i .nuclides,.shall also be analyzed and reported in the Annual Radiological Environmental C'perating Report pursuant to Technical Specification .

6.9.1.6.

2. . Required. detection capabili+.ies for thermoluminescent dosimeters used for i environmental measurements shall be in.accordance with-the recommenda-

j. tions of Regulatory Goide 4.13. -

3. The LLD is defined, for purposes _of these commitments, as the' smallest 1

concentrations of radioactive material-in a sample that will yield:a net' count, above system background, that will be detected with 05% pro--

t- bability with only 5% probabi-ity of falsely concluding th't-a blank ~-

j observation represents a "real" signa n. -

For a particular measurement system, which may include radiochemical-separation:

i' 4.66's LLD = E V 2.22 _Y exp (-1At)  !

L j Where:

LLD = the "a priori" lower limit of detection (picoCuries'per unit mass or volume); ,

e s ti,e standard deviation of the background counting rate orf of b' = the counting rate of a. blank sample as appropr-late (counts per minute);

l e

E = the counting e.f ficiency (counts per disintegration);- -

V = the sample size (units of mass or. volume); -

2~ 22 = the number of-disintegrations per-minute per picocurie; i = the fractional- radiochemical yield, when appl _icable; A = the radioaccive decay.' constant-for..the particula-rNionuclide. (sec~2); and,.

At = the elapsed time b men environmental collection,-or end-of the- sample collect,sn period, and time of counting (sec).

Typical values of E, V, Y and.At should be used11n the calculation.

16.11-56 _

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p f . TABLE _16.11-8 (Page 3 of 3)

TABLE NOTATIONS (Continuedl a

It should be recognized .that the.LLO 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. Analyses shall be performed.in such a manner that the

. stated LLDs will be achieved under routine conditions. Occasionally l background fluctuations, unuvoidable small sample sizes. the presence of i

interfering nuclides, Lor other uncontrollable circumstances may render . 4 i- these LLDs unachievable.~ In such cases,-the contributing factors shall be identified and described in the Annual Radiological Environmental j Operating Report pursuant to Technical Specification 6.9.1.6.

4. LLD for drinking water samples. If no drinking water. pathway exists, the j- LLD of gamma isotopic analysis may be used.

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16.11 1 a

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16.11 RADIOLOGICAL EFFLUENT CONTPOLS

, RADIOLOGICAL ENVIRONMENTAL MONITORING 16.11-14 LAND USE CENSUS

)

4 COMMITMENT i-1 A Land Use Census shall be conducted and shall identify within a distance of- 8 i km (5 miles) the location in each of the 16 meteorological-sectors of the 4 nearest milk animal,' the- nearest residence, and the nearest garden

• of greater

!. than 50 m'-(500 f t") producting broad leaf vegetation.

APPLICABILITY: At'all times.

' REMEDIAL ACTION:

a. With a Land Use Census identifying a location (s)_that yields a-

]. calculated dote or dose commitment greater than-the values currently:

being calculated in SLC 16.11-9, _ identify the new location (s) in tile i

next Semiannual Radioactive Effluent Release Report pursuant to-Technical Specification 6.9.1.7.

b. With a. Land Use Census ide.itifying a location (s) that' yields a e ulculated dose or dose commitment (via.the'same exposure nathway)

! 20% greater than at a location from which samples are currently i' being obtained in accordance with SLC 16.11-13, ada_the new

. location (s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. -The sampling location (s). ..

excluding the. control station location, having the lowest _calculsted 4 dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after_0c+.ober 31 or the year in.

which this Land Use Census was conducted. Pursuant?to Technical l Specification 6.14, submit-in the next Semiannual Radioactive.

i' Effluent Release Report documentation for a change 1tn.the.00CM-including a revised figure (s) and table (s) for the ODCM reflecting

>. the new location (s), with information-supporting the change in the-4 sampling locations.-

j

• Broad leaf veget9 tion sampling _of at least three different kinds of i vegetation may be performed at the SITE BOUNDARY in each_of two different direction sectors with the highest predicted D/Qs in lieu o.f the garden censes. Commitments for broad _ leaf vegetation sampling in Table 16.11-7.4.c shall be followed, including analysis of control samples.

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-16.11-58

, - - ~. - - - .-. . . . . . . . -

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!' TESTING _ REQUIREMENTS:

j :The Land Use Census.shall be conducted.during the growing season at least once ,

per-12 months-using~that information that will provide the.best results, such .;

L as by a door-to-door survey, aerial survey, or by consulting loca. agriculture authorities. The results of the Land Use Census shall be includec in the i

Annual Radiological. Environmental Operating' Report pursuant to'Tecnnical Speci fication 6.9.1.6.

l

REFERENCES:

l 1. Catawba Offsite Dose Calculation Manual.

2. '10 CFR Part 50, Appendix I

j. BASES:

j< This commitment is provided to ensure.that' changes in the-use of areas at and beyor d the SITE BOUNDARY are-identified and that modifications to the Radiological Environmental Monitoring Program given in the- 0DCM _are made if required by the results of-this-census. The best.information from the

';- door-to-door survey, from a2 rial survey or from consulting with-local.

agricultural authorities shall be used. This census satisfies-the requircnnnts of_ Section IV.B.3 of Appendix I to 10 CFR Part- 50. Restricting

! the census to gardens of greater than 50 m2 provides assurance that significant' exposure pathways via leafy vegetables will-be identified and

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l i monitored- since a garden of- this size is the minimum required to p oduce the quantity (26 kg/ year) of leafy vegetables assumed i'i Regulatory Guide 1.109 L for consumption by a child. To determine this minimum garden size, the j- 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/m . 2 i

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16.11-59

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16.11 RADIOLOGICAL EFFLUENI_ CONTROLS RADIOLOGICAL ENVIRONMENTAL MONITORING 16.11-15 INTERLABORATORY COMPARISON PROGRAM

_ COMMITMENT Analyses shall be parformed on all radioactive materials, supplied as part of an Interlaboratory , imparison Program that'has been approved by the Commission, that correspond to samples required by Table 16 'l-7.

APFLICABILITY

At all times.

REMEDI AL_ACT_ ION:

With analyses not being performed as required above, report the corrective i actions-taken to prevent a recurrence to the Commission i t the Annual

Radiological Environmental Operating Report pursuant to Technical-Specification 6.9.1.6.

TESTING RE_QUIREMENTS:

I- The Interlaboratory Comparison Program shall be described in the 0DCM. A summary of the results obtained as part t f the above required Interlaboratory Comparison Program > hall be included in the Annual Radiological Environmentcl Operating Report pursuant to Technical Specification 6.9.1.6.

4

REFERENCES:

L 1. Catawba Offsite Dose Calculation Manual.

2. 10 CFR Part 50, Appendix I

-BASES:

t

. The requirement for participation in= an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and

~

accuracy nf the measurements of radioactive material in environmental sample i matricer are performed as part of the quality assurance program for-i- environmental 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.

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16.11 -- ,