ML20246L604

Amend 159 to License DPR-49,revising Radiological Effluent Tech Specs (RETS) to Adopt Format of NRC Model RETS for BWRs

ML20246L604
Person / Time
Site:	Duane Arnold
Issue date:	04/28/1989
From:	Hannon J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20246L609	List: ML20246L604 ML20246L611
References
NUDOCS 8905180359
Download: ML20246L604 (35)

Text

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UNITED STATES j

NUCLEAR REGULATORY COMMISSION 7,,

t WASHINGTON,0. C. 20555

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IOWA ELECTRIC LIGHT.AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN. BELT F0WER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER i

l AMENDMENT TO FACILITY OPERATING. LICENSE Amendment.No.159 License No. DPR-49 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Iowa Electric Light and Power Company, et al., dated April 24, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

l 2.

Accordingly, the license is amended by changes to the Technical Specif1-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of facility Operating License No. DPR-49 is hereby amended to read as follows:

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8905180359 890428 I

PDR ADDCK 05000331 p

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(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.159, are hereby incorporatrf in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The license amendment is effective as of the date of issuance and shall be implemented within 30 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION i

% h, John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 2'8, 1989 l

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q ATTACHMENT TO LICENSE AMENDMENT NO.159, FACILITY OPERATING LICENSE WO. DPR-49 DOCKET NO. 50-331 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

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111a 3.14-1 3.14-2 3.14-3 3.14-4 3.14-6 3.14-12 3.14-13 3.15-1 3.15-2 3.15-3 3.15-4 3.15-5 3.15-6 3.15-12 3.15-13 3.15-14 3.15-15 3.16-1 3.16-2 3.16-4 3.16-5 3.16-11 3.16-12 i

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DAEC-1 SURVEILLANCE LIMITING CONDITION FOR OPERATION REQUIREMENTS

_PAGE ND.

3.13 Fire Protection Systems 4.13 3.13-1 A.

Fire Detection Instrumentation A

3.13-1 B.

Fire Suppression Water Systen B

3.13-3 C.

Deluge and Sprinkler Systems C

3.13-5 I

D.

CO2 Systen D

3.13-6 i

E.

Fire Hose Stations E

3.13-7 F.

Fire Rated Assemblies F

3.13-8

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3.14 Radioactive Liqu'id Effluent 4.14 3.14-1 A.

Radioactive Liquid Effluent-l Instrumentation A

3.14-1 i

1 B.

Liquid Effluent Concentration B

3.14-2 C.

Dose Due to Radioactive Effluents C

3.14-3 D.

Liquid Waste Treatment D

3.14-4 3.15 Radioactive Gaseous Effluents 4.15 3.15-1 A.

Radioactive Gaseous Effluent Instr Linentation A

3.15-1 B.

Gaseous Ef fluent Concentration B

3.15-2 C.

Doses Due to Noble Gases C

3.15 3 D.

Doses Due to Iodine and Particulate in Air D

3.15-4 E.

Gaseous Radwaste Treatment E

3.15-5 F.

Explosive Gas Mixture F

3.15-6 3.16 Offsite Dose Assessment 4.16 3.16-1 A.

Doce A

3.16-1 B.

Radiological Environmental B

3.16-2 Monitoring Program C.

Interlaboratory Comparison Progran 3.16-4 D.

Radioactive Waste Solids D

3.16-5 iiia Amendment No. f3,J32,159

DAEC-1 LfMITING CONDITIONS FOR OPERAT10N SURVEILLANCE REQUIREMENT 3.14 RADI0 ACTIVE LIQUID EFFLUENT 4.14 RADI0 ACTIVE LIQUID EFFLUENT l

3.14.A Radioactive Liquid 4.14.A Radioactive Liquid Effluent l

Effluent Instrumentation Instrumentation l

3.14.A.1 The radioactive liquid 4.14.A.1 Each radioactive liquid l

effluent monitoring effluent monitoring instrumentation instranentation channels shown in channel shall be demonstrated Table 3.14-1 shall be OPERABLE OPERABLE by performance of the with their alarm and trip CHANNEL CHECX, SOURCE CHECK, CHANNEL setpoints set to ensure that the CALIBRATION, and CHANNEL FUNCTIONAL l

limits of Specification 3.14.B are TEST operations during the modes and not exceeded, at the' frequencies shown in Table 4.14-1.

APPLICABILITY: As shown in Table 3.14-1.

4.14.A.2 The setpoints shall be l

determined in accordance with the ACTION:

method described in the ODAM.

a. When a radioactive liquid effluent monitoring instrumentation channel alarm and trip setpoint is less conservative than a value which will ensure l

that the limits of 3.14.B are met, adjust without delay to meet l

Specification 3.14.B. or suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel ino per abl e.

b. When less than the minimum required liquid effluent monitoring instrument channel is OPERABLE, take the ACTION stated in Table 3.14-1 and make every reasonable effort to restore the instrument to operable status.

In the,

event the minimum required instrumentation is not returned to OPERABLE status within 30 days, explain in the next Seniannual Radioactive Material Release Report, in lieu of any other report, why the instranent was not made OPERABLE in a timely manner.

3.:,4-1 Amendment No. J99,J28,159

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DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.14.B Liquid Effluent 4.14.B Liquid Effluent Concentration Concentration 3.14.B.1 The concentration of 4.14.B.1 Each radioactive liquid radioactive material in liquid waste batch shall be supled and effluent released from the site to analyzed in accordance with Table the unrestricted area (see UFSAR 4.14-2 before release.

Figure 1.2-1) shall not exceed the concentrations specified in 10CFR Alternatively, pre-release analysis Part 20, Appendix B, Table II, of batch (es) of radioactive liquid Colmn 2 for radionuclides other waste may be by gross s or y than dissolved or entrained noble counting provided the maxima gases.

For dissolved or entrained pemissible concentration,1 x 10-7 noble gases, the concent shall not exceed 2 x 10 gation u C1/ml, is applied at the pCi/ml unrestricted area boundary.

total activity.

4.14.B.2 The' results of pre-release APPLICABILITY:

At all times, analyses shall be used with the calculational methods in the ODAM to ACTION:

establish trip setpoints for batch releases to assure that the

a. With the concentration of concentration at the restricted area radioactive material boundary does not exceed the limit released from the site to in Specification 3.14.B.

l unrestricted areas exceeding the limit, 4.14.B.3 In any week during which l

without delay restore the Service Water is released to the concentration within the unrestricted area, a grab sample of limit.

water shall be collected from that Service Water System and analyzed as specified in Table 4.14-2, Item B.1 or B.2, and Item B.4.

In the event the rr. bioactivity concentration in the service water exceeds the LLD stated in Table 4.14-2 for the analytical method used, the activity concentration shall be determined by supling and post-release analyses specified in Table 4.14-2, Items B.2 through B.S.

3.14-2 Amendment No. JU.J28,159

DAEC-1 l

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.14.C Dose Due to Radioact've 4.14.C Dose Due to Radioactive j

Ef fl uents Effl uents l

3.14.C.1 The dose or dose 4.14.C.1 Dose Calculations. In any l

comitment to a msnber of the quarter in which radioactive liquid Public from radioactive materials effluent is discharged, an in liquid effluents released to the assessment shall be perfomed in unrestricted area (see UFSAR Figure accordance with the ODAM at least 1.2-1) shall not exceed:

once per 30 days in order to verify that the cumulative dose comitment 1.5 mrem to the total body during does not exceed the limits in any calendar quarter, Specification 3.14.C.

l 5.0 mrem to any organ during any calendar quarter, 3.0 mrem to the total body during

.any calendar year, or 10.0 mrem to any organ during any calendar year.

APPLICABILITY:

At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding the above limit, prepare and submit to the Comission within 30 days from the end of the quarter during which the release occurred, pursuant to Specification 6.11.3, and in lieu of any other report, a Special Report which identifies the cause(s) for exceeding the-limit and defines the corrective actions to be i

taken.

l 3.14-3 Amendment No. J09,J28.159

DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT l

3.14.D Liquid Waste Treatment 4.14.0 Liquid Waste Treatment l

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3.14.0.1 Appropriate liquid 4.14.D.1 Each radioactive liquid l

i radwaste equipment shall be used to waste batch shall be sampled and treat any untreated batch of liquid analyzed in accordance with Table l

waste prior to discharge when a 4.14-2 before release.

pre-release analysis indicates a radioactivity concentration Alternatively, pre-release analysis (exclusive of trititan and dissolved of batch (es) of radioactive liquid noble gases) of 0.01 pCi/ml or wast'e may be by gross 8 or y counting hig her, concentration,1 x 10 yrmissibleuC1/m1, is provided the maximum p APPLICABILITY: At all times.

applied at the unrestricted area bound ary.

ACTION:

a. With radioactive liquid' waste being discharged without treatment and in excess of the above limit, prepare and subnit to the Commission within 30 days, pursuant to' Specification 6.11.3, a Special Report, in lieu of any other report, which includes the following infonnatier:

1.

Identification of equip'nent or subsystems not OPERABLE and the reason for inoperability.

2.

Action (s) taken to restore the inoperable equipnent to OPERABLE status.

3.

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

3.14-4 Amendment No. JM,159

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I TABLE 3.14-1 (Continued)

TABLE NOTATION ACTION 18 With no channel OPERABLE, effluent may be released provided that prior to initiating a release:

1.

At least two samples are analyzed in accordance with Specification 4.14.8.1, and; l

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A technically qualified member of the Facility Staff verifies

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the release rate calculations and discharge valving determined by another technically qualified Facility Staff member.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 20 With no channel OPERABLE, effluent releases via the affected pathway may continue provided the effluent is sampled and analyzed for gross radioactivity at least once per eight hours during actua1 release.

The analysis shall be capable of detecting 10-7 pCi/ml.

ACTION 21 With r.o channel OPERABLE, effluent releases via this pathway may continue provided the flow rate is estimated with pump curves at least once per batch during actual releases.

ACTION 22 With no channel OPERABLE, suspend release of radioactive effluents via this pathway.

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3.14-6 Amendment No.109,J28,159

DAEC-1 3.14.A and 4.14.A BASES l

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Radioactive Liquid Effluent Instrumentation The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the release of radioactive material in liquid effluents.

The OPERABILITY and use of these instruments implements the requirements of 10 CFR Part 50, Appendix A. General Design Criteria 60, 63, and 64.

The alarm and/or trip setpoints for these instruments are calculated in the manner described in the ODAM to assure that the alarm and/or trip will occur before the limit specified in 10 CFR Part 20.106 is exceeded.

Instrumentation is expected to be OPERABLE and in service when required by Specification.

An instrument may be. removed from service voluntarily for the purpose of tests, checks, calibration, or preventative maintenance without declaring the channel inoperable.

3.14.B and 4.14.B BASES 1.

Liquid Effluer,t Concentration Specification 3/4.14.B is provided to satisfy the regulation governing l

the maximum concentration of radioactive material in liquid effluent that may be released to an unrestricted area as stated in 10 CFR Part 20.106 and the regulation requiring surveys needed to detennine compliance stated in Part 20.201.

Conformance to Specification 3.14.B. when applied to the activity l

concentration in the river at the site boundary due to liquid effluent, would assure that the average activity concentration in liquid effluent released to the unrestricted area is a small fraction of the limit specified in Part 20.106.

The sample points noted in Table 4.14-2 are adequate to ensure sampling of potential liquid radioactive effluents from the service water systems.

The sample nints include the General Service Water System and the RHR Service Water Systems A and B.

The sample point for the RHR Service Water Systems is at a location downstream of the point where Emergency Service Water discharge joins with the RHR Service Water System, and upstream of the point where the RHR Rupture Disc Line branches off of the RHR Service Water System.

This sample point will therefore provide for sampling effluents from the RHR Service Water System Emergency Service Water System and/or RHR Rupture Disc Line.

3.14.C and 4.14.C BASES l

1.

Dose Due to Radioactive Effluents Specifications 3.14.C. 3.15.C. and 3.15.0 implement the requirements of 1

10 CFR Part 50.36a and of 10 CFR Part 50, Appendix I, Section IV.

These specifications state Limiting Conditions of Operation (LCO) to keep levels of radioactive materials in LWR effluents as low as is reasonably achievable.

Compliance with these specifications will also keep average releases of radioactive material in effluents at small percentages of the limits specified in 10 CFR Part 20.106.

Surveillance requirements provide for the measurement of releases and calculation of doses to verify compliance with the Specifications. Action statements in these Specifications implement the requirements of 10 CFR Part 50.36(c)(2) and 10 CFR Part 50, Appendix I, Section IV. A in the event a LCO is not met.

3.14-12 Amendment No. JM,128,159

DAEC-1 2.

Liquid Effluents I

With the implementation of Specification 3.14.C, there is reasonable l

I assurance that Station operation will not cause a radionuclides concentration in public drinking water taken from the River that i

exceeds the standard for anthropogenic radioactivity in community

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drinking water.

The equations in the ODAM for calculating doses due to measured releases of radioactive material in liquid effluent will be consistent with the methodology in Regulatory Guide 1.109 and 1.113.

The assessment of personal doses will examine potential exposure pathways including, as appropriate, constanption of fish and water taken from the River downstream of the discharge canal.

3.14.0 and 4.14.D BASES l

1.

Liquid Waste Treatment This specification implements the requirements of 10CFR Part 50.36a (a)

(1) that operating procedures be established and followed and that equipment be maintained and used to keep releases to the environment as low as is reasonably achievable. The specification intends that appropriate portions of the system which were used to establish compliance with the design objectives in 10CFR Part 50, Appendix I, Section II be used when specified to provide reasonable assurance that releases of radioactive material in liquid effluent will be kept as low as is reasonably achievable.

The components in the liquid radwaste system which are appropriate to process liquid waste in order to satisfy Specification 4.14.D are the floor drain demineralized and the l

radwaste demineralized.

The activity concentration, 0.01pCi/m1, below which liquid radwaste

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treatment would not be cost-beneficial, and therefore not required, is demonstrated below.

The quantity of radioactive material in liquid e{ fluent released annually from the DAEC has been calculated to be total iodines 0.11 curie 3

total others (less H )

0.25 l

Total TG curie The population dose commitment resulting from the radioactive gaterial in liquid effluent released annually has been calculated to be j

thyroid 0.164 man rem total body 0.114 Total IU7F man rem 1" Evaluation of the Duane Arnold Energy Center to demonstrate Confonnance to the Design Objectives of 10 CFR 50 Appendix I, " Iowa Electric Light & Power 3

Company, May 1976.

3.14-13 Amendment No. 109,159 l

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DAEC-1 j

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT l

3.15 RADIOACTIVE MSEOUS EFFLUENTS 4.15 RADI0 ACTIVE MSEOUS EFFLUENTS l

l 3.15.A Radioactive Gaseous 4.15.A Radioactive Gaseous Effluent Instraentation Effluent Instrumentation l

3.15.A.1 The radioactive gaseous 4.1E.A.1 Each radioactive gaseous l

effluent monitoring instrumentation effluent monitoring instraentation channels shown in Table 3.15-1 channel shall be demonstrated shall be OPERABLE.

Their OPERABLE by perfomance of the radioactive noble gas monitor alarm CHANNEL CHECK, SOURCE CHECK, CHANNEL setpoint shall be set to cause CALIBRATION, AND CHANNEL FUNCTIONAL automatic alarm when the limits of TEST operations during the MODES and l

Specification 3.15.B.1 are at the frequencies shown in Table exceeded.

4.15-1.

APPLICABILITY: As shown in Table 4.15.A.2 The setpoints shall be l

3.15-1.

detemined according to 'the method described in the ODAM,

a. With radioactive gaseous effluent monitoring instraentation channel alarm setpoint less conservative than a value which will ensure that the l

limits of 3.15.B are met, adjust without delay to l

, meet Specification 3.15. A.

declare the channel inoperable, or imediately suspend any release via the instraented pathway,

b. With less than the minimun required gaseous effluent monitoring instroent channels OPERABLE, take the action stated in Table 3.15-1 and make every reasonable effort to restore the instr aent to operable status.

In the event the minimum required instrumentation is not returned to OPERABLE status within 30 days, explain in the next Semiannual Radioactive Material Release Report, in lieu of any other report, why the instroent was not made OPERABLE in a timely manner.

3.15-1 Amendment No. J99,J28,159

DAEC-1

.s LIMITING CONDITIONS FOR OPERATION SURVE1LLANCE REQUIREMENT 3.15.B Gaseous Effluent 4.15.B Gaseous Effluent Concentration Concentration l

3.15. B.1 Tne dose rate in tne 4.15.B.1 Compliance with 3.15.B

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unrestricted area (see UFSAR Figure shall be assessed on the basis of 1.2-1) due to radioactive noble gas results of measurements specified in l

released in effluents shall not Table 4.15-2 and according to exceed SUO mrem / year to the total methodology stated in the ODAM.

body or 3000 mrem / year to skin.

l 3.15.B.2 The dose rate in the unrestricted area due to I-131,1-133, H-3, and to radioactive particulate having half-lives of 8 days or more that are released in effluents shall not exceed 1500 mrem / year to any organ.

APPLICABILITY: Whenever monitoring or sampling is required.

ACTION: When the dose rate exceeds l

a limit in 3.15.B. decrease the release rate without delay to conply with the limit.

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3.15-2 Amendment No. J99.J28,159 L_____

DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT I

3.15. C Doses Due to Noble Gases 4.15.C Doses Due to Noble Gases l

3.15.C.1 The air dose in the 4.15.C.1 Dose Assessment An unrestricted area (see UFSAR Figure assessment shall be performed in 1.2-1) due to noble gases released accord with the ODAM at least once in gaseous effluents shall not every 30 days to verify that the exceed:

cumulative air dose during the quarter and year due to noble gases 5.0 mrad frcrn gamma radiation does not exceed the limits in during any calendar quarter, Specification 3.15.C.

l 10.0 mrad from beta radiation during any calendar quarter, 10.0 mrad from gamma radiation during any calendar year, or, 20.0 mrad from beta radiation during any calendar year.

APPLIC.iBILITY:

At all times when monitors are required.

ACTION:

a. If the calculated air dose from radioactive noble gases in gaseous effluents exceeds either of the above limits prepare and submit a Special Report to the Commission within 30 days following the end of the calendar quarter during which the release occurred.

The Special Report shall be pursuant to Specification 6.11.3, shall be in lieu of any other report, and shall identify the cause(s) for exceeding the limit and define the corrective actions taken.

3.15-3 Amendment No. 199. 159

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DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.15.D Doses Due to Iodine and 4.15.0 Doses Due to Iodine and Particulate in Air Particulate in Air

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l 3.15.D.1 The dose tu a member of 4.15.D.1 An assessment she'll be l

the public ' am iodine-131,1-133, perfomed in accordance with the H-3, and % radionuclides in ODAM at least once every 31 z!ays to particula se fJrm having half-lives verify that the cinulative dose greater th.n eight days in gaseous commitment due to I-131,1-133, effluents released from the site to H-3, and radioactive particulate the unrestricted area (see UFSAR having half-lives greater than eight Figure 1.2-1) shall not exceed:

days in gaseous effluents does not exceed the limits in Specification 7.5 mrem to any organ during any 3.15.D.

l calendar quarter, or, 15.0 mrem to any organ during any calendar year.

APPLICABILITY: At all times when monitors are required.

ACTION:

a. With the calculated dose from the release of I-131, I-133, H-3, and radionuclides in particulate form having half-lives greater than eight days in gaseous effluents exceeding the above limit, prepare and submit a Special Report to the Comission within 30 days following the end of the calendar quarter during which the release occurred.

The Special Report shall be made pursuant to Specification 6.11.3, shall be in lieu of any other report, and shall identify the cause(s) for exceeding the limit and define the corrective actions taken.

3.15-4 Amendment No. JM,128,159 w____-___-____-_____

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s DAEC-1 l

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT l

3.15.E Gaseous Radwaste Treatment 4.15.E Gaseous Radwaste Treatment l

l 3.15.I.1 Every reasonable effort 4.15.E.1 The gaseous effluent l

shall be made to maintain at least monitoring systems of Specification one train of the Offgas System 3.2.0 shall be used to verify the OPERABLE.

operation of the offgas system.

Within four hours after conrnencing operation of the main condenser air ejector, at least one train of charcoal beds in the Offgas System shall be placed in operation to treat radioactive gases from the main condenser air ejector. During continuing reactor operation, at least one train of charcoal beds in the Offgas System shall be 'used to treat the gases before discharge.

APPL 3CABILITY: When the main condenser air ejector is operating.

ACTION:

a. If gaseous wastes are discharged for more than 7 days without treatment, prepare and submit a Special Report to the Commission within 30 days pursuant to Specification 6.11.3, in lieu of any other report, including the following information:

1. 3 identification of the inoperable equipment or subsysts.n and reason for inoperability.

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

3. Sunrnary description of action (s) taken to prevent a recurrence.

3.15-5 Amendment No.197 J28,159

DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT l

3.15.F Explosive Gas Mixture 4.15.F Explosive Gas Mixture

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l 3.15.F.1 The concentration of 4.15.F.1 The concentration of l

hydrogen in the offgas system hydrogen in the Offgas Systen shall downstream of the recombiners shall be determined by monitoring the be limited to < 4% by volume, offgases in the Offgas System downstream of the recombiners with APPLICABILITY:

During Offgas the hydrogen monitors.

System operation.

ACTION:

a. With the concentration of hydrogen in the main condensor offgas treatnent system downstream of the recombiners exceeding the limit, restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />,

b. In the event the hydrogen concentration is not reduced to < 4% within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, be in at least HOT SHUTDOWN or within the limit within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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l 3.15-6 Amendment No. 109,159 l

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TABLE 4.15-2 (Continued)

TABLE NOTATION a.

Table 4.14-2, Note a is a definition of the lower limit of detection (LLD).

b.

Analyses shall be perfomed following an increase of more than 50% in the steady state releases as indicated by the post-treat noble gas l

activity monitor, after factoring out the effect due to a change in reactor power.-

c.

Sample media shall be changed at least once per seven days and the analysis completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after reoval from the sampler). Analyses shall also be perfomed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> following an increase of more than 50% in the steady state release as indicated by the post-treat noble gas activity monitor, after factoring

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'out the effect due to a change in reactor power. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less are analyzed, the corresponding LLD may be increased by a factor of 10.

d.

The ratio of the sample flow rate to the sampled stream flow rate shall l

be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.15.B. 3.15.C and 3.15.0.

e.

The princhal gamma emitters for which the LLD specification will apply are exclusively the following radion. ' ides: Kr-87, Kr

• .8, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54 Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD may be reported as "less than" their respective LLD and should not be reported as being present at the LLD of the nuclide. Each measured radionuclides concentration is used in a required concentration or dose calculation only if it is detected at or above the LLD. When unusual ciremstances persist more than 30 days and cause LLD higher than required, the reasons shall be doceented in the Semiannual Radioactive Material Release Report.

f.

A quarterly composite sample shall include an equal fraction of each weekly particulate sample collected during the quarter.

g.

An H-3 grab sample will also be taken from the Offgas Stack or Reactor Building Vent when the reactor head is removed.

l 3.15-12 Amendment No. Jg),159

DAEC-1 3.15. A and 4.15. A BASES l

1.

Radioactive Gaseous Effluent Instraentation The radioactive gaseous effluent instraentation is provided to monitor the release of radioactive materials in gaseous effluents and, as appropriate, to control potential releases.

Instraentation for monitoring the concentration of potentially explosive gas mixtures in the main condenser offgas treatment syste is also provided. The presence of instraents for monitoring both radioactive and explosive gaseous effluents is depicted in ODAM F.igure 3-1.

The OPERABILITY and use of these instraents implements the requirements of 10CFR Part 50, Appendix A, General Design Criteria 60, 63, and 64.

Reactor building exhaust ventilation shaft radiation monitors initiate isolation of the reactor building nomal ventilation and start standby gas treatment when a high trip point is reached.-

DAEC is equipped with a radioactive gaseous. effluent monitoring system, r

which includes detectors at the offgas stack (R3), the reactor building vent (R4), the turbine building vent (R5), and the LLRPSF vent. A roote indication and control unit located near each detector displays the detector reading and, whenever the setpoint is exceeded, an indicator light. The data are also routed to a control computer and a control room display and, except for the LLRPSF vent detector, do not cause a trip to isolate the ventilated area. The LLRPSF vent detector does isolate the LLRPSF ventilation system.

However, the isolation function is not required by regulation but is provided as an engineering design conservatism.

In the event the control computer and/or control room display fail to function or are voluntarily taken out of service, each remote indication and control unit is designed to acquire data for up to 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

It is intended that each affected ruote indication and control unit display be observed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (in which case the affected channel remains OPERABLE).

w If an alam trip setpoint is exceeded at the same time the control computer and/or control room display are neither functioning nor in service, alam annunciation will still occur in the control room.

In the event the detector reading and the indication of exceeding the monitor setpoint are not provided at either the control room or the remote indication and control unit, then the affected channel is not OPERABLE and DAEC will either perfom the appropriate ACTION or will provide an alternate monitoring system. This permits DAEC to retain the GE gaseous monitoring systs as an alternate syste for nomal effluent monitoring when the Kaman system is temporarily inoperable.

When used as an alternate monitoring system, the GE system is subject to the requirements stated in Specifications 3.15.A and 4.15. A and to l

LLD requirements stated in Table 4.15-2 Its C.

3.15-13 Amendment No. 199,125.JM,159

DAE0-1 2.

Not used 3.

Gaseous Effluents Assessments of dose required by Specifications 4.15.C and 4.15.D to l

verify compliance with Appendix I,Section IV are based on measured radioactivity in gaseous effluent and on calculational methods stated in the ODAM.

Pathways of exposure and location of individuals are selected such that the dose to a nearby resident is unlikely to be underestimated. Dose assessment methodology described in the ODAM for gaseous effluent will be consistent with the methodology in Regulatory Guides 1.109 and 1.111.

Cumulative and projected assessments of dose made during a quarter are based on historical average meteorological conditions measured at DAEC. Assessment made for the annual radiological environmental report will be based on annual averages of atmospheric conditions during the period of release.

3.15.B and 4.15.B BASES

>l Gaseous Effluent Concentration This specification is intended to ensure that the concentration of radioactive material in the unrestricted area beyond the site boundary due to gaseous effluents from DAEC will maintain doses within the annual dose limits to unrestricted area provided in 10 CFR Part 20.

Compliance with these limits also reasonably assures that radioactive material in gaseous effluents will not result in exposure of a mober of the public in an unrestricted area to annual averaged concentrations

' exceeding the limit in 10 CFR Part 20.106.

The occupancy time of members of the public who may occasionally be on the site is expected to be low enough to compensate for any less atmospheric dispersion on l

site than to the environs offsite.

Assessment of compliance is based upon an effluents measurement program defined in Table 4.15-2 and methodology stated in the ODAM.

Tne resolving time of the measurements, ie., the sample integration time, bounds the minimum averaging time of the effluent measurements waste stre ams.

The Standby Gas Treatment System is considered an Engineered Safety Feature and not an exhaust ventilation treatment system. Thus the exhaust ventilation system discharges via the reactor building v ent.

3.15.C and 4.15.C BASES l

Doses due to Noble Gases These specifications implement the requirements of 10 CFR Part 50, Appendix I.

3.15-14 Amendment No.199,J28,159

DAEC-1 3.15.D and 4.15.0 BASES Doses due to Iodine and Particulate in Air These specifications implement 10 CFR Part 50, Appendix 1.

The dose calculation methods in the ODAM depend on existing pathways of exposure to a member of the public or more conservative conditions assumed (yielding a higher calculated dose). Calculations and methods are such that an estimate of the dose to a member of the public is not likely to be underestimated substantially.

3.15:E and 4.15.E BASES 1.

Gaseous Radwaste Treatment This specification impiments the requirment of 10 CFR Part 50.36a (a)(1). that operating procedures be established and followed and that equipment be maintained and used to keep releases to the environment as low as is reasonably achievable.

In order to satisfy Technical Specification 3.15.E, every reasonaole effort shall be made to maintain and operate at least one train of the Offgas System charcoal adsorbers l

with pre-and aft-particulate filters to process radioactive gaseous effluent prior to release. The specification that the Offgas System which was used to establish compliance with the design objectives in 10CFR Part 50, Appendix I, Section II be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable.

ODAM Figure 3-1 is a flow diagram depicting gaseous radioactive waste streams. The Standby Gas Treatment System is considered an Engineered Safety Feature and not an exhaust ventilation treatment system.

3.15.F. and 4.15.F BASES 1.

Explosive Gas Mixture Specification 3/4.15.F is provided to ensure that the concentration of l

potentially explosive gas in the offgas treatment sytem downsteam of the recombiners is maintained below the flannability limit of a hydrogen and oxygen mixture in the. system. Keeping the mixture below its flammability limit will provide assurance that offgas treatment system integrity and operability is maintained and that the radioactive material concentration in the offgas will be controlled in confomance with 10CFRPart 50, Appendix A, Criterion 60.

Calibration gas concentrations will be within the range of interest for hydrogen concentration and will not include 0% or 100% hydrogen concentrations.

3.15-15 AmendmenitNo. 199,159 l

A

DAEC-1 o

LIMlTING CONDITIONS FOR OPERATION

_ SURVEILLANCE REQUIREMENT l

3.16 0FFSITE DOSE ASSESSMENT 4.16 0FFSITE DOSE ASSESSMENT l

l 3.16.A Dose 4.16.A Dose l

l 3.16.A.1 The annual dose or dose 4.16.A.1 Cumulative dose l

comitment to any member of the contributions from liquid and gaseous public due to radiation and effluents to a member of the public radioactive material in effluents offsite shall be evaluated at least from DAEC shall not exceed 75 mrem once every year as described in the to his thyroid or 25 mrem to his ODAM.

total body or any other organ.

APPLICABILITY: At all times.

ACTION:

a.

If the calculated dose from radioactive material released in liquid or gaseous effluents exceeds twice the limits of Specifications 3.14.C, 3.15.C.

or 3.15.0, perfonn an assessment of compliance with 40 CFR 193 and limit subsequent releases such that the dose or dose commitment to a member of the public is < 75 mram to his thyroid and < 75 mrem to his total body or any other crgan over 12 consecutive months including the period of elevated release, b.

If the estimated dose exceeds either limit in Specificati9n l

3.16. A. prepare and submit a Special Report to the NRC within 30 days in lieu of any other report; it shall include the cause of the release of exposure, an estimate of the dose to the likely most exposed member (s) of the public, corrective actions taken or planned to prevent a recurrence, and a schedule for achieving compliance.

If the condition causing the limit (s) to be exceeded has not been corrected the Special Report may also s, tate a request for 6 variance in accordance with the provisions of 40 CFR Part 190.

In that event, the request is timely and a variance is granted until NRC action on the request is complete.

3.16-1 Amendment No. JD, 159

DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.16.B Radiological Environmental 4.16.B Radiological Environmental Monitoring Program Monitoring Program l

3.16. B.1 A radiological 4.16.B.1 Sampling and analyses l

environmental monitoring program required in Table 3.16-1 shall be shall be conducted as specified in performed such that the detection Table 3.16 1.

capabilities specified in Table l

3.16-2 are achieved under routine APPLICABILITY: At all times.

conditions.

If a sample analysis does not meet the LLD specified, j

ACTION:

report, the reason attributed in the next Annual Radiological

a. In the event the Environmental Report.

radiological environmental monitoring program is not 4.16.B.2 Land Use Census DAEC l

conducted as specified in shall conduct annually a land use the Table 3.16-1, prepare census within three miles of the and submit to the Station to identify radiologically Commission in the Annual important changes in land use.

Radiological Enviremental Report the reasons for not conducting the program in accord with the Table 3.16-1 and the plans for preventing a recurrence,

b. In the event radioactivity in a sampled environmental medium, averaged over a calendar quarter is attributableto6AECand exceeds an appropriate value listed in Table 3.16-3 or, if not listed, causes a potential annual dose exceeding two times the quarterly dose limit in Specification 3.14.C or 3.15.0,Conrnission within 30 prepare and submit to the days after discovery a Special Report which includes an evaluation of any release conditions, environmental factors or other conditions which caused the value(s) of Table 3.16-3 or two times the quarterly dose limit to be exceeded and which defines the corrective actions to be taken.

If the radioactivity in environmental sample (s) is not attributable to releases from the Station the Special Report is not, 3.16-2 Amendment No. J07 J28,159 i

)

DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT I

l 3.16.C Interlaboratory Comparison Program l

3.16.C.1 Analyses shall be performed on radioactive materials supplied in an Interlaboratory Comparison Program which has been approved by the NRC.

APPLICABILITY: Applicable to the Radiological Environmental Monitoring Program at all times.

ACTICN:

In the event analyses were not performed as required in l.

Specification 3.16.C. report the corrective actions taken to prevent a recurrence in the Annual Radiological. Environmental Monitoring Report.

3.16-4 Amendment No. 107, 159 l

DAEC-1

\\

LIMITING COND1110NS FOR OPERATION SURVEILLANCE REQUIREMENT l

3.16.D Radioactive Waste Solids 4.16.D Radioactive Waste Solids l

l 3.16.D.1 Appropriate equipment 4.16.0.1 The Process Control l

shall be operated in accordance Progran shall state the essential with a Process Control Progra to operating parameters of the process wet radioactive waste process (es), the essential solids destined for disposal to a characteristics of the waste form to form that meets appropriate be shipped, and the essential requirements of 10 CFR Part 61.56 product verification requirements.

before the waste is shipped from the DAEC site.

APPLICABILITY:

'Ouring Processing of radioactive waste solids for dispossi.

ACTION:

1.

Suspend delivery to a transport carrier of any container of radioactive waste not complying with 10 CFR Part 61.56.

I l

)

3.16-5 Amendment No. 109,J28,159 l

1

r DAEC-1 3.16. A and 4.16.' A BASES J'

1.

Dose Specification 3.16. A is provided to comply with the dose limitation requirement of 40CFR190.

This specification requires the assessment of dose to demonstrate that a person (a-nearby resident) has not received i

a radiation dose exceeding that specified in 40CFR190. including doses-l from direct radiation. There is no other licensed nuclear fuel ~ cycle facility within 50 miles of DAEC, thus it is assmed that the dose from other uranin fuel' cycle f acilities is negligible.

In the event 'a report is required to satisfy Specification 3.16. A. Action b, it shall be deemed adequate-to satisfy the reporting requirment in Specification 6.11.1.g.(5).

3.16.B and 4.16.B BASES 1.

Radiological Environmental Monitoring The radiological environmental monitoring program, including the land use census, is conducted to satisfy the requirements of 10CFR Part 50, Appendix I, Section IV.B.2 and.3.

The minimun radiological monitoring '

program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring _ program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pai.hways.

The land use census is conducted annually to identify changes in use of the unrestricted area in' order to recommend modifications in monitoring programs for evaluating individual doses from principal exposure pathways.

It' may be conducted by door-to-door survey, by aerial survey, or by consulting with local agricultural or governmental authorities.

In order that radiological environmental monitoring stations may be relocated to reflect current conditions, the locations of stations required by Table 3.16-1 are described in a section of the Offsite Dose Assessment Manual.

Revisions thereto are administered in accordance with Specification 6.15.

IELP may conduct additional environmental monitoring exclusive of the requirements of Specifications 3.16.8 and 6.11.1.g.

3.16.C BASES 1.

Interlaboratory Comparison Progra The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in 3.16-11 Amendment No. 199 159

)

i environmental sample matrices are perfomed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

3.16.D and 4.16.D BASES l

1.

Radioactive Waste Solids This specification implements the requirements of 10 CFR Part

-50.36a(a), the General Design Criterion 60 of 10 CFR Part 50 Appendix i

A, and of 10 CFR Part 61.56 on characteristics of low-level radioactive wastes destined for disposal by burial, Applicable requirements on packaging and delivery of packages of radioactive material to a carrier for transport sttted in 10 CFR Part 71 and on transportation of hazardous matertAs in 49 CFR 171-179 are not restated in the technical i

specifications.

Drocessing waste to meet characteristics permitted under 10 CFR Part ol.56 may include solidification, preparation for deposit in a high integrity container, or any fonn acceptable under Part 61 for shipment to and receipt by a licensed disposal facility or licensed radioactive waste processor.

It is intended that a Contractor may perform the waste processing provided he operates according to a Process Control Program approved in accordance with Technical Specification 6.15.

i i

1 1

3.16-12 Amendment No. J09,J28,159

(

4 DAE0-1 2.

Not used 3.

Gaseous Effluents Assessments of dose required by Specifications 4.15.C and 4.15.D to l

verify compliance with Appendix I,Section IV are based on measured radioactivity in gaseous effluent and on calculational methods stated in the ODAM.

Pathways of exposure and location of. individuals are j

selected such that the dose to a nearby resident is unlikely to be underestimated.

Dose assessment methodology described in the ODAM for gaseous effluent will be consistent with the methodology in Regulatory Guides 1.109 and 1.111.

Cumulative and projected assessments of dose made during a quarter are based on historical average meteorological conditions measured at DAEC. Assessment made for the annual radiological environmental report will be based on annual averages of atmospheric conditions during the period of release.

3.15.B and 4.15.B BASES l

Gaseous Effluent Concentration This specification is intended to ensure that the concentration of radioactive material in the unrestricted area beyond the site boundary due to gaseous effluents from DAEC will maintain doses -within the annual dose limits to unrestricted area provided in 10 CFR Part 20.

Compliance with these limits also reasonably assures that radioactive material in gaseous effluents will not result in exposure of a member of the public in an unrestricted area to annual averaged concentrations exceeding the limit in 10 CFR Part 20.106.

The occupancy time of members of the public who may occasionally be on the site is expected to be low enough to compensate for any less atmospheric dispersion on site than to the environs offsite.

Assessment of compliance is based upon an effluents measurement program defined in Table 4.15-2 and methodology stated in the ODAM. The resolving time of the measurements, ie., the sample integration time, bounds the minimum averaging time of the effluent measurements waste stre ams.

The Standby Gas Treatment System is considered an Engineered Safety Feature and not an exhaust ventilation treatment system. Thus the exhaust ventilation systen discharges via the reactor building vent.

3.15.C and 4.15.C BASES l

Doses due to Noble Gases l

These specifications implement the requirements of 10 CFR Part 50, Appendix I.

i 3.15-14 Amendment No. 199,J28,159

e DAEC-1 3.15.0 and 4.15.0 BASES Doses due to Iodine and Particulate in Air These specifications implement 10 CFR Part 50, Appendix I.

The dose calculation methods in the ODAM depend on existing pathways of exposure to a member of the public or more conservative conditions assuned (yielding a higher calculated dose). Calculations and methods are such that' an estimate of the dose to a member of the public is not likely to be underestimated substantially.

3.15.E and 4.15.E BASES 1.

Gaseous Radwaste Treatment This specification implements the requirement of 10 CFR Part 50.36a 1

(a)(1) that operating procedures be established and. followed.and that equipnent be maintained and used to keep releases to the environment as low as is reasonably achievable.

In order to satisfy Technical Specification 3.15.E. every reasonable effort shall be made to maintain and operate at least one train of the Offgas System charcoal adsorbers l

with pre-and aft-particulate filters to process radioactive gaseous effluent prior to release. The specification that the Offgas System which was used to establish compliance with the design objectives in 10CFR Part 50, Appendix I, Section II be used when specified provides reasonable assurance that the releases of radioactive materials in gaseou: af"uents will be kept as low as is reasonably achievable.

ODAM Figure 3-1 is a flow diagram depicting gaseous radioactive waste streams. The Standby Gas Treatment System is considered an Engineered Safety Feature and not an exhaust ventilation treatment system.

3.15.F and 4.15.F BASES 1.

Explosive Gas Mixture Specification 3/4.15.F is provided to ensure that the concentration of l

i potentially explosive gas in the offgas treatment sytem downsteam of the recombiners is maintained below the flammability limit of a hydrogen and oxygen mixture in the system. Keeping the mixture below its flammability limit will provide assurance that offgas treatment system integrity and operability is maintained and that the radioactive l

material concentration in the offgas will be controlled in confomance with 10CFRPart 50, Appendix A, Criterion 60. Calibration gas concentrations will be within the range of interest for hydrogen concentration and will rot include 0% or 100% hydrogen concentrations.

l l

3.15-15 AmendmentNo. JSP,159 I

4 DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT l

3.16 0FFSITE DOSE ASSESSMENT 4.16 0FFSITE DOSE ASSESSMENT l

l 3.16.A Dose 4.16.A Dose l

I l

3.16.A.1 The annual dose or dose 4.16.A.1 Cumulative dose l

comitment to any member of the contributions from liquid and gaseous 1

public due to radiation and effluents to a member of the public radioactive material in effluents offsite shall be evaluated at least from DAEC shall not exceed 75 mrem once every year as. described in the to his thyroid or 25 mren to his ODAM.

total body or any other organ.

APPLICABILITY: At all times.

ACTION:

~

a.

If the calculated dose from r adioactiv'e material released in liquid or gaseous effluents ecceeds twice the limits of Specifications 3.14.C 3.15.C.

or 3.15.D, perfonn an assessment of compliance with 1

40 CFR 190 and limit subsequent releases such that the dose or dose connitment to a member of the public is < 75 mram to his thyroid and < 75 mrem to his tott body or any other crgan over 12 consecutive months including the period of elevated release.

b.

If the estimated dose exceeds either limit in Specification l

3.16. A, prepare and submit a Special Report to the NRC within 30 days in lieu of any other report; it shall include the cause of the release of exposure, an estimate of the dose to the likely most exposed member (s) of the public, corrective actions taken or planned to prevent a recurrence, and a schedule for achieving compliance.

If the condition causing the limit (s) to be exceeded has not been corrected, the Special Report i

may also state a request for a variance in accordance with the provisions of 40 CFR Part 190.

In that event, the request is timely and a variance is granted until NRC action on the request is complete.

j DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.16.B Radiological Environmental 4.16.B Radiological Environmental Monitoring Program Monitoring Program l 3.16.B.1 A radiological 4.16.8.1 Sampling and analyses

[

environmental monitoring program required in Table 3.16-1 shall be I

shall be conducted as specified in performed such that the detection Table 3.16-1.

capabilities specified in Table 3.16-2 are achieved under routine APPLICABILITY: At all times.

conditions.

If a sample analysis does not meet the LLD specified, ACTION:

report the reason attributed in the next Annual Radiological

a. In the event the Environmental Report.

radiological environmental monitoring program is not 4.16.8.2 Land Use Census DAEC

.[

conducted as specified in shall conduct annually a land use the Table 3.16-1, prepare census within three miles of the and submit to the Station to identify radiologically Commission in the Annual important changes in land use.

Radiological Environmental Report the reasons for not conducting the progr n in accord with the Table 3.16-1 and the plans for preventing a recurrence.

b. In the event radioactivity in a sampled environmental media, averaged over a calendar quarter is attributable to 6AEC and exceeds an appropriate value listed in Table 3.16-3 or, if not listed, causes a potential annual-dose exceedin two times the quarter 1 dose limit in Specific tion 3.14.C or 3.15.D. prepare and submit to the Comission within 30 days after discovery a.

Special Report which includes an evaluation of any release conditions, environmental factors or other conditions which caused the value(s) of Table 3.16-3 or two times the quarterly dose limit to be exceeded and which defines the corrective actions to be taken.

If the radioactivity in environmental sample (s) is not attributable to releases from the Station the Special Report is not, 3.16-2 Amendment No. J97 J28,159

r

.,j.

J DAEC-l' l'

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT l

-l 3.16.C Interlaboratory Comparison l

Program

-l 3.16.C.1 Analyses shall be performed on radioactive materials supplied in an Interlaboratory Comparison Program which has been approved by the NRC.

APPLICABILITY:. Applicable to the Radiological Environmental Monitoring Program at.all times.

ACTION:

In the event analyses were not performed as required in l.

Specification 3.16.C.. report the' corrective actions.taken to prevent i

a recurrence in the Annual Radiological Environmental Monitoring Report.

i l

l l

3.16-4 Amendment No. 199 159

.~

DAEC-1 t

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT l

3.16.0 Radioactive Waste Solids 4.16.D Radioactive Waste Solids l

l 3.16.D.1 Appropriate equipment 4.16.D.1 The Process Contro1 l

shall be operated in accordance Program shall state the essential with a Process Control Program to operating parameters of the process wet radioactive waste process (es), the essential solids destined for disposal to a characteristics of the waste form to form that meets appropriate be shipped, and the essential requirements of 10 CFR Part 61.56 product verification requirements.

before the waste is shipped from the DAEC site.

APPLICABILITY:

During Processing of radioactive waste solids for di spo s al.

ACTION:

1.

Suspend delivery to a transport carrier of any container of radioactive waste not complying with 10 CFR Part 61.56.

1 3.16-5 Amendment No. J09.J28,159

o DAEC-1 3.16. A and 4.16. A BASES 1.

Dose Specification 3.16. A is provided to comply with the dose limitation i

requirement of 40CFR190.

This specification requires the assessment of dose to demer': rate that a person (a nearby resident) has not received a radiation os 4 exceeding that specified in 40CFR190 including doses from direct radiation. There is no other licensed nuclear fuel cycle facility within 50 miles of DAEC, thus it is assmed that the dose from other uranitrn fuel cycle f acilities is negligible.

In the event a report is required to satisfy Specification 3.16. A, Action b, it shall l

be deemed adequate to satisfy the reporting requirement in Specification 6.11.1.g.(5).

I 3.16.B and 4.16.B BASES 1.

Radiological Environmental Monitoring The radiological environmental monitoring program, including the land use census, is conducted to satisfy the requirements of 10CFR Part 50, Appendix 1,Section IV.B.2 and.3.

The minimm radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring progran by verifying that the measurable concentrations of radioactive materials anti levels of radiation are rot higher than expected on the basis of the effluent measurements and modeling of the envirorrnental exposure paihways.

The land use census is conducted annually to identify changes in use of the unrestricted area in order to recommend modifications in monitoring programs for evaluating individual doses from principal exposure pathways.

it may be conducted by door-to-door survey, by aerial survey, or by consulting with local agricultural or governmental authorities.

In order that radiological environmental monitoring stations may be relocated to reflect current conditions, the locations of stations required by Table 3.16-1 are described in a section of the Offsite Dose Assessment Manual. Revisions thereto are administered in accordance with Specification 6.15.

IELP may conduct additional environmental monitoring exclusive of the requirements of Specifications 3.ta S and 6.11.1.g.

3.16.C BASES 1.

Interlaboratory Comparison Program i

The requirmnt for participation in an Interlaboratory Comparison l

Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in 3.16-11 Amendment No. J09,159

\\

i environmental sample matrices are performed as part of the quality I

assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

l 3.16.D and 4.16.0 BASES l

1.

Radioactive Waste Solids l

This specification implements the requirements of 10 CFR Part 50.36a(a), the General Design Criterion 60 of 10 CFR Part 50 Appendix l

A, and of 10 CFR Part 61.56 on characteristics of low-level radioactive i

wastes destined for disposal by burial. Applicable requirements on l

packaging and delivery of packages of radioactive material to a carrier for transport stated in 10 CFR Part 71 and on transportation of hazardous materials in 49 CFR 171-179 are not restated in the technical specifications.

Processing waste to meet characteristics permitted under 10 CFR Part 61.56 may include solidification, preparation for deposit in a high integrity container, or any form acceptable under Part 61 for shipment to and receipt by a licensed disposal facility or licensed radioactive I

waste processor.

It is intended that a Contractor may perform the waste processing provided he operates according to a Process Control Program approved in accordance with Technical Specification 6.15.

3.16-12 Amendment No. 109,J28,159 a

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _