ML20024C168

Tech Spec Re Monitoring,Instrumentation & Valves

ML20024C168
Person / Time
Site:	Crane
Issue date:	07/07/1983
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20024C161	List: ML20024C160 ML20024C163 ML20024C168
References
NUDOCS 8307120352
Download: ML20024C168 (23)

Text

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i 2-1 LIMITING CONDITIONS FOR OPERATION 2.0 MON 1TORING REQUIREENTS 2.1 Radioactive Dis &arges 2.1.1 Liould Effluents i

Applicability i

Applies to the controlled release of radioactive liquids from TMI Unit No. 2.

Objective Objective To define the limits and conditions To ensure that radioactive i

for the controlled release of liquid liquid releases from the radioactive effluents to the environs facility are within the limits l"

to ensure that these releases are as of Specifications 2.1.1 a.

low as practicable. These releases through f.

should not result in radiation exposures to off site areas greater than a few percent of ba& ground exposures. The instantaneous releases rate for all effluent disdarges should be within the limits specified in 10 TR Part 20.

To assure that the releases of radioactive liquids to off site areas meet the "as low as practicable" concept, the following objectives apply-

a. The annual total quantity of radioactive materials in liquid waste, excluding tritium and dissolved gases, should not exceed 5 curies per radioactive waste-producing reactor, and the annual. dose to the whole body or any organ of an individual should not exceed 3 mrem to the total body and shall be less than or equal to 10 t

mrem to any organ.

b. The annual average concentration of radioactive materials in the offluent from the Mechanical Draft Cooling Towers prior to dilution in the Susquehanna River, excluding tritium and dissol d gases, should not exceed 2 x 10 uci/ml.

8307120352 830707 PDR ADOCK 05000320 P

PDR

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2-2 LIMITING CONDITIONS FOR OPERATION 2.0 MONITORING REQUIREE NTS Objective (Cont'd)

c. The annual average concentration of tritium in liquid waste prior to dilution in the environment should not exceed 5 x 10-6 uCi/ml.

Specification Specification

a. The radioactivity release During release of liquid radioactive concentration in liquid effluents wastes from the Waste Evaporator from lhit No. 2 to the environment Condensate Storage Tank and the Waste l shall.not exceed the values Evaporator Condensate Test Tank, the specified in 10 CFR 20, Appendix B, following conditions shall be met.

for unrestricted areas.

A. The liquid gross activity monitor

b. The total release of radioactive (Unit 2: WOL-R-1311) or similar l

liquid effluent from Unit No. 2, device, and recorder on the radwaste excluding tritium and noble gases, effluent line shall be operable, shall not exceed 10 curies during any calendar quarter.

B. The liquid gross activity monitors l (Unit 2: WOL-R-1311) or similar

c. The equipment installed in the device shall be set to alarm and liquid radioactive waste system shall automatically close waste discharge be maintained and shall be operated valve (thit 2: WDL-V-99) respectively j

to process all radioactive liquid prior to exceeding the limits wastes prior to this discharge when specified in 10 CFR 20, Appendix B for the activity release rate will exceed unrestricted areas.

1.25 curies, excluding tritium and l

dissolved gases, during any calendar C. Liquid waste radioactivity and fl'ow quarter.

rate from the Waste Evaporator Condensate Test Tank (Unit 2) shall be

d. The maximum radioactivity to be continuously monitored and recorded contained in one liquid radwaste during release.

If this requirement tank, excluding tritium and dissolved camot be met, continued release of gases, that can be discharged liquid effluents shall be permitted directly, to the environs, shall not only during the succeeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> exceed 10 curies.

provided that during this 48-hour period two independent samples of each

e. When the average release rate of tank shall be analyzed and two station radioactive effluents, excluding personnel shall independently check tritium and dissolved gases, exceeds valve line-up prior to the discharge.

2.5 curies per radioactive waste-producing reactor during any calendar D. Facility records shall be main-L quarter, the licensee shall notify tained of the radioactive concentra-l the NRC within 30 days, identifying tions and volume before dilution of the causes and describing the each batch of liquid effluent proposed program of action to reduce released, and the average dilution such release rates.

flow and length of time over which each discharge occurred. Estimates of the error associated with each reported value should be included in facility records.

I

2-3 LIMITING CONDITIONS FOR OPERATION 2.O MONITORING REQUIREMENTS Specification (Cont'd)

Specification (Cont'o)

"For the purposes of this E. Radioactive liould waste sampling specification, the MPC (168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />) and activity analysis shall be w

for Xe-133 is 5 x 10-3 sci /ml.

performed in accordance with Table The MPCw (168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />) for Xe-135 is 1 2.3-1.

Prior to the release of each x 10-3p C1/ml".

batch of liauld effluent, a sample shall be taken from that batch and

f. The dose or dose commitment from analyzed for the concentration.of each liquid effluents shall be less than significant gamma emitter to or equal to 3 mrem total body and_

demonstrate compliance with less than or equal to 10 mrem to any Specification "a" using the flow into organ for the calendar year.

which the effluent is discharged.

F. The liauld effluent radiation g

monitor WDL-R-1311 shall be calibrated I

at least quarterly by means of a known radioactive source. WDL-R-1311 shall l

also have an instrument channel test monthly and a source check prior to each discharge to verify that the read-out device is indicating as expected.

G. The ability of WDL-V-99 to close automatically on receipt of a high radiation alarm signal from WDL-R-1311 l

shall be checked annually.

Bases Bases Liquid radioactive waste release Specifications A, B, and C, above levels to unrestricted areas should reauire that suitable eouipment to be kept "as low as practicable" and monitor the release of radioactive are not to exceed the concentration materials in 11auid effluents are limits specified in 10 CFR 20. The operating during any period these specifications provide reasonable releases are taking place.

assurance that the resulting annual exposure to an individual in off site The surveillance reouirements given in areas will not exceed the design the remaining specifications provide objectives of Appendix I to 10 CFR assurance that liquid wastes are Part 50, which were established as properly controlled and monitored requirements for the cleanup of TMI-2 during any planned release of in the NRC's' Statement of Policy of radioactive materials in liouid

' April 27, 1981. This assurance is ef fluents.

based on the fact that the Susauehanna River will dilute the liquid effluents upon their release

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_ ___ ~ _ _ _ _ _

2-4 TABLE 2.3-1 9

Radioactive Liquid Waste Sampling and Analysis (4, 5)

A.

Monitor Tank Releases Type of Detectable Samplino Frecuency Activity Analysis Concentration (3)

Each Batch Individual Gamma 5 x 10-7 uci/ml (2)

H-3 10-5 uci/ml Monthly Composite (1)

Gross Alpha 10-7 uci/ml Sr-89 5 x 10-8 uci/ml Sr-90 5 x 10-8 uci/ml Notes (1) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant.

(2) For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near this sensitivity limit when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using measured ratios with those radionuclides which are routinely identified and meacured.

l (3) The detectability limits for radioactivity analysis are based on the l

technical feasibility and on the potential significance in the environment of the quantities released. For some nuclides, lower l

i detection limits may be readily achievable and when nuclides are measured l

below the stated limits, they should also be reported.

(4) The results of these analyses should be used as the basis for recording and reporting the quantities of radioactive material released in liquid l

effluents during the sampling period.

In estimating releases for a l

period when analyses were not performed, the average of the two adjacent data points spanning this period should be used. Such estimates should be included in the effluent records and reports; however, they should be clearly identified as estimates, and the method used to obtain these data l

should be described.

l (5) Deviations from the sampling / analysis regime will be noted in the report specified in Section 5.6.1.

=

'A I

2-5 LIMITING C0tOITIONS FOR OPERATION 2.0 MONITORING REQUIREMENTS 1

Bases (Cont'd)

Beses (Cont'd) from the site. The effluents will be These surveillance requirements pro-diluted by a factor of about 250 in vide the data for the licensee and the i

the region where finfish can exist commission to evaluate the station's (within a one-quartel: mile radius of performance relative to radioactive the discharge point). At the same liquid wastes released to the time these specifications permit the environment. Reports on the flexibility of operation, compatible quantities of radioactive materials with considerations of health and released in liquid effluents shall be safety, to assure that the public is furnished to the Commission on the 4

provided a dependable source of power basis of Section 5.6.1 of these under unusual operating conditions, Technical Specifications. On the which,may temporarily result inhigher basis of such reports and any than normal releases, but still additional information obtained from within the concentration limits the licensee or others,-the Commission specified in 10 CFR 20.

It is may require the licensee to take expected that by using this appropriate action.

operational flexibility under unusual operating conditions, and exerting every effort to keep levels of radioactive material in liquid wastes as low as practicable, the annual releases will not exceed a small fraction of the annual average concentration limits specified in 10 CFR 20.

Specification a. above requires the licensee to limit the concentration of radioactive materials in liquid effluents from TMI-2 to levels specified in 10 CFR 20, Appendix B, for unrestricted areas. This spec-ification provides assurance that no member of the general public can be exposed to liquids containing radio-active materials in excess of limits considered permissible under the comission's rules and regulations.

Specification b. above establishes an upper limit for the release of radio-active liquid effluents, excluding tritium and dissolved gases, of 10 curies during any calendar quarter.

The intent of this specification is to permit the licensee the flexibility of operation to assure that the public is provided a

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2-6 LIMITING CONDITIONS FOR OPERATION 2.0 MONITORING REQUIREENTS Bases (Cont'd)

Bases (Cont'd) dependable source of power under unusual operating conditions, which may temporarily result in releases hitfier than the levels normally actilevable when the unit and the liquid radwaste equipment are functioning as desicyied. Releases of up to 10 curies during any calendar quarter will result in concentrations of radioactive materials in liquid effluents at small percentages of the limits specified in 10 CFR 20.

Specification c. requires the the licensee shall maintain and operate the~ equipment installed in the liquid radioactive waste system to reduce the release of radioactive materials in liquid effluents to as low as practicable, consistent with the requirements of 10 CFR 50.36a.

Normal use and maintenance of installed equipment in the liquid radioactive system is expected to result in releases of not more than about five curies per year, excluding tritium and dissolved gases during normal operations.

In order to keep releases of radioactive materials as low as practicable, the specification requires, as a minimum, operation of equipment whenever the rate of release exceeds 1.25 curies per quarter, excluding tritium and dissolved gases.

In addition to the limiting condi-tions for operation listed under Specification b., the reporting requirements of Specification e., the requirements of Section 5.6.2, delineate that the licensee shall identify the cause whenever the rate of radioactive effluents, excluding tritium and noble gases, exceeds 2.5 curies during any calendar quarter and describe the proposed program of action to reduce suct) release rates.

2-7 LIMITING CONDITIONS FOR OPERATION 2.0 MONITORING REQUIREMENTS Bases (Cont'd)

This report must be filed within 30 days following the calendar quarter in which the 2.5 curies release occurred.

Specification f. requires that the dose to offsite personnel be limited to the design objectives of Appendix I of 10 CFR Part 50. This will assure the dose received by the public during the cleanup is equivalent to or less than that from a normal operating reactor. The limits also assure that the environ-mental impacts are consistent with those assessed in the PEIS.

2.1.2 Gaseous Effluents Applicability Applies to the controlled release of radioactive gases from TMI Unit No. 2.

Objective Objective To define the limits and conditions To ensure that radioactive gaseous for the controlled release of radio-releases from the facility are active gaseous effluents to the within the limits of specifications.

environs to ensure that these releases are as low as practicable.

These releases should not result in radiation exposures in offsite areas greater than a few percent of background exposures. The instant-aneous release rate for all effluent discharges should be within the limits specified in 10 CFR 20.

To assure that the release of radio-active gases to offsite areas meet the as low as practicable concept, the following objectives apply:

a.

The release rate of gaseous effluents shall not' result in doses to the public exceeding the design objectives of Appendix I to 10 CFR Part 50.

2-8 LIMITING CONDITIONS FOR OPERATION 2.0 MONITORING REQUIREMENTS Specification Specification a.

The instantaneous release rate of During release of radioactive gross gaseous activity except for gaseous wastes, the following halogens and particulates with conditions shall be met; half-lives longer than eight days shall not exceed:

A.

During release of gaseous waste Qi l.5 x 105 m3 from the waste gas decay tanks, the following conditions shall be met:

(MPC)1 sec 1.

Waste gas discharge monitor where Qi is the release rate in (Unit 2: WDG-R-1480) or similar pCi/sec for isotope i, and MPCi device, shall be operable.

3 (pCi/M ) is the maximum permissible concentration of isotope 2.

Auxiliary and Fuel Handling and defined in Appendix B, Table II, Building and Unit Exhaust Vent Column 1. 10 CFR 20.

exhaust gas, iodine and particulate monitor (Unit 2: W-R-219) on b.

The instantaneous release rate of similar device, shall be operable.

particulates with half-lives greater than eight days, released to the env-3.

The waste gas decay tank dis-irons as part of the airborne charge valves (Unit 2: WDG-V-30A or effluents, shall not exceed 0.3 308) shall be operable.

p C1/sec.

4.

The waste gas decay tank dis-c.

The release rate of gross gaseous charge valves (Unit 2: WDG-V-30A or activity shall not exceed:

308) shall be closed on receipt of any one of the following conditions:

3

[(g 1 2.4x1@

)i ec a.

A high radiation signal from the waste gas discharge monitor (Unit 2:

when averaged over any calendar WDG-R-1480).

quarter.

d.

The release rate of particulates b.

A high radia' tion signal from the l

with half-lives greater than eight Auxiliary and Fuel Building exhaust days, shall not exceed: 0.024 monitor (Unit 2: HP-R-219).

I pCi/sec. when averaged over any calendar quarter.

c.

A high flow signal from the Waste Gas Decay Tank discharge flow l

e.

Radioactive gaseous wastes transmitter (Unit 2: WDG-FT-3923).

collected in the gas decay tanks shall be held up to a minimum of 45 d.

Observation of loss of flow days, except when the release rate through the Unit vent.

shall not exceed:

B.

During purge of the Reactor 1.

Qi 3 x 103 m3 Building, the following conditions (MPC)1 sec shall M med l

(noble gases) or l

2.

0.003 pC1/sec (particulates with half-lives greater than 8 days)

2-9 LIMITING CO E TIONS FOR OPERATION 2.0 MONITORING REQUIREMENTS Specification (Cont'd)

Specification (Cont'd) i f.

Radioactive gas and particulates 1.

The Reactor Building Purge purged from'the reactor building Exhaust Monitor (Unit 2: HP-R-225 shall be filtered through the high or HP-R-226 and HP-R-219) or similar efficiency particulate air filters.

device shall be operable.

g.

The maximum activity to be con-2.

The Purge Exhaust Valves (Unit tained in one gas decay tank shall 2: D5129 A/D and D5129 B/C) shall be not exceed 8800 curies (equivalent to operable.

Xe-133).

3.

The valves (Unit 2: D5129 A/D l

h.

When the release rate of radio-and D5129 B/C) shall be interlocked active materials in gaseous wastes, to recirculate on receipt of a high l

averaged over a calendar quarter radiation signal from their

exceeds, respective Reactor Building Exhaust Monitors (Unit 2: HP-R-225 and

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Qi 6 x 103 m3 C.

The. flow rate for radioactive (MPC)i

- (noble gas)see effluent streams and the Auxiliary or and Fuel Handling Building and the Reactor Building, shall be monitored 0.006 uCi/sec (particulates and recorded. Gaseous effluents with half-lives from the Waste Gas Decay Tanks and greater than 8 the Reactor Building Purge Exhaust days) shall be continuously monitored and recorded.

the licensee shall notify the NRC within 30 days, identifying the D.

Radioactive gaseous waste causes and describing the proposed sampling and activity analysis shall program of action to reduce such be performed in accordance with release rates.

Table 2.3-2 1.

The air dose due to noble gases E.

The waste gas decay tank in gaseous effluents shall be less effluent monitor (Unit 2:

than or eoual to 10 mrad for gamma WDG-R-1480) shall be tested using radiation and less than or eoual to the installed check source or 20 mrad for beta radiation for the eauivalent prior to any release of calendar year.

radioactive gas from a holdup tank i

and shall be calibrated quarterly J. The dose for radionuclides (other using a referenced calibration than noble gaseous effluents) shall source in a controlled reproducible be less than or equal to 15 mrem to geometry.

any organ for the calendar year.

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2-10 LIMITING CONDITIONS FOR OPERATION 2.0 MONITORING REQUIREMENTS Specification (Cont'd)

F.

During power operation, the con-

^

densor vacuum pump discharge shall

.be continuously monitored for gross gaseous activity. The monitor shall not be inoperable for more than a i

week. Whenever this monitor is in-operable, a grab semple shall be taken daily and analyzed for gross radioactivity. (s y).

G.

Facility records shall be main-tained of radioactive concentration, release ratio and volume of each batch of gaseous effluents released and the length of time over which release occurred. Estimates of the error associated with each reported value should be included in facility records.

H.

At least annually, automatic initiation and closure of the Waste Gas Decay Tank Discharge valve on alarm of (Unit 2: WDG-R-1480) shall be verified.

I.

The Unit Vent monitors for TMI-2 (HP-R-219, HP-R-219A, HP-R-225, HP-R-226), respectively, shall be calibrated at least every eighteen months by means of a known radioactive source. These detectors shall have an instrument channel test at least monthly, and a sensor i

check at least daily, to verify that the read-out device is indicating as expected.

Bases The specified levels provide reasonable assurance that the Specifications A. through I.,

above, resulting annual exposure rate from require that suitable eouipment to noble gases at any location at the monitor the radioactive gaseous site boundary will not exceed 10 releases are operating during any millirems per year. At the same period these releases are taking place.

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2-10a GASEOUS EFFLUENTS 2.1. 2. J The release rate of radioactive materials, other than noble gases, in gaseous effluents shall be deteImined to be within the limits calculated in accordance with this specification by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 2.1-1.

BASES 2.1.2.J This specification is provided to ensure that the dose at any time at the site boundary from gaseous effluents from TMI-2 will be within the annual dose limits of 10 TR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1.

These limits provide reasonable assurance that 6

radioactive material disdiarged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix 8, Table II of 10 WR Part 20 (10 7R Part 20.106(b)).

For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem /yr to the total body or to less than or equal to 3000 mrem /yr to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above bad < ground to an infant via the cow-milk-infant pathway to less than or equal to 1500 mrem /yr for the nearest cow to the plant.

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2-10b TABLE 2.1-1 RADI0 ACTIVE GASEOUS WASTE SAMPLING Af0 ANALYSIS PROGRAM i

l i

l I

I l

l l Minimum

-l l Lower Limit of I I

Gaseous Release l Sampling l Analysis l Type of Activity l Detection (LLD) l I

Type l Frequency l Frequency l Analysis I

(gCi/ml)a l

l 1

I I

I I

l 1

1 I

I I

I I

I I

l EPICOR-II Ventilation l

Mb i

M l Principal Gamma EmitterscI 1x10-4 l

l 1

1 I

I I

I I Grab Sanple l l

l l

I I

I I

I I

I I

I I

H-3 1

1x10-6 1

I I

1.

I I

I I

I I

-1 I

I 9

4 e

2-lDe TABLE 2.1-1 (Continued)

TABLE NOTATION a.

The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 sh LLD -

E. V. 2.22. Y. exp (-Aat)

Where LLD is the lower limit of detection as defined above (as picoeurie per unit mass or volume).

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute).

E is the counting efficiency (as counts per transformation),

V is the sample size (in units of mass or volume),

2.22 is the number of transformations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, nor environmental samples),

The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank L

samples (as appropriate) rather than on an unverified theoretically predicted variance.

In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and at shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be with + one FWHM (Full-Width-at-Half-Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide.

l l

I

2-10d TABLE 2.1-1 (Continued)

TABLE NOTATION b.

Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the Chemical Cleaning Building.

c.

The principal gamma emitters for which the LLO specification applies exclusively are the following radionuclides: Mn-54, Fe-59, C0-58, 00-60, Zn-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 for the analyses shall be reported as "less than" the nuclide's LLD and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations.

2-11

' TABLE 2.3-2 Radioactive Gaseous Waste Sampling and Analysis (5)

SamDie Type Samplina Freauency Type of Activity Analysis Detectable Concentration (1)

Waste Gas Oecay Tank Release Gas Each Tank H-3 10-6 uC1/cc Release Individual Gamma Emitters 10-4 uCi/cc (2)

^

Reactor Buildino Purae Releases Gas Eech Purge H-3 10-6 uC1/cc 4

Individual Gama Emitters 10-4 uCi/cc (2)

]

Condenser Vacuum Pump Releases Gas Monthly H-3 10-6 uC1/cc Monthly (3)

Individual Gamma Emitters 10-4 uCi/cc (2) i Unit Exhaust Vent Release Points Gas Monthly (4)

H-3

'10-6 uCi/cc Individual Gamma Emitters 10-4 uCi/cc (2)

Charcoal Weekly (6)

I-131, 1-133, I-135 10-12uCi/cc Particulates Weekly Individual Gamma Emitters 10-10uCi/cc (2)

Monthly Composite Sr-89, Sr-90 10-IluC1/cc Monthly Composite Gross Alpha Emitters 10-IluCi/cc 11)

The above detectability limits are based on technical feasibility and on the potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported.

2-12 (2)

For certain mixtures of gamma emitters, it may be possible to measure radionuclides at levels near their sensitivity limits when other nuclides are present in the sample at much higher levels. Under these circumstances, it will be more appropriate to calculate the levels of such radionuclides using observed ratios in the gaseous component in the reactor coolant for those radionuclides which are measurable.

(3)

Analysis shall also be performed following each refueling period, start-up or similar operational occurrence which could alter the mixture of radionuclides.

(4)

Sampled during periods when no waste gas decay tank release or reactor building purge is in progress.

(5)

Deviations from the sampling and analysis regime will be noted in the report specified in Section 5.6.1.

(6)

Sample not required for Unit exhaust vent (TMI-2). However, the charcoal in the charcoal sampler should be replaced on a weekly basis although a weekly analysis is not reouired.

O

2-13 LIMITING CONDITIONS FOR OPERATION 2.O MONITORING REQUIREENTS Bases (Cont'd)

Bases (Cont'd) time, these specifications permit the The surveillance requirements given flexibility of operation, compatible under the remaining Specifications with consideration of health and above, provide assurance that safety, to assure that the public is radioactive gaseous effluents from provided a dependable source of power the station are properly controlled under unusual operating conditions, and monitored over the life of the which may temporarily result in station. These surveillance hicjier than the desigi objective requirements provide the data for levels, but still within the the licensee and the Commission to concentration limits specified 10 CFR evaluate the station's performance 20.

It is expected that using this relative to rad.ioactive gaseous operational flexibility under unusual wastes released to the environment.

operating conditions, and by exerting every effort to keep levels of Reports on the quantities of radio-radioactive material in gaseous active materials released in gaseous wastes as low as practicable, the effluents shall be furnished to the annual releases will not exceed a Commission on the basis of Section small fraction of the annual 5.6.1 of these Technical Specifica-concentration limits specified in 10 tions. On the basis of such report TR 20 and will not result in doses and any additional information the which exceed the desigi objectives of Commission raay obtain from the Appendix I to 10 CFR 50, which were licensee or others, the Commission endorsed as limits for the cleanup of may from time to time recpire the TMI-2 by the NRC's statement of licensee to take such action as the Policy of April 27, 1981.

Commission deems appropriate.

These efforts should include con-sideration of meteorological conditions during releases.

The annual objectives have been developed taking into account a i

l combination of system variables in-cluding fuel failures, primary system leakage, primary to secondary system leakage, and the performance of radionuclide removal mechanisms.

I-131 is not @ecifically monitored because it has decayed to less than i

detectable activity since the March 28, 1979, accident.

Specification a. above, requires the licensee to limit the concentration of noble gases from TMI-2 to levels specified in 10 ER 20, Appendix B, for unrestricted areas. Based on a l

2-14' LIMITING COPOITIONS FOR OPERATION 2.0 MONITORING REQUIREMENTS Bases (Cont'd)

'X/Q of 6.7 x 10-6 sec/m3, this specification provides assurance that no member of the general public would be exposed to radioactive materials in excess of limits specified in the Commission's rules and regulations.-

Specification b. above, requires the licensee to limit the concentration of particulates with half-lives greater than eight days, released from TMI-2 to unrestricted areas to levels such that no individual will receive more than 500 mrem /yr to the total body or 3000 mrem /yr to the skin. The absence of iodine insures that the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway is less than or equal to 1500 mrem /yr.

A grazing period of 6 months has been applied to all rsdionuclides in particulate form with half-lives greater.than 8 days, to allow for the milk exposure pathway.

The release rate is determined by using the methodology of Regulatory Guide I.109 (Rev. 1) and a relative l

depgsitgonfactor(D/Q)'of2.1x 10-o m.

The D/Q of 2.1 x 10-8 m-2 was calculated for the nearest cow located 1.2 miles SE of the station, using on-site i

meteorological data.

Specifications c. and d. above, establish an upper limit for the release of gaseous activity at 16% of instantaneous release limit of noble

[

gases and at eight percent of the release rate of particulates with half-lives greater than 8 days, averaged _over any calendar quarter, l

.respectively. The intent of this l'

specification is to permit the licensee the flexibility of operation to assure that the public is provided l

a dependable source of power under e

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2-15 LIMITING CONDITIONS FOR OPERATION 2.0 MONITORING REQUIRE >ENTS Bases (Cont'd) unusual operating conditions which may temporarily result in higher releases than the objectives.

Specification e. above, requires a 45 day hold @ time for radioactive gaseous wastes collected in the gas decay tanks to assuIe decay of most radionuclides. The whole body dose from noble gases at the site boundary is expected to be less than 10 mreWyr (primarily from Kr-85). The whole body dose from particulates at the nearest farm is expected to be less than 5 mrem /yr.

Specification f. above, limits the radioactivity that may be released to the environment to "as low as prac-ticable."

Specification g. above, limits the maximum of fsite dose to well below the limits of 10 Cfr 100, postulating that the rupture of a Waste Gas Decay Tank holding the maximum activity releases all of the contents to the atmosphere.

In addition to the limiting condi-tions for operation listed under a, b and c above, the reporting require-ments of Specification H. delineate l

I that the licensee shall identify the cause whenever the radioactive gaseous release rate exceeds 4 percent of Specification a. or 2 percent of Specification b. above, averaged over a calendar quarter, and describe the proposed program of action to reduce such release rates.

The report must be filed within 30 days following the calendar quarter j

in which more than twice the design release rate occurred.

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2-15a 2.1.3 RADI0 ACTIVE GASEDUS EFFLLENT MONITORING INSTRLAENTATION LIMITING CONDITION FOR OPERATION The radioactive gaseous effluent monitoring instrumentation channels shown in Table 2.1-3a shall be OERABLE.

APPLICABILITY: As shown in Table 2.1-3a.

Action:

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERAELE, take the ACTION shown in Table 2.1-3a.

SURVEILLANCE REQUIREMENTS Eadi radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERAELE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 2.1-3b (per occupational exposure considerations and detector sensitivity in ambient radiation areas).

BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criterion 64 of Appendix A to 10 CFR Part 50.

2-15b TABLE 2.1-3a RADIOACTIVE GASEDUS EFFLUENT MONITORING INSTRUENTATION MINIMM CHANELS INSTRlNENT OPERABLE APPLICABILITY ACTION

10. EPICOR-II VENTILATION SYSTEM a.

Noble Gas Activity Monitor 1

37 b.

Deleted c.

Particulate Sampler 1

41 d.

Flow Rate 2nitor 1

36 e.

Sampler Flow Rate Monitor 1

36 TABLE NOTATION

• At all times.

ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 37 - With the number of channels OPERABLE less than required by the l

Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are l

taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 41 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 2.1-1.

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1 2-15c TABLE 2.1-3b RADI0 ACTIVE GASEDUS EFFLUENT MONITDRING INSTRlNENTATION SURVEILLANCE EQUIREMENTS CHANNEL CHANNEL SOURCE CHANEL FUFCTIONAL INSTRLMENT CHECK CECK CALIBRATION TEST

10. EPICOR-II VENTILATION SYSTEM

a. Noble Gas Activity Monitor D M

R(3)

Q(2)

b. Deleted I

c. Particulate Sampler W

N.A.

N.A.

N.A.

d. Flow Rate Monitor D

N.A.

SA SA

e. Sampler Flow Rate Monitor D

N.A.

SA SA TABLE NOTATION (2) CHANNEL FUfCTION TEST shall also demonstrate that control room alarm.

annunication occurs if any of the following conditions exist.

1.

Instrument indicates measured levels above the alarm setpoint.

2.

Circuit failure (alarm function only).

3.

Instrument indicates a downside failure (alarm function only).

4.

Instrument controls not set in operate mode or the switch position administrative 1y monitored and controlled.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with tes. These standards shall permit calibrating the system over its intended range 4

of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

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2-16 LIMITING C0tOITIONS FOR OPERATION 2.0 MONITORING REQUIREMENTS References (1) Meteorology and Atomic Energy, pp. 204 (2) Meteorology and Atomic Energy, pp. 112 i

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