Text

Forwards Proposed Tech Specs Changes Revising App a & B Re Radiological Effluents.Disputes NRC Position That Changes Require Submission of Class III Fees
	ML18024A874
Person / Time
Site:	Browns Ferry
Issue date:	06/29/1979
From:	Gilleland J; TENNESSEE VALLEY AUTHORITY
To:	Harold Denton; Office of Nuclear Reactor Regulation
Shared Package
ML18024A875	List: ML18024A874; ML19246A800;
References
	TVA BFNP TS 124, TVA-BFNP-TS-124, NUDOCS 7907060354
	Download: ML18024A874 (326)
	v • d • e

ENCLOSURE 1 BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (DOCKET NOS ~ 50 259 j 50 260~ AND 50 296)

PROPOSED CHANGES TO APPENDIX A TECHNICAL SPECIFICATIONS BAIRD/a'lib

~

R>.-

Q-Q~

Weaeaem+

H i

b 0

UNIT 1 1.0 DETl!flT?OPS (Cont 'd)

10. ~Lo ic - h logic is aa arranger~nt of relays, contacts, and 'other components that producas a decision outout.

(a) ~gnicicrin A logic rhnc rccnivc oignclc iron channalo aag produces docieion outputs to the <<ctuation logic,.

(b) Actuation -. A logic that receives signals (either frotg initiation logic or channels) and produces dociaion outputs to accoagplish a protoctive action.

1'1. Channel Calibration Shall be the adjustment, as necessary, of the channel output such that it. responds with necessary range and accuracy to known values of the parameters which the channel monitors. The channel calibration shall encompass the entire channel .including alarm and/or trip functions and shall include the channel functional test. The channel cali-bration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

Non-calibratable components shall be excluded from this require-ment, but will be included in channel functional test and source check.

12. Channel Functional Test Shall be

a. Analog Channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b. Bistable channels the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

13. Source Check Shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive sources or multiple of sources.

1.0 DEFINITIONS (Cont'd)

Fuactianal Teste - A functional test ie the manual operation or functions vithin design tolerancoe (e.g., the nanual start of a corn spray puay to verify that it runs and that it junpa the roquirod voluao of vator).

X. Shutdown <<The reactor is in a sbutdovn condition vhan the r actor mode avitch ia in tha shutdovn aocLa position'nd no cora alteratians are boing performed.

Y En ineorad Sate uard - An engineered safeguard is a sa ety systno thn actions o vhich are ossantial to a safety action raguired in response to accidents.

g ~ulative Doubt.&e - The ~~ tive doMnthna for those safety oocaponents snd systole uhoea downtime ls linLited-to 7 consacutiva days prior to requiring reaator shutdown shall be limited to any 7 days in a ocnsacutive 30 day pariad.

AA. Solidification Shall be the'conversion of radioactive wastes to conform to the license requirement of the receiving burial ground.'B.

Offsite Dose Calculation Manual (ODCH) Shall be a manual describing the environmental monitoring program and the methodology and parameters used in the calculation of release rate limits and off-site doses due to radioactive gaseous and liquid effluents..

P CC. Unrestricted Area - All area beyond the site boundary access to which is not controlled for protection of individuals from exposure to radiation and radioactive materials.

7a

TABLE I. 1 SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours.

At least once per 24 hours.

At least once per 7 days.

At least once per 31 days.

~

. At least'nce per 92 days.

SA At least once per 6 months.

At least'once per 18 months.

S/U Prior to each reactor startup.

N.A. -Not applicable.

LIHIYING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS

.3.2.K Radioactive Gaseous Effluent 4.2.K Radioactive Gaseous Effluent Monitorin Instrumentation Monitorin Instrumentation

1. The radioactive 'gaseous 1. Each of .the radioactive effluent monitoring instru- gaseous effluent monitoring ments listed in table 3.2.K instruments shall be demon-

-hall be operable at all strated operable by perfor-times with their alarm/trip mance of tests in accordance setpoints set to ensure that with table 4.2.K.

the limits of specification 1 3.8.B.1 are not exceeded.

2. The action required when the number of operable channels is less than the Minimum Channels Operable requirement is specified in the notes for table 3.2.K.

54a

TABLE 3.2.K RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument Parameter Action

l. Stack Noble Gas (a) Release Rate A/C Activity Monitor Measurement

b. Iodine Installed B

.Cartridge

c. Particulate NA Installed B filter

2. Reactor /Turbine Building Ventilation

a. Noble Gas Release Rate A/C Activity Monitor Measurement

b. Iodine Monitor Release B/C Rate'easurement

c. Particulate Monitor Release Rate B/C Measurement

3. Turbine Building Exhaust

a. Noble Gas Release Rate A/C Activity Monitor Measurement

b. Iodine Monitor Release Rate B/C Measurement

c. Particulate Monitor Release Rate B/C Measurement,

3.2.K (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels a Instrument Patametet Action

4. Rad~aste Building Ventilation Noble Gas (l) Release Rate 'A/C.

Activity Monitor b.. Iodine Monitor (l) Release Rate B/C Measurement

c. Particulate Monitor (l) Release. Rate B/C Measurement

NOTES FOR TABLE 3.2.K

During releases via this pathway.

ACTION A 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 7 days provided a tem-porary monitoring system is installed oi grab samples are taken and analyzed at least once every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

I ACTION B 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 28 days, provided samples are continuously collected with auxiliary sampling equipment for periods on the order of seven (7) days and analyzed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the end of the sampling period.

ACTION C A monitoring system may be out of service for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for functional testing, calibration, or repair without providing temporary monitor or initiating grab sampling.

84c

TABLE 4.2.K-MONITORING INSTRUMENTATION SURVEILLANCE RADIOACTIVE GASEOUS EFFLUENTREQUIREMENTS Channel Modes In Which Instrument Source Channel Functional Surveillance Instrument Check Check Calibzatica Test Re uired

1. Stack a; Noble Gas Q(1) M(2)

Activity Monitor

2. Reactor/Turbine Ventilation

'uilding

a. Noble Gas M Q(1) M(2)

Activity Monitor

b. Iodine Monitor Q(1) M(2) a

c. Particulate Monitor M Q(1) M(2)

3. Turbine Building Exhaust Noble Gas M -

Q(1) M(2)

Activity Monitor

b. Iodine Monitor M --Q(1) M(2)

c. Particulate Monitor Q(1) M(2)

4. Raduaste Building Ventilation

a. Noble Gas D Q(1) M(2)

Activity Monitor

b. Iodine Monitor D M Q(1) M(2)

c. Particulate Monitor D M Q(l) M(2)

NOTES FOR TABLE 4.2.K

During releases via this pathway.

The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Bureau of standards radiation measurement system) radioactive source (s) positioned in a reproducible geometry with respect to the sensor. I (2) The CHANNEL FVNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following'conditions exist:

l. Instrument indicates measured levels above the alarm/trip setpoint.

2. Instrument indicates an inoperable downscale failure. "

110b

3.2 BASCS For each parameter n~nitored, as listed in Table 3.2.F, there are two channels of instrumentation except as noted. Gy comparing readings between the two channels, a near continuous surveillance of instrument performance is available. Any deviation in readings vill initiate an early recalibra-tion, thereby maintaining the quality of the instrument readings.

Instrumentation is provided for isolating the control room and initiating a pressurizing system that processes outside air before supplying it to the control room. An accident signal that isolates prinmry containment vill also automatically isolate the control room and initiate the emex'gency pressuriration system. In addition, there are radiation monitors in the normaL ventilation system that vill isolate the control room and initiate the emergency pressurization system. Activity required to cause automatic actuation ie about one mRem/hr.

Because of the constant surveillance and control exercised by TVA over the Tennessee Valley, flood levels of large mangitudes can be predicted in advance of their actual occurx'ence. In all cases, fulL advantage will be taken oE advance warning to take appzopriate action whenever reservoir levels above normal pool are predicted; however, the plant flood px'otection is always in place and does not depend in any way on advanced warning.

Therefore, during Elood conditions, the plant vill be permitted to operate until vater begins to x'un across the top of the pumping station at elevation 565. Seismically qualified,.redundant level switches each povcred,from a separate division of power are pr'ovided at thc pumping station to give main control room indication of this condition. At that tine an orderly shutdown oE the plant vill be initiated, although surges even to a depth of several feet over the pumping station deck vill rot cause the loss of the main con-denser circulating water pumps.

The operability of the meteorological Instrumentation ensures that suf ficient meteorological data is available for estimating potential radiation dose to the public as a x'esult of routine or accidental release oE radioactive materials to the atmosphere. This cap'ability is required to evaluate the need for initiatin'g protective measures to protect the health and safety of the public.

The operability of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features impnrtant to safety.

This capability is required to permit comparison of the measured response to that used in the design basis for Browns Ferry lluclear P'ant. The instrumentation provided is consistent with specific portions of the recommendations of Regulatory, Guide 1.12 "Instrumentation for Farthquakes."

The radioactive gaseous effluent instrumentation is'rovided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments will be calculated in accordance with plant approved p'rocedures to ensure that the alarm/trip vill occur prior to exceeding the limits of 10 CFR Part 20.

115

yl 4 2 HARES there is no true minimum. The curve docs have a definite knee,and very little reduction in system unavailability is achieved by testing at a shorter interval than computed by the equation for a single, channel.

The best test procedure of all those examined Is to perfectly stagger the teste. That is, if the test interval is four months, test one or the other channel every two months, This is shown in Curve No. 5.

The difference between Cases 4 and 5 is negligible. There may be other arguments, however, that more strongly support the perfectly staggered tests inc iud Ing rcduct fons in human error.

~

The conclusions to be drawn are these:

l, A l out'of n system may be treated the same as a single channel in terms of choosing a t'est interval; and 2, more than one channel should not be bypassed for testing at any one time.

The radiation monitors in the r'efueling arcs ventilation, duct which initiate building isolation and standby gas treatment operation are arranged in two l out of 2 logic systems. The bases given for the rod blocks apply here also and were used to arrive at the functional testing frequency. The off-gas post treatment monitors are connected in a 2 out of 2 logic arrangement.--Based on experience wI,th instruments of similar design,'a testing interval of once every throu months has been found adequate.

The automatic prcssure relief instrumentation ran be considered to bo a I out of 2 logic system and the discussion above applies also.

The criteria for ensuring the reliability and accuracy of the radioactive gaseous effluent instrumentation in listed in Table 4."2.K.

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REqUIREMENTS 3.8 RADIOACTIVE MATERIALS 4;8 RADIOACTIVE MATERIALS A licabilit Applies to the controlled release of 'Applies to the pe'riodic test and record radioactive liquids and gases from requirements and sampling and monitoring the facility. methods used for facility effluents.

~Ob ective ~0b ective To define the limits and conditions To ensure that radioactiv'e liquid for the release of radioactive and gaseous releases from the facility effluents to the environs to assure are maintained within the limits that any radioactive releases are specified by Specifications 3.8.A and as low as reasonably achieveable and 3.8.B.

within the limits of 10 CFR Part 20.

A. Li uid Effluents A. Li ui'd Effluents

1. The concentration of radio- 1. Facility records shall be active material released at maintained of radioactive any time from the site to concentrations and volume unrestricted areas (see before dilution of each Figure t.RA J shall be batch of liquid effluent limited to the concentrations released, and of the average "

specified in 10 CFR Part 20, dilution flow and length of Appendix B, Table II, Column time over which each discharge 2 for radionuclides other occurred.

than dissolved or entrained noble gases. For dissolved 2. Radioactive liquid waste or entrained noble gases, the sampling and activity analysis

'concentration shall be of each liquid waste batch to limited to 2E-4 uCgml total be discharged, shall be performed activity. prior to release in accordance with Table 4.8.A.

2. If the limits of 3.8.A.1 are exceeded, appropriate action shall be initiated to bring the release within limits.

Provide prompt notification to the NRC pursuant to Section 6.7.2.a.

\

3. The dose or dose commitment 3. The liquid effluent radiation to an individual from. radio- monitor shall be calibrated at active materials in liquid least quarterly by means of a effluents released from each known radioactive source(s). The unit to unrestricted areas monitor shall also have an (See Figure 4.S > 1 ) shall instrument channel functional be limited: test monthly and an instrument check daily.

281

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREZKNTS 3.8.A Li uid Effluents 4.8.A Li uid Effluents

'. During any calendar quarter to

<1.5 mrem to,the total body and to <5 mrem to any organ and,

b. During any calendar year to 3 mrem to the total body and~10 mrem to any organ..

4. If the limits specified in 3.8.A.3. The operation of the automatic a6b above are exceeded, prepare and isolation valves and discharge tank submit Special Report persuant to selection values shall be checked Section 6.7.3.C,2. annually.

5. The liquid radwaste system shall be 5. 'he ac'curacy of the radwaste maintained and operated to process effluent flow rate monitor shall liquid radwaste when it appears be checked at least monthly.

during quarterly operation that the releases to unrestricted areas (see "Figure W.F A.l ) when averaged over 31 days would exceed 0.06 mrem to the total body and 0.21 mrem to any organ.

6. During a quarter if radioactive with-, 6. Cummulative quarterly and yearly liquid waste must be discharded dose contributions from liquid out treatment after the limits effluents shall be determined as specified in 3.8.A.5 above are ex- 'pecified in plant approved pro-ceeded, prepare and submit the cedures at least on'e every 31. days.

Special Report pursuant to Section 6.7.3.C.3.

7. During 'release of radioactive wastes 7. Doses due to liquid releases from the radwaste processing system, to unrestricted areas shall be the following conditions shall be met: projected at least once per 31 days.

a. Liquid waste activity and flow rate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge valve before exceeding the limits specified in 3.8.A.1. above. If this requirement cannot be met, continued release of liquid effluents shal'.:~c permitted only during the suc<<is'Ing 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period, two inu;pendent samples o each tank shall be analyzed and two station personnel shall indop .ndently check valving before 'the discharge.

282

LIMITING CONDITIONS FOR OPERATION ~

. SURVEILLANCE REQUIREMENTS 3.8 RADIOACTIVE,MATERIALS 4.8 RADIOACTIVE MATERIALS B. Airborne Effluents B. Airborne Effluents "

l. The dose rate at any The gross B/ and time in the unre- particulate activity of stricted areas (see gaseous wastes released Figure 'PR8 I ) due to to the environment shall radioactivity released be monitored and recorded:

in gaseous effluents from the site shall be limited to the follow-ing values:

a. The dose rate a ~ .For effluent limit for noble streams having con-gases shall be tinuous monitoring

~500 mrem/yr to capability, the the total body activity and flow and ~ 3000 rate shall be mrem/yr to the monitored and skin, 'nd recorded to enable release rates of gross radioactivity to be determined on an hourly basis using instruments specified in Table 3.

b., The dose rate b. For effluent stream limit for all without continuous 2.K.'.

radioiodines for monitoring capa-all radioactive bility, the activit materials in shall be monitored particulate for and recorded and and for radio- the releases throuc nuclides other these streams shall than noble gases be controlled so with half lives that the release greater than 8 rates from all days shall be streams are within 1500 mrem/yr to the limits speci-any organ. fied in 3.8.B If the limits of 2. Radioactive gaseous waste 3.8.3.1: e exceeded, sampling and activity appropr a+a-corrective analysis shall be perform@

action shall be ini- in accordance with Table tiated to bring the 4.8.3.

releases within 'limits.

Provide prompt notifi-cation to the NRC pursuant to section 6.7.2.a.

283

'LIHITING CONDITIONS FOR OPERATION ~ . SURVEILLANCE REQUIREHENTS

3. The air <Osa in unre- 3. Cumulative quarterly and stricted areas (see yearly dose contributions Figure 4 > 8 l ) due to shall be determined a,s noble gases released specified in plant approve in gaseous effluents procedures at least once per unit shall be every 31 days.

limited to the follow-ing:

a. During any calendar quarter, to < 5 mrad for gamma radiation and ~ 10 mrad for beta radia-tion;

b. During any calendar year, to ~ 10 mrad for gamma radiation and ~

20 mrad for beta radiation.

4. If the calculated air the limits

4. Doses due releases to gaseous to unrestricted dose exceeds specified in 3.8.~ 3 F axeas shall be projected above, prepare and at least once per 31 days.

submit a special report pursuant to section 6.7.3. C.5

5. The dose 'to an indivi- 5. Samples. of of fgass dual from radioiodines, effluents shall be ana-radioactive materials lyzed at least weekly to in particulate form, determine the identity and radionuclides other and quantity of, the than noble gases with principal radionuclides half lives greater, than being released.

8 days in gaseous effluent released per unit to unrestricted areas (see Figure 4.> >3 ~

) shall be limited to the following:

a. During any c..lendar quarter to ~ 7.5 mrem;

b. During any calendar year to 15 mrem; 284

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE"REQUIREMENTS

6. If the calculated doses exceed the limits of 3.8.B.5 above, prepa're and submit a special re-port pursuant to section 6.7.3. C.4

7. During operation above 50% power the dis-charge of the S JAE must'e routed through the charcoal adsorbers when the projected

'gaseous effluent re-leases to unrestricted areas (see Figure 4 8; 8.

) when averaged over 31 days would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation.

8. With gaseous wastes being discharged for more than 31 days with-out, treatment and in excess of the limits of

3. 8.B . 7 above, prepare and submit a special report pursuant to section 6.7.3.C .3 285

LIHITIiVG CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8.C Radioactive Effluents - Dose 4.8.C Radioactive'ffluents Dose The dose or dose commitment to a real 1. Cumulative dose contributions individual from all uranium from liquid and gaseous sources is limited to ~ 25 mrem fuel'ycle effluents shall be determined to the total body or any organ (except in accordance with specifi-the thyroid, which is limited to ~ 75 cations 3.8.A. 3, 3.8.B.3, and mrem) over a period of 12 consecutive 3.8.B.5.

months.

2. With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits'f specification 3.8.A.3, 3.8.B.3, or 3.8.B.5, prepare and submit a Special Report to the Commission pursuant to specif ication

.6.7.3.C.6 and limit the subsequent releases such that the limits of 3.8.C.l are not exceeded.

D. Mechanical Vacuum Pum D. Mechanical Vacuum Pum

1. The mechanical vacuum pump shall At least once during each be capable of being automatically operating cycle verify automatic isolated and secured on a signal securing and isolation of the or high radioactivity in the mechanical vacuum pump.

I steam lines whenever the main steam isolation valves are open.

2. If the limits of 3.8.C.1 are not met, the, vacuum pump shall be isolated.

286

3 ~ 8 RADIOACTIVE MATERIALS 4~ 8 RADIOACTIVE MATERIALS Miscellaneous Radioactive ~ E Miscellaneous Radioactive Materials Sources Materials Sources

1. Source Leaka e Teat 1 ~ Surveillance R uirement

" Each sealed source Tests for leakage containing and/or contamination radioactive material shall be performed by in excess of those the licensee or by quantities of other persons byproduct material specifically listed in 10 CFR authorized by the 30.71 schedule B and Commission or an all other sources, agreement State, as including alpha follows:

emitters, in excess of 0.1 microcurie, a~ Each sealed shall be free of source, except 0.005 microcurie of atartup sources removable subject to core contamination. Each ~ flux, containing sealed source with radioactive removable material, other contamination in than Hydrogen 3, excess of the above with a half-life limit shall be greater than immediately withdrawn thirty days and from use and (a) in~any form either decontaminated other than,gas; and repaired, or (b) shall be tested disposed of for leakage with in'ccordance and/or Commis a ion contamination at regulations. intervals not to exceed six months. The leakage test be capable

~'hall of detecting the presence ot 0.005 microcurie of radioactive material on the teat sample.

286a

TABLE LX UID WASTE SAMPLING AND ANALYSIS PROGRAM 4.8.A'ADIOACTIVE LIQUID RELEASE SAMPLING MINIMUM ANALYSXS TYPE OF ACTIVITY LOWER LIMIT OF DETECTION TYPE FRE UENCY FRE UENCY ANALYSIS LLD uCi/ml Batch Waste Each Batch Each Batch Principal Gamma Releases I prior to release Emit;ters 4 5 E-7 One Batch Monthly Dissolved and per Month Entrained Gases 1 E-5 Monthly Tritium :1 E-5 Proportional Monthly Composite Gross a 1 E-7 (2)

P-32 1 E-6 Quarterly Sr-89 , Sr-90 5 E-8 Proportional Quarterly Composite Fe-55 1 E-6 (2) r

TABLE NOTATION TABLE 4.8.A A batch release is the discharge of liquid wastes of a discrete volume.

(2) A proportional composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant.

(3) For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radio-nuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the con-centrations of such radionuclides using observed ratios with those radionuclides which are measurable or the lower limit of. detection may be increased proportionally to the magnitude of the gamma yield (i.e.,

5 E-7/I where I is the photon abundance expressed as a decimal fraction),

but in no case shall the lower limit of detection as calculated in this manner be greater than 10X of the MPC value specified in 10 CFR Part 20, Appendix B, Table II, Column 2.

(4) The principal gamma emitters (those expected to account for ~95X of

'he total activity present:) for which the LLD specification will apply are exclusively the following radionuclides: Cr-51, Zn-65, Co-60, Cs-137, Zr-95, Nb-95, I-131, Na-24, Mn-54, Co-58, Ag-110m, Cs-134, I-133, Cu-64, Mo/Tc-99, and Fe-59 for liquid releases. This list does not mean that only these nuclides are to be detected and reported. Other nuclides which influence accounting for ~95X of the total activity, together with the above nuclides, shall also be identified and reported as being present.

Nuclides which are below the LLD for the analysis may not be reported as being present at the LLD Level for that nuclide. When unusual circum-stances result in LLD's higher than required the reasons shall be documented in the semi-annual effluent report.

287a

TABLE 4.8.B RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Gaseous Minimum of Detection Release Sampling Analysis Type of (LLD)

~TB Fre uenc Fre uenc Activit Anal sis (1)

'-3 A.Containment Each Purge Each Purge Principal Gamma Emitters (3)

Purge Grab Sample H-3 1E-6 B 1. Stack Principal Gamma Emitters (3) 1E-4

2. Building Vent- Grab Sample Monthly 1E-6 ilation

a. Reactor/Turbine

b. Turbine Exhaust

c. Radwaste C All Release Continuous Charcoal I-131 lE-12 Points listed Sample Weekly I-1-33 'E-10 ( )

in B. above Continuous Par ticula te Principal Gamma 'Emitters (3) lE-ll (2)

Sample Weekly Continuous Composite Gross 1E-ll Particulate Sample Monthly Continuous Composite Sr-89, Sr 90 lE-ll Particulate Sample quarterly

TABLE NOTATION 4.8.B (1) For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near their sensitivity limits 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 observed. ratios with those radionuclides which are measurable or the lower limit of detection may be increased proportionally to the magnitude of the gamma yield 1E-4/I where I is the photon abundance expressed as a decimal 'i.e.

fraction), but in no case shall the lower limit of detection as calculated in this manner be greater'han 10% of the MPC value specified in 10 CFR Part 20, Appendix B, Table II, Column 1.

(2) When samples are taken more often than that shown, the minimum detectable

. concentrations can be correspondingly higher.

(3) The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, M0-99, Cs-134, Cs-137, Ce-141, and Ce-144 for parciculate 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 should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the semi-annual effluent report. The principal gamma emitters ( those expected to account for a 95% of the activity present) for which the LLD specification will apply are exclusively the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, and Cs-137 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other nuclides which influence accounting for 95% of the total activity together with the above nuclides shall also be identified and reported. Nuclides which are below the LLD for the analyses may not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in the LLD's higher than required, the, reason shall be documented in the semi-annual effluent report.

288a

1

~ ~,

~~~ g~~~@ggyj~ l 3>> << ~

Restricted hree~

~ I I

I

/I I I SWITCIIVARO

"'I PARRlrVC I

I I TRAIISFORIIER TARO ly ly

-'3 Iw I i+ I I SERV TIIRCIIIE Q r I

/ OCOC OI.OC g OO SI33RACE AD AREAS OFPICE WASTE eCOC REACTOR SI.OC INTAEE PIIIIP>IIC Qo,pc> STATIOR

<<l>v 0'IACA'EWACE

<<. I3~yp+> .

~~@

TREATAIEN'T PCAVT 0 X~S', .">.'>3 <<Y iwgi >J. >i '> p '~%w<".A P-.+~ ><<<<*Ryiqgg33'(~i

3": ,... ::.i.

+4'>33

<<Aking@>>'IGURE

": Pw J<<>>g q + f .,ZP<5. <<> 8 3<<c 4>gP+>>><<A,P3 PP.: WWP~PPP 3>>

3>>>

~$

. ~

qAPcgg > 3 < <<. -3+PP+cg>T>>3 t JCC Vk<>> > 33>3>333 J3 i. i 3 '"'"~3<<4'"><<> i T>>&i <<<<3 fJKN58c4ifi 3>>l>A&m4WVK+~>>~%8%~~~ . 4~3-.

4.8.A.l Assumed Liquid Effluent Restricted Area 288b

388Z DCI CO QIM l

/ I

i. r r

J A

r

~ k

~ ~ JJJ 0 ~ I p'Q, r r err J

Or,rtA

~, JJ I g

J

3.8 BASES Radioactive waste release levels to unrestricted areas should be kept "as low as reasonably achievable" and are not to exceed the concentration limits specified in 10 CFR Part 20. At the same time, these specifications permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than design objectives but still within the con-centration limits.'specified in 10 CFR Part 20. It is expected that by using this operational flexibility under unusual operating conditions, and exerting every effort to keep levels of radioactive materials released

.as low as reasonably achievable, the annual releases will not exceed a small fraction of the annual average concentration limits specified in 10 CFR Part 20."

3.8.A LI UID EFFLUENTS Sp cification 3.8.A.1 is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestriqted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II. This limitation provides addi-tional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures within (1) the Section 11.A design objectives of Appendix I, 10 CFR Part 50, to an indi-vidual and (2) the limits of 10 CFR Part 20.106 (e) to the population. The concentration limit for noble gases is based upon the assumption that Xc-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in Xnternational Commission on Radiological Protection (KRP )

Publication 2.

Specification 3;8.A.3 is provided to implement the requirements of Sections IX.A, III.A and IV.A of Appendix I, 10 CFR Part.50. The Limiting Condition for Operation implements the guides sht forth in Section 11.A of Appendix I.

Specification 3.8.A.4 provides the required operating flexibility and at the same time implement the guides set forth in Section .IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable".

Also, for fresh water sites with drinking, water supplies which can be potentially affected by plant Operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in section IXI.A of Appendix X that conformance with 289

3.8.A LIQUID EFFLUENTS (cont'd) the guides of Appendix .I be shown by calculational procedures based on models and data such .that the actual exposure of an individual through appropriate pathways is unlikely to be substantially under-estimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1..109, "Calculation of Annual Doses to Man Erom Routine Releases of Reactor Effluents fox the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision October 1977'and Regulatory Guide 1.113, "Estimating Aquatic Dispexsion

. 0 f.Zffl

.. s" from Accidental and Routine Reactor Releases-~x-theWurpose uen ts~

'of Implementing-Appendix I," April 1977. NUREG-0133 provides'me t ho d s for o dose calculations:consistent with Regulatory Guides 1.109 and 1.113.

Specificatioa 3.8.A.5 requires that the appropriate. portions of the liquid radwaste treatment system be used when specified. This provides assurance that the releases of radioactive materials in-liiquz d eeffluents will be kept "as low as is reasonably achievable."

This specification implements the requirements of 10 CFR Part 50.3 a, General Design Cxiterion 60 of Appendix A to 10 CFR Part 50 and design

.objective Section 11.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appxopxiate portions of the liquid radwaste treatment system were. specified as a, suitable fraction of the guide set forth in Section 11.A of Appendix I, 10 Cfx Part 50, for liquid.

effluents.

Specification 3.8.A.6 requires submittal of a special repoxt if the

.limiting values of Specification 3.8.A.5 are exceeded and unexpecte Eailures of non-redundant radwaste processing equipment halt waste treatment.

SpeciEication 3.8.A.7 requires that suitable equipment,to control and monitor the releases of radioactive materials in'he liquid effluents are operating during any period when these releases are taking place.

3.8. B AXRBOKJE EF LUZiiTS Specification 3.8.B.1 is provided to ensure that the dose xate at any-time. at the exclusion boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table IX. These limits provide reasonable assurance that radioactive material discharged effluents will not result in the exposuxe of an individual in anin'aseous unrestricted area, either within or outside the exclusion area oundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)0. For individuals who may at times be within the exclusion area oundary, the occupancy oE the individual will be sufficiently low to compensate for anv increase in the atmospheric diffusion Eactox abo b ve that for the ex-elusion area boundary.

290

3. 8. B AIRBORNE EFFLUENTS (Cont 'd)

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 exclusion area boundary'o~ (500) mrem/ .

year to the total body or to ~ (3000) mrem/year to the skin. These, release rate limits also restrict, at all times. the corresponding.

thyroid dose rate above background to an infant via the cow-milk-,

infant pathway to ~ 1500 mrem/year for the nearest cow to the plant.

Specification 3.8.B.2 requires that appropriate, corrective action gs) be taken are exceeded.

to reduce gaseous effluent releases if the limits of 3,8.B.l r

Specification 3.8.B.5 is provided to implement the requirements of Section II.C, III.A, a'nd IV of Appendix I, 10 CFR Part 50. The limiting conditions for operation are the guides set forth in Section II.c of Appendix I.

Specification 3.8.B.6,provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable."

The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that confor-mance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual .

through appropriate pathways is unlikely to be substantially under-estimated. The ODCM calculational methods approved by NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, "Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision I, October 1977 and Regulatory Guide l.ill, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"

Revision 1, July 1977. These equations also"provide for determining the actual doeses based upon the historical average atmospheric conditions.

The release rate specifications for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man in the unrestricted area.

The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where. milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

Specification 3.8.B.6 requires that a special report be prepared and submitted to explain violations of the limiting doses contained in Specification 3.8.B.5.

290a

AIRBORNE EFFLUENTS Specification 3.8.B.7 requires that the offgas charcoal adsorber beds be used when specified to treat gaseous effluents prior to their release to the environment. This provides reasonable assurance that the .

releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appen-dix A to 10 CFR Part 50, and design objective Section IXD of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections XX.B and XX.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

Specification 3.8.B.8 requires that a special report be prepared and submitted to explain reasons for any failure to comply with Specification

'3.8.B.7.

Specification 3.8.B.3 is provided to implement the requirements of Sections II.B, IXI.A and XV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in

-Section IV.A of B of Appendix X.

Specification 3.8.B.4 provides the required operating flexibility and at the same time implement the guides set'orth in Section I'V.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is.

unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the'oses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents-in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.'he ODCM equations provided for determining the air doses at the exclusion area boundary will be based upon the historical average atmos-pheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. Specification 3.8.8.4 requires that a special report be prepared and submitted to explain violations of the limiting doese contained'n Specification 3.8.B.3.

3.8.D.4.8. D Mechanical Vacuum.Pum The purpose of isolating the mechanical vacuum pump line is to limit the release of activity from the main condenser. During an accident, fission products would be transported from the reactor through the main steam 'lines to the condenser. The fission product radioactivity would be sensed by the main steam line radioactivity monitors which initiate isolation.

291

4 ~ 8. A AND 4.8. B BASES The surveillance requirements given under Specification 4.8.A and 4.8.B provide assurance that liquid and gaseous wastes are properly controlled and monitored during any release of radio-active materials in the liquid and gaseous effluents. These surveillance requirements provide the data for the licensee and the Commi'ssion to evaluate the station's performance relative to radioactive wastes released to the environment. Reports on the -quantities of radioactive materials released i,n effluents shall be furnished to the Commission on the basis of Section 6 of these technical specifications. On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such actions as the Commission deems appropriate.

3.8.E and 4.8.E BASES The objective of this specification is to assure that leakage from byproduct, 'source, and special nuclear radioactive material sources does not exceed allowable limits.

291a

6 0 ADMIN I STRATI VE CONTROLS (b) Annual 0 erati Re ort A tabulation on an annual. 'oasis of the number of statiora, utility and other personnel (includinq contractors) receiving exposures greater than 100 mrem/yr and their associated man rem exposure according to work and job functions,'.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refuelinq.

The dose assignment to various duty functions may be e timate" Lased on pocket dosimeter, TLD, or film badge measurements. small exposure.'otallirg less than 20% of the individual total do e need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall oe assigned to specific major work functions.

C ~ i~>anthl O erati nc ne orta.o.utine reports or operating statistics and shutdown experience shall be submitted on a mont,hly basis to the Of fice, of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, washington, C.C. 20555, with a copy to the appropriate Regional Office, to be submitted no later than the tenth of each month following tne calendar month covered by the report. A narrative summary of operating experience s1mll be submitted in the above schedule.

Any changes to the Offsite Dose Calculation Manual of Specification 6.10 shall be submitted with the Monthly Operating Report within 90 days in which the change(s) was made effective.

350

Revised 1-10-78, 4~ 0 ADA I NI STRATI VLi COYiTROL'.

Radar olorr.ical Environmental Noni tori

1. TVA shall prepare a report cnt tied uEnviron=ental Radio-activity Levels"- Browas Ferry Nuclear .'ant - Annual Report."

Tne report shall cover the previous 12 months of operation and shall be submitted to the Director of the hTC Region II Of fice (with a copy to the Director, Office of Nuclear Reactor Regulation) with~m 120 days af tcr January 1 of each year.

The rcport format shown in Regulatory Guide 4.8 Q.tie 1 shall be used. The xeport shall include su~acies, interpretations, and evaluations of the results of the radiological enviroraental surveillance activities for the report period, including a comparison with preoperational studies and/or operational controls (as appropriate), and an assessment of the observed impacts of thc plant operation on thc environuent. 1f harmful ef fccts or evidence of irreversible 'damage arc detected by the monitoring, the licensee shall provide an an lysis of th problem and a proposed course of .action to alleviate the problcu.

2~ Results of all radiological cnvirozunental samples taken shall be summarired and tabulated on an annual basis. In the event that some results are not available within thc 120-day period, the report shall be subuitted noting and explaining the reason for the missing resu1ts. The missing data shall be submitted as soon as possible in a supplementary report.

2 ~ Reportable Occurrences Reportable occurrerrces, includ'ng corrective actions and measures to preven: reoccurr ~nce, shall be reported to the NRC. Supplemental repor.-ts ay be required to fully rr describe f inal resolution of occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.

351

6. 0 ADMINISTRATIVE CONTROLS (9) Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically considered in the, safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an un sa fe condition.

Note: This item is inten'ded to provide for reporting of potentially generic problems.

"(10) The concentration of radioactive material in liquid effluents released to unrestricted areas exceeds the concentrations specified in 10 CFR Part 20, Appendix 8, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.. Concentration of dissolged or entrained noble gases exceeds 2 xl0 Ci/ml total activity.

(ll) (a). The dose rate for noble gases equals or exceeds 500 mrem/yr to the total body or 3000 mrem/yr to the skin.'b).

The dose rate for all radioiodines, for all. radioactive "materials in particular form, and for radionuclides other than noble gases with half lives greater than 8 days exceeds 1500 mrem/yr to any organ.

354

6.0 ADMINISTRATIVE CONTROLS

b. Thirt -Dav written Reports. The reportable occurrences discussed below shall be tne subject of written reports to the Director of the appropriate Regional Office w'thin thirty days of occurrence of the event. The written report shall- include, as a rninimQm, a completed cooy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

(1) Reactor protection system or engineered safety feature instrument settings which are found to be less conservative tnan those established by the technical speci'ications but wh'ch do not pr even t the f u lfi liment of the 'unc". iona l requirements of a fected systems.

(2) Conditions leadi'ng to "operation in a degraded mode permitted by a limiting condi" ion for operation or plant shutdown required by a limiting condition for operation.

Note: Routine surveillance testing, instrument calibration, o preventat'e maintenance which equire system configurations as described in items 2.b. (1) and 2.b. (2) need not 'ce repor" ed evcect where test results themselves revea' degraded mo;!e as described above.

(3) Observed inadequacies in the'mplementation of administrative or orocedural conr.rois which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.

(rr) Abnormal. degradation of systems other than those specif ied in item 2. a (3) above designed to contain radioactive material re ulting from "the fission process.

Note: Sealed sources or calibrat,ion sources are not included under this .item. Leakage of valve packing or gaskets within the linrits for identified leakage set forth in technical specifications need not be reported under this i tern.

(5) An unplanned offsite release of 1) more than I curie of radioactive v>aterial. in 3iqrrid ef fluents, 2) more than 150 curies of noble gas in gaseous efiluents, or 3) more than 0.05 curies of radioiodine in gaseous effluents.

The report of an unplanned offsite release of radioactive material shall include the following information:

H

l. A description of the event and equipment involved.

2. Cause(s) for the unplanned release.

3. Actions taken to prevent recurrence.

4. Conseqrences of the unplanned release.

355

6. 0 ADMINISTRATIVE CONTROLS Anomalous Measurements -Radiolo ical Environmental Monitorin (1.) If> during any, 12-month report-period, a measured Level of radio-s'ctivity in any environmental mediuc> other than those associated arith gaseous radioiodine releases exceeds tca time" thc control station Value, a written notification vill be submitted vithin one veek advising the NRC of this cbndition.~ This notification should include an evaluation of any release conditions, environ-mental factors, or other aspects necessary to explain the anomalous result.

(2. If, during any 12-month report period, a measured level of radioactivity in any environmental medium other than those associated Mith gaseous radioiodine releases exceed" four times

,the control station value, a u::itten notification vill be submitted v'thin 30 day advis'ng the llRC oi t?>is condi ion.

This notification should inclu>le an cvzlua< Pen of any release conditions, environmental factors, or other aspec-s necessary to explain the anor~lous resul=.

If individual milk samples sh>o I-'31 concentrations of 10 picocurics per 1>> ter or greater, a plan sh:.11 be submitted vithin 10 day" advising the NRC of the proposed action to ensure the plant related annual doses vill be Mithin the desigu ob)ective of 15 mrea/yr/reactor to thc thyroid of any ind'vidual.

(., concentrations 4.) If mi.lk .ples collcc s ed ovc of 6.0 picocuries a ca.',>':i".>><ua'.r s: J average per lxtcr cr >re-.rcr, a plan shall be submitted uithin 30 day". adv. in. tnc N'iC o the proposed action to ensure thc plant-vela ec.'nnual doses Hll be Mithin the design ob)ective of 15>>>:cn/yr/reactor to of any individual. tbl-'hyroid

+In the case of a tentatively anomalous value for rodiostrontium a c on c 'l ~ ~i t0 ry reanalysis of the origin-l, a duplicate or a neo sample may be des':abl . In this ~

insta<<cc the results of th>> confir "tory analysis shel'~ co;.p >e> w cQ 1 esi time collsisten arith the analysl>>, and i. he higa vain ~ 'c:, > ~ ~ ~ ~ >

t';.e re,>nrt to the hRC shall be submit cd m.thin one week following this a'nalysts.

5.) If such levels as discussed in 6.7.2.c.3 and 6.7.2.c.4 can be definitely shovn to result from sources other than the Bro-n>> Ferry Nuclear Plant, the reporting action called for in ~.3(a)3 and 5.6.3(a)4 need not be taken. Justification for assigning high levels of radioactivity to sources other than the BroMns Ferry Nuclear Plant must be provided in the annual report.

355a

6. 0 ADMINISTRATIVE CONTROLS 6.7.3 Uni ue Re ortin Re uirements A. Radioactive Effluent Release Re ort, A report on the radioactive discharges 'released from the site during the previous 6 months'f operation shall be submitted to the Director of the Regional Office of Inspection and Enforcement within 60 days after January 1 and July 1, of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents released and solid waste shipped from the plant as delineated in Regulatory Guide l.'21, Revision 1, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B thereof.

The report shall include a summary of the meterological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1. 21, Revision 1, with data summarized on a quarterly basis following the format of Appendix B thereof. Calculated offsite ~

dose to humans resulting from the release of effluents and their subsequent. dispersion in the atmosphere shall be reported as recommended in Regulatory Guide 1.21, Revision 1. Doses to individuals outside the site boundary (UNRESTRICTED AREA) shall be calculated in accordance with the ODCM.

B. Source Tests Results of required leak tests performed on sources i the tests reveal the presence of 0.005 microcurie or more of removable contamination.

C. Special Reports (in writing to the Director of Regional Office of inspection and Enforcement).

1. 'eports on the following area" shall be submitted as noted:

a. Secondary Containment Leak Rate Testing (5) 4 ',C ~ wxthxn 90 days of completion oi each test.

b. Fatigue Usage 6.6 Annual Evaluation Opera ting Report C, Seismic I nstrumen tati on 3. 2 .J . 3 h i thin 10 Jays Inoperabi1i ty after 30 days of inoperabi1 i ty 356

6. 0 ADMINISTRATIVE CONTROLS

2. Prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding THE LIMIT(s) and defines the corrective action(s) to be taken to reduce the releases of radioactive material in liquid effluents during the remainder of the current calendar quarter and during the subsequent'hree calendar quarters so that the average dose or dose commitment to an individual from such'eleases 'during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include:

(1) the results of radiological analyses of the drinking water sources (if applicable), and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act. (Applicable only if drinking ~ater supply is taken from the receiving water body.) See item 6 below.

3~ Prepare and submit to the Commission within 30 days, a Special Report which includes the following information:

a. Identification of equipment of subsystems not OPERABLE and the reason for nonoperability.

b. Action(s) taken to restore the non operable equip-ment to OPERABLE status.

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

4, Prepare,and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and'efines the corrective actions to be taken to reduce the releases of radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose or dose commitment to an individual from such releases during these four calendar quarters is within 15 mrem to any organ. See item 6 below.

5. Prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduc>> rhe releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and duri~; Tie subsequent three calendar quarters so that the average dose during these four calendar quarters is within 10 mrad for gamma radiation and (20) mrad for beta, radiation.

See item 6 below.

356a

6.0 ADMINISTRATIVE CONTROLS

6. Prepare and submit to the Commission a Special Report which includes an analysis demonstrating that radiation exposures Lo all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard.

Otherwise obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard.'56b

UNIT 2 1.0 DE?IAITIOH9 (Cont 'd)

10. ~Lo ic - A logic io aa arrangement of relaygg, contacts, snd 'other components that producoo a decision outout.

7.

( ~) ~tntttattn A logic ttrat tccaivc cignala ttonchannalc ccg producos docioion outputs to the actuation logic,.

(b) Actuation , A logic that receives signals (either frau initiation logic or channels) and produces decision outputs to accomplish a protective action.

Channel Calibration Shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameters which the channel monitors. The channel calibration shall encompass the entire channel .including alarm and/or trip functions and shall include the channel functional test. The channel cali-bration may be .performed by any. series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

Non-calibratable components shall be excluded from this require-ment, but will be included in channel functional test and source check.

12. Channel Functional Test - Shall be

a. Analog Channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b. Bistable channels the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.,

13. Source Check - Shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive sources or multiple of sources.

l. 0 DEFINITIONS (Cont ')

- functional cert's the oanua1 operation or M,

ryunctional Tests A functions vithin daairn tolerancea (a.g., the ctanual start of a COre SFray puxap tO Verify that it rune and that it punpe the

~

roquirod volmae of vater).

X. Shutd~ - Zhs reactor 1s 1a s shutdovs cosdlttoc vhsr tho r actor

~a odo svltch 1s lc tho ahutdovs coda posttiso acd so cora altcratlocc are being perfozmedo En ineered Safe ua.d - An enginaerad safegusard is a sa ety systao the actions o vhLch ar ~ essential to a safety action rsguirod in response to accidents.

Oustulativo Dohdnt&e The ~>tive doMnt1mo fosr those safety ocdspenents snd systoos whoso doMntfno 'is limited to 7 consecutive days prior to requiring reaotor shutdnm shall be linitod to any 7 days & a oanaecutive 30 day period.

AA. Solidification Shall be the'conversion of radioactive wastes to conform to the license requirement of the receiving burial ground.'B.

Offsite Dose Calculation Manual (ODCM) Shall be a manual describing the environmental monitoring program and the methodology and parameters used in the calculation of release rate limits and off-site doses due to radioactive gaseous and liquid effluents..

CC. Unrestricted Area All area beyond the site boundary access to which is not contro11ed for protection of individuals from exposure to radiation and radioactive materials.

TABLE 1.1 SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours.

D At least once per 24 hours.

'W At least once per 7 days.

At least once per 31 days.

. At least once per 92 days.

SA At least once per 6 months.

At least'once per 1S months.

S/U Prior to each reactor startup.

N.A. Not applicable.

7b

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIRENENTS

.3.2.K Radioactive Gaseous Effluent 4.2.K Radioactive Gaseous Effluent Monitorin Instrumentation Monitorin Instrumentation

1. The radioactive gaseous 1. Each of .the radioactive effluent monitoring instru- gaseous effluent monitoring ments listed in table 3. 2.K instruments shall be demon-

-hall be operable at all strated operable by perfor-with their alarm/trip

'imes mance of tests in accordance setpoints set to ensure that with table 4.2.K.

the limits of specification 3.S.B.1 are not exceeded.

2. The action required when the number of operable channels is less than the Minimum Channels Operable requirement is specified in the notes for table 3.2.K.

54a

TABLE 3.2eK RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument Parameter Action

1. Stack Noble Gas Release Rate A/C

'Activity Monitor Measurement

b. Iodine Installed B

.Cartridge

c. Particulate Installed B filter

2. Reactor /Turbine Building Ventilation

a. Noble Gas Release Rate A/C Activity Monitor Measurement

b. Iodine Monitor Release B/C Rate'easurement

c. Particulate Monitor Release Rate B/C Measurement '.

Turbine Building Exhaust

a. Noble Gas Release Rate A/C Activity Monitor Measurement

b. Iodine Monitor Release Rate B/C Measurement

c. Particulate Monitor Release Rate B/C Measurement

3.2.K (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument Parameter Attica

4. Radwaste Building Ventilation Noble Gas (I) Release Rate Activity Monitor r

b. . Iodine Monitor (>) Release Rate B/C Measurement

c. Particulate Monitor (l) Release:Rate B/C Measurement

NOTES FOR TABLE 3.2.K

During releases via this pathway.

ACTION A With the number of channels OPERABLE less than required by the Minimup Channels Operable requirement, effluent releases via the affected pathway may continue for up to 7 days provided a tem-porary monitoring system is installed or grab samples are taken and analyzed at least once every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION B 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 28 days, provided samples are continuously collected with auxiliary sampling equipment for on the order of seven (7) day's and analyzed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

'eriods after the end of the sampling period.

ACTION C A monitoring system may be out of service for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for functional testing, calibration, or repair without providing temporary monitor or initiating grab sampling.

84c

TABLE 4.2.K RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREk!ENTS A

Channel Modes In Which Instrument Source Channel Functional Surveillance Instrument Check Check Calibration Test Re uired 1.. Stack 2.

a.

Reac Noble Gas Ac t ivity. Monitor tor/Turbine Building Ventilation

a. Noble Gas Activity Monitor D

'(1) Q(1)

M(2)

b. Iodine Monitor Q(1) M(2)

c. Particulate Monitor D M(2)

3. Turbine Building Exhaust

a. Noble Gas Q(1) M(2)

Activity Monitor b; Iodine Monitor D Q(1) M(2)

c. Particulate Monitor Q(1) M(2)

4. Radwaste Building Ventilation

a. Noble Gas Q(1) M(2)

Activity Monitor

b. Iodine Monitor Q(1) M(2)

c. Particulate Monitor Q(l) M(2)

NOTES FOR TABLE 4 ~ 2.K

+During releases via this pathway.

(1) The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Bureau of standards radiation measurement system) radioactive source (s) positioned in a reproducible geometry with respect to the sensor.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following'conditions exist:

l. Instrument indicates measured levels above the alarm/trip setpoint.

2. Instrument indicates an inoperable downscale failure.

110b

3. 2 8*SF%

For each p~rxmeter crnnicored, as listed in Table 3.2.F, there are two channels of instrumentation except as noted. Gy comparing readings between the tuo channels, a near continuous surveillance of instrument performance is available. Any deviation in readings will initiate an early recalibra-tion, thereby maintaining che quality of the instrument readings.

Instrumentation is pxovided fox'solating the control room and initiating a pressurizing system that processes outside air before supplying it to the control room. An a'ccident signal that isolates primary containment vill also automatically isolate the control room and initiate the emergency pressurization system. In addition, chere are radiation monitors in che normal ventilation system that vill isolate the'ontxol room and initiate the emergency pressurization system. Activity required to cause automatic actuacion is about one mRem/hr.

Because of the constant surveillance and control exercised by TVA over the Tennessee,Valley, flood levels of large mangitudes can be predicted in advance of cheir actual occurrence. In all cases, full advantage vill be taken of advance warning to take appropriate action vhenevar resexvoir levels above normal pool are predicted; hovever, the plant flood protection ie aluays in place and does not depend in any uay on advanced uarning.

Therefore, during flood conditions, the plant vill be permitted to operate until uatcr begins to run across the top of the pumping station at elevation 565. Seismically qualified,-redundanc level'witches each powered from a separate division of power are provided at thc pumping station to give main control room indication of this condition. At that time an orderly shu dovn ot the plant uill be initiated, although surges even to a de'pth of savcral feet over the pumping station deck vill rot cause the loss of the main con-denser circulating water pumps.

The operabilicy of the meteorological inscrumencacion ensures that suf.icient meteorological data is available for estimating potential radiation dose to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required co evaluate the need for initiatin'g protective measures to protect the health and safety of the public.

The operability of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features impnrtant to safety.

This capability is required to permit comparison of he measured response to that used in the design basis for Brovns Ferry f/uclear p'ant..he instrumentation provided is consistenc with spec'fic portions of the recommendations of Regulatory Guide 1.12 "Instrumentation for Farthquakes."

The radioactive gaseous effluenc instrumentation is provided .,

to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluencs. The alarm/trip setpoints for these instruments will be calculated in accordance with plant approved procedures to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.

, 115

4~2 Shgl S there is no true minimum. The curve does have a definite knee,and very little reduction in system unavailability is achieved by testing at a shorter interval than computed by the equation for a singLe channel.

The best test procedure of all those examined is to perfectly stagger the tests. That is, if the test interval is four months'est one or the other channel every tvo months, This is shovn in Curve No. 5.

The difference betveen Cases 4 and 5 is negligible. .There m<<y be other arguments, hovever, that more strongly support the perfectly staggered tests, including reductions in human error.

The conclusions to be dravn are these:

l. A 1 out of n system may be treated the same as a single channel in terms of choosing a test interval; and 2, more than one channel should not be bypassed for testing nt any one time.

'the radiation monitors in the refueling area ventilation duct vhich initiate building isolation snd standby gas treatment operation are arranged in tvo 1 out of 2 logic systems. The bases given for the rod blocks apply here also and vere used to arrive at the functional testing frequency. The off-gas post treatment monitors are connected in

<< 2 out of 2 logic arrangement. - -Based on experience vt,th instruments of simil<<r design,'a testing interval of once every three months hss been found adequate.

The automatic prcssure relief instrumentation ran be considered to bo a 1 out of 2 logic system and the discussion above applies <<lso.

The criteria for ensuring the reliability and accuracy of the radioactive gaseous effluent instrumentation in listed in Table 4.2.K.

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8 RADIOACTIVE MATERIALS 4;8 RADIOACTIVE MATERIALS Applies to the controlled release of 'Applies to the periodic test and record radioactive liquids and gases from requirements and sampling and monitoring the facility. methods used for facility effluents.

~Ot ecttve ~Ob'ecttve To define the limits and conditions To ensure that radioactive liquid for the release. of radioactive and gaseous releases from the facility effluents to the environs to assure are maintained within the limits that any radioactive releases are specified by Specifications 3.8.A and as low as reasonably achieveable and 3.8.B.

within the limits of 10 CFR Part 20.

S cification S ecification A. Li uid Effluents A. Li uid Effluents

l. The concentration of radio- ~

1. Facility records shall be maintained of radioactive active material released't any time from the site to concentrations and volume unrestricted areas (see before dilution of each Figure t.RA J shall be batch of liquid effluent limited to the concentrations released, and of the average specified in 10 CFR Part 20, dilution flow and length of Appendix B, Table II, Column time over which each discharge 2 for radionuclides other occurred.

than dissolved or 'entrained noble gases. For dissolved 2. Radioactive liquid waste or entrained noble gases, the sampling and activity analysis

'concentration shall be of each liquid waste batch to limited to 2E-4 pCgml total be discharged, shall be performed activity. prior to release in accordance with Table 4.8.A.

2. If the limits of 3.8.A.1 are exceeded, appropriate action shall be initiated to bring the release within limits.

Provide prompt notification to the NRC pursuant to Section 6.7.2.a.

3. The dose or dose commitment 3. The liquid effluent radiation to an individual from radio- monitor shall be calibrated at active materials in liquid least quarterly by means of a effluents released from each known radioactive source(s). The unit to unrestricted areas monitor shall also have an, (See Figure 4.<>.I ) shall instrument channel functional

'e limited: test monthly and an instrument check daily.

281

I LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8.A Li uid Effluents 4.8.A Li uid Effluents

a. During any calendar quarter to

<1.5 mrem to .the tota1 body and to <5 mrem to any organ and,

b. During any calendar year to 3

'mrem to the total body and~10 mrem to any organ.

4. If the limits specified in 3.8.A.3. The operation of the automatic a&b above are exceeded, prepare and isolation valves and discharge tank submit Special Report persuant to selection values shall be checked Section 6.7.3.C.2. annually.

5. The liquid radwaste system shall be 5. 'he ac'curacy of the radwaste maintained .and operated to process effluent flow rate monitor shall liquid radwaste when it appears be checked at least monthly.

during quarterly operation that the releases to unrestricted areas (see

~ .Figure 0-3'.l ) when averaged over 31 days would exceed 0.06 mrem to the total body and 0.21 mrem to any organ.

6. During a quarter if radioactive with-. 6. Cunnnulative quarterly and yearly dose contributions from liquid liquid waste must be discharded out treatment after the limits effluents shall be determined as specified in 3 '.A.5 above are ex- 'pecified in plant approved pro-ceeded, prepare and submit the cedures at least once every 31 days.

Special Report pursuant to Section 6.7.3.C.3.

7. During 'release of radioactive wastes Doses due to liquid releases from the radwaste processing system, to unrestricted areas shall be the following conditions shall be met: projected at least once per 31 days.

a. Liquid waste activity and flow rate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge valve before exceeding the limits specified in 3.8.A.1. above. If this requirement cannot be met, continued relea. e of liquid effluents shal'. be permitted only during the suer ~'n'g 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period, two independent samples o each tank shall be analyzed and discharge.'.

two station personnel shall independently check valving before'the 282

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8 RADIOACTIVE MATERIALS 4.8 RADIOACTIVE MATERIALS B. Airborne Effluents B. Airborne Effluents

l. The dose rate at any time in the unre-

1. The gross Bl ac<

particulate activity of stricted areas (see gaseous wastes released Figure %8".8 I ) due to to the environment shall radioactivity released be monitored and recorded:

in gaseous effluents from the site shall be limited to the follow-ing values:

a. The dose rate a. .For effluent limit for noble streams having con-gases shall be tinuous monitoring

~500 mrem/yr to capability, the the total body activity and flow and ~ 3000 rate shall be mrem/yr to the monitored and skin, and recorded to enable release rates of gross radioactivity to be determined on an hourly basis using instruments specified in Table 3.2.K;

b. The dose rate b. For effluent strearr limit for all without continuous radioiodines for monitoring capa-all radioactive bility, the activit materials in shall be monitored particulate fo and recorded and and for radio- the releases throuc nuclides other 'hese streams shall than noble gases be controlled so with half lives that the release greater than 8 rates from all days shall be streams are within 1500 mrem/yr to the limits speci-any organ. fied in 3.8.B

2. If the limits of 2. Radioactive gaseous waste sampling and activity 3.8.B. 1 ".re exceeded, appropr:~-corrective analysis shall be performs action "hall be ini- in accordance with Table tiated to bring the 4.8.B.

releases within 'limits.

Provide prompt notifi-cation to the NRC pursuant to section 6.7.2.a.

283

K LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

3. The air ~0<a in unre- 3. Cumulative quarterly and stricted areas (see yearly dose contributions Figure 4 > I> l ) due to shall be determined as noble gases released specified in plant approve in gaseous effluents procedures at least once per unit shall be every 31 days.

limited to the follow-ing:

a. During any calendar quarter, to ~ 5 mrad for gamma radiation and ~ 10 mrad for beta radia-tion;

b. During any calendar year, to ~ 10 mrad for gamma radiation and ~ "

20 mrad for beta radiation.

4. Xf the calculated air 4. Doses due to gaseous dose exceeds the limits releases to unrestricted specified in 3.8.> ~ ~

areas shall be projected above, prepare and at least, once per 31 days.

submit a special report pursuant to section 6.7.3.'C.S

5. The dose to an indivi- S. Samples. of offgass dual from radioiodines, effluents shall be ana-radioactive materials lyzed at least weekly to in particulate form, determine the identity and radionuclides other and quantity of the than noble gases with principal radionuclides half lives greater than being released.

8 days in gaseous effluent released per unit to unrestricted areas (see Figure 4 > >3 ~

) shall be limited to the, following:

a. Du.r-ing any c.'.lendar quarter to ~ 7.5 mrem;

b. During any calendar year to 15 mrem; 284

I LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

6. Xf the calculated doses exceed the limits of 3.8.8.5 above, prepare and submit a special re-port pursuant to section 6.7.3. C.4

7. During operation above 50% power the dis-charge of the SJAE must.'e routed through the charcoal adsorbers when the projected

'gaseous effluent re-leases to unrestricted areas (see Figure d.S; 8-l ) when averaged over 31 days would exceed 0.2 mrad for gamma radiation and 0. 4 mrad for beta radiation.

8. With gaseous wastes being discharged for more than 3l days with-out treatment and in excess of the limits of

3. 8.B . 7 above, prepare and submit a special report pursuant to section 6.7.3.C .3 285

LIHITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8.C Radioactive Effluents Dose 4.8.C Radioactive Effluents Dose The dose or dose commitmerit to a real 1. Cumulative dose contributions individual from all uranium from liquid and gaseous sources is limited to ~ 25 mrem fuel'ycle effluents shall be determined to the total body or any organ (except in accordance with specifi-the thyroid, which is limited to ~ 75 cations 3.8.A. 3, 3.8.B.3, and mrem) over a period. of 12 consecutive 3.8.B.5.

months.

2. With the calculated dose from the release of radioactive materia'ls in liquid or gaseous effluents exceeding twice the limits of specification 3,8.A.3, 3.8.B.3, or 3 '.B.5, prepare and submit a Special Report to the Commission pursuant to specification

.6.7.3.C.6 and limit the subsequent releases'uch that the limits of 3.8.C.1 are not exceeded.

D. Mechanical Vacuum Pum D. Hechanical Vacuum Pum

1. The mechanical vacuum pump shall At least once during each be capable of being automatically 'perating cycle verify automatic isolated and secured on a signal securing and isolation of the or high radioactivity in the mechanical vacuum pump.

steam lines whenever the main steam isolation valves are open.

2. If the limits of 3.8.C.l are not met, the. vacuum pump shall be isolated.

286

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3 ~ 8 RADIOACTIVE MATERIALS 8 RADIOACTIVE MATERIALS Miscellaneous Radioactive E. Miscellaneous Radioactive Materials Sources Materials Sources

1. Source Leaka e Test 1. Surveillance R uirement

" Each sealed source Tests for leakage containing and/or contamination radioactive material shall be performed by in excess of those the licensee or by quantities of other persons byproduct material specifically listed in 10 CFR authorized by the 30.71 Schedule B and Commission or an all other sources, agreement State, as including alpha follows:

emitters, in excess of 0.1 microcurie, Each sealed

. shall be free of source, except 0.005 microcurie of startup sources x emovable subject to core contamination.. Each flux, containing sealed source with radioactive removable . material, other contamination in than Hydrogen 3, excess of the above with a half-life limit shall be greater than .

immediately withdrawn thirty days and from use and (a) in'ny form either decontaminated other and repaired, or (b) tested than,gas,'hall be disposed of in for leakage accordance with and/or Commission contamination at regulations. intervals not to exceed six months. The leakage test be capable /'hall of detecting the presence of 0.005 microcurie of radioactive material on the test sample.

286a

TABLE 4.8.A

~

RADIOACTIVE LI UID WASTE SA"iPLING AND ANALYSIS PROGRAM LIQUID RELEASE SAYZLING MINI".IPii ANALYSIS TYPE OF ACTIVITY LOWER'IMIT OF DETECTION TYPE FRE UEViCY FRE UENCY ANALYSIS LLD) pCi/ml)

Batch Waste Each Batch Each Batch Principal Gamma 4

Releases prior to release Emit;ters 5 E-7

.One Batch Monthly Dissolved and per Month Entrained Gases. 1 E-5 Monthly Tritium 1 E-5 Proportional Monthly Composite Gross a 1 E-7 (2)

P-32 1 E-6 Quarterly Sr-89, Sr-90 5 E-8 Proportional Quarterly Composite Fe-55 1 E-6 (2)

TABLE NOTATION TABLE 4.8.A (1) A batch release is the discharge of liquid wastes of a discrete volume.

(2) A proportional composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant.

(3) For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radio-nuclides in concentrations near their sensitivity, limits when other nuclides are present in the sample in much greater concentrations. Under these circumstances,'it will be more appropriate to calculate the con-centrations of such radionuclides using observed ratios with those radionuclides which are measurable or the lower limit of, detection may be increased proportionally to the magnitude of the gamma yield (i.e.,

5 E-7/I where I is the photon abundance expressed as a decimal fraction),

but in no case shall the lower limit of detection as calculated in this manner be greater than lOX of the MPC value specified in 10 CFR Part 20, Appendix B, Table II, Column 2.

(4) The principal gamma emitters (those expected to account for ~95X of the total activity present) for which the LLD specification will apply are exclusively the following radionuclides: Cr-51, Zn-65, Co-60, Cs-137, Zr-95, Nb-95, I-131, Na-24, Mn-54, Co-58, Ag-110m, Cs-134, I-133, Cu-64, Mo/Tc-99, and Fe-59 for liquid releases. This list does not mean that only these nuclides are to be detected and reported. Other nuclides which influence accounting for ~95X of the total activity, together with the above nuclides, shall also be identified and reported as being present.

Nuclides which are below the LLD for the analysis may not be reported as being present at the LLD Level for that nuclide. When unusual circum-stances result in LLD's higher than required the reasons shall be documented in the semi-annual effluent report.

287a

TABLE 4.8.B RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Gaseous Minimum of Detection Release Sampling Analysis Type of (LLD)

~TB Fre uenc Activity Anal sis Ci(ml).

(>>

'-3 A. Conta inment Each Purge Each Purge Principal Gamma Emitters (3) 1E-4 Purge Grab Sample H-3 lE-6 BE 1. Stack Principals Gamma Emitters (3) 1E-4

2. Building Vent- Grab Sample Monthly 1E-6 ilation

a. Reactor/Turbine

b. Turbine Exhaust

c. Radwaste O'All Re 1 eas e Conginuous Charcoal I-131 1E-12 Points listed Sample Weekly '-133 1E-10 ( )

'in B. above Continuous Particulate Principal Gamma Emitters (3) 1E-11 Sample Weekly Continuous Composite Gross 1E-ll Particulate Sample Monthly Continuous Composite Sr-89, Sr 90 1E-ll Particulate Sample Quarterly

TABLE NOTATION 4.8.B (1) For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near their sensitivity limits 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 observed ratios with those radionuclides which are measurable or the lower limit of detection may be increased proportionally to the magnitude of the gamma yield (i.e. 1E-4/I where I is the photon abundance expressed as a decimal fraction), but in no case shall the lower limit of detection as calculated in this manner be greater than 10% of the M'C value specified in 10 CFR Part 20, Appendix B, Table TI, Column 1.

(2) When samples are taken moreoften than that shown, the minimum detectable

, concentrations can be correspondingly higher.

(3) The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:, Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, H0-99, Cs-134, Cs-137, Ce-141, and Ce-144 for parciculate 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'hich are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the semi-annual effluent report. The principal gamma emitters ( those expected to account for a 95% of the activity present) for which the LLD specification will apply are exclusively the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Hn-54, Fe-59, Co-58, Co-60, Zn-65, Ho-99, Cs-134, and Cs-137 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other nuclides which influence accounting for 95% of the total activity together with the aboye nuclides shalL also be identified and reported. Nuclides which are below the LLD for the analyses may not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in the LLD's higher than required, the reason shall be documented in the semi-annual effluent report.

288a

1 f

Restricted Area

/I

~ I

~ 1, ~ .../

~ ~ ~ q !I I S JYITCHYARO I

I I PlRKIHC I I I I I TRAHSFOWIER YARD I

Iy I I~X I't, I TVRDIHE 0

, j, TrtP1',

\ ~(

'l y

~

F I I 0'ERV DI.DC A

R'ASTE DC DC DI.DC REACTOR g 00 STORACE lRElS DLDC IHTAKE PVHP!HC STlTIDH S TACK SEW/DE S TREAI AIEHT PI AHT

~Pw4. '>~~>~

MM4~~

-C

~

RGB KK'~v: Pp vto'4 u

+4"; v" 44 u /XiI'> +44 3 1 F~ Ai@YPArs&N.Ci %mi i%':4@VÃlkA " 5 %k C4+A@i@&A -"MOTSIP:~~' '~4MVaQA.ci Q~'+c~c:,

~>>'R:-

pep r ",w FIGURE 4.8.A.1 Assumed Liquid Effluent Restricted Area 288b

~

I

~

I

'. ~

7 I

~

~ ~,

i? .0."}j'I:.'r?

r ~"

IS~I4.,

II r.'jl~ . X .Ir SI ~ . j! I "r,:.4 r I 4

I ~ I AH. .,/;QI'IGNIS II ~I 4Q W)kg 4

<<45))

18 4 ~ '

HI)be 555 W)154545 W )Hi 144 555

~4K x 19

't I4Ij, Hr~<<.

'3 2 y

(/V~-)}lr r: I. I 4H %54 r(D 5 5 5 401 f I)g )C 0 .r 1 ';q)) I W IHf 11 I !I Jt. ~.(,.~,I( Airborne Effluent Restricted Area ~ ." -'H&1 . C' 514 FIGURE 4.8.3.1 ) ) I I) 4I j)21I ) I 3.8 BASES Radioactive waste, release levels to unrestricted areas should be kept "as low as reasonably achievable" and are not to exceed the, concentration limits specified in 10 CFR Part 20. At the same time, these specifications permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than design objectives but still within the con-centration limits specified in 10 CFR Part 20. It is expected that by using this operational flexibility under unusual operating conditions, and exerting every effort to keep levels of radioactive materials released as low as reasonably achievable, the annual releases will not exceed a small fraction of the annual average concentration limits specified in 10 CFR Pait 20.'.8.A LI UID EFFLUENTS Specification 3.8.A.1 is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II. This limitation provides addi-tional assurance that the levels of radioactive materials in bodies of water outside the'ite will not result in exposures within (1) the Section 11.A design objectives of Appendix I, 10 CFR Part 50, to an indi-vidual and (2) the limits of 10 CFR Part 20.106 (e) to the population. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and'its HPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection gCRP ) Publication 2. Specification 3;8.A.3 is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part .50. The Limiting Condition for Operation implements the guides sht forth in Section 11.A of Appendix I. Specification 3.8.A.4'rovides the required" operating flexibility and at the same time implement the guides set forth in Section .IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". Also, for fresh water sites with'rinking water supplies which can be potentially affected by plant dperations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in section III.A of Appendix I that conformance with L 289 3.8.A LlOUXD EFFLUENTS (cont'd) the guides of Appendix $ be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways .is unlikely to be substantial'ly under-estimated. The equations specified in the ODCN for calculating the doses due to the actual felease rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1..109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977'and Regulatory Guide 1.113, "Estimating Aquatic Dispersion .of..Effluents from Accidental and Routine Reactor Releases.~r-the&urpose of Implementing Appendix I," April 1977. NUREG-0133 provides methods for dose calculations;consistent with Regulatory Guides 1.109 and 1.113. Specification 3.8.A.5 requires that the appropriate, portions of the liquid radwaste treatment system be used when specified. This provides assurance that the releases of radioactive materials in-iiquid effluents vill be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion'0 of Appendix A to 10 CFR Part 50 and design objective Section 11.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were. specified as a sui.table fraction of the guide set forth in Section 11.A of Appendix I, 10 Cfr Part 50, for liquid effluents. Specification 3.8.A.6 requires submittal of a special report if the .limiting values of Specification 3.8.A.5 are exceeded and unexpected failures of non-redundant radwaste processing equipment halt waste treatment. Specification 3.8.A.7 requires that suitable equipment to control and monitor the releases of radioactive materials in the liquid effluents are operating during any period when these releases-are taking place. 3'. 8. B AXRBOKiE EFFLULiiTS Specification 3.8.B.I is provided to ensure that the dose rate at any-time a" the exclus-on boundary from gaseous effluents from all units on the siL'ill be within the annual dose limits of "10 CFR Part 20 for unrestricted areas. The annuli dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix', Table 1X. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an .'ndividual in an unrestricted area, either within or outside the exclusion area. boundary, to annual average concentrations exceeding the limits specified in App'ndix B, Table XX of 10 CFR Part 20 {10 CFR Part 20.106{1)0. For individuals who may at times be within the exclusion area boundary, the o<<cupnncy of the individual. will be sufficiently low to compensate for any increase in the atmospheric diffusion. factor abave that for the ex- << iusion area boundary. 290

3. 8. B AIRBORNE EFFLUENTS (Cont'd)

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 exclusion area boundary'o~ (500) mrem/ year to the total body or to ~ (3000) mrem/year to the skin. These, release rate limits also restrict, at all times. the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to ~ 1500 mrem/year for the nearest cow to the plant. Specification 3.8.B.2 requires that appropriate corrective action gs) be taken to reduce gaseous are exceeded.'\ effluent releases if the limits of 3.8.B.1 r" Specification 3.8.B.S is provided to implement the requirements of Section II.C, III.A, a'nd IV of Appendix I, 10 CFR Part 50. The limiting conditions for operation are the guides set forth in Section II.c of Appendix I. Specification 3.8.B.6 provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that'onfor-mance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual . through appropriate pathways is unlikely to be substantially under-estimated. The ODOM calculational methods approved by NRC for calculating the doses due to the actual release rates of the sub)ect materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, "Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision I, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also"provide for determining the actual doeses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man in the unrestricted area. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) deposition. of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. Specification 3.8.B.6 requires that a special report be prepared and submitted to explain violations of the limiting doses contained in Specification 3.8.B.5. 290a AIRBORNE EFFLUENTS Specification 3.8.B.7 requires that the offgas charcoal adsorber beds be used when specified to treat gaseous effluents prior to their release to the environment. This provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appen-dix A to 10 CFR Part 50, and design objective Section IID of Appendix I to 10 CFR Part 50. The. specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections IX.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents. Specification 3.8.B.8 requires that a special report be prepared and submitted to explain reasons for any failure to comply with Specification 3.8.B.7. Specification 3.8.B.3 is provided to implement the requirements of Sections II.B, IIX.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in "Section IV.A of B of Appendix X. Specification 3.8.B.4 provides the required'perating flexibility and at the same time implement the guides set forth ln Section TV.A of Appendix I to assure that the'eleases of radioactive ~aterial in gaseous cffluents will'e kept "as low as is reasonably achievable." The Surveillance Requirements imp'ement the'equirements in Section XII.A of Appendix I that conformance with the guides 'of Appendix I is to be shown by calculational procedures based on models and data such that the ac'tual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the'oses'ue to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Ga'seous Effluents'n Routine Releases from Light-'ater-Cooled Reactors,". Revision 1, July 1977.'he ODCH equations provided for determining the air doses at the exclusion area boundary will be based upon the historical average atmos-pheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. Specification 3.8.B.4 requires that a special report be prepared and submitted to explain violations of the limiting doese contained in Specification 3.8.B.3. 3.8.D. 4. 8. D Mechanical Vacuum. Pum The purpose of isolating the mechanical vacuum pump line is to limit the release of activity from the main condenser. During an accident, fission products would be transported from the reactor through the main steam 'lines to the condenser. The fission product radioactivity would be sensed by the main steam line radioactivity monitors which initiate isolation. 291 4.8.A AND 4.8.B BASES The surveillance requirements given under Specification 4.8.A and 4.8.B provide assurance that liquid and gaseous wastes are properly controlled and monitored during any release'of radio-active materials in the liquid and gaseous effluents. These surveillance requirements provide the data for the licensee and the Commi'ssion to evaluate the station's performance relative to radioactive wastes released to the environment. Reports on the quantities of radioactive materials released in effluents shall be furnished to the Commission on the basis of Section 6 of these technical specifications. ,On the basis of such reports and any additional information the Commission may obtain from time to time require the licensee to take such actions as the Commission deems appropriate. 3.8.E and 4.8.E BASES The objective of this specification is to assure that leakage from byproduct, 'source, and special nuclear radioactive material sources does not exceed allowable limits. 29la (b) ~ Annual 0 era ti Re or t ix tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrern/yr and their associated man rem exposure according to work and job functions,~ e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignnrent to various duty functions may be estimate based on pocket dosimeter, TLO, or film badge measurements. Small exposures totalling less than 20% of the irrdividual total do e need not be accounted for. In the aggregate, at least 80K of the total whole body dose received from external sources shall be assigned to specific major work functions. C ~ i>onthlv 0 erati n Re ~ort. Routine reports oi operating statistics and shutdown experience shall be submitted on a monthly basis to the Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washinqton, C.C. 20555, with a copy to the appropriate Regional Of ice, to be submitted no later than the tenth of each month following tne calendar month cove~ed by the report h narrative summary of operating experience . plmll be submitted in the above schedule. 'ny changes to the Offsite Dose Calculation Manual of Specification 6.10 shall be submitted with the Monthly Operating Report within 90 days in which the change(s) was made effective. 350 Revised 1-10-7S, O. 0 AOYINISTRATIVtl COYiTROl.S

d. Radioloaical Environmental Nonitori

l. TVA shall prepare a report cnt tied "Environ=ental Radio-activity Levels Bro~s Ferry nuclear P'anc - Annual Report."

The report shall cover the previous l2 months of operation and shall be submitted co the Director of the NRC Region II Office (with a copy to the Director, Office of Nuclear Reactor Regulation) withe 120 days af ccr January 1 of each year. 'The rcporc formac horn in Regulatory Guide 4,8 Ticle 1 shall be used. The report shall include su~acies, interpretat'ons, and cvaluacions of thc results of the radiological envirorcental surveillance activicics for the rcport period, 'including a co@parison with preoperational studies aod/or operational controls'as appropriate), and an assessment of the observed impacts of chc plant operation on chc environment. If harmful ef feces or evidence of irreversible damage are detected by the monitoring, the licensee shall provide an an lysis of the problem and a proposed course of, action to alleviate the problem.

2. Results of all radiological environmental camples taken chall be sueuarired and tabulated on an annual basis. In the event that some results are noc available Michin thc 120-day period, the report shall be submitted noting and explaining the reasons for the missing resu1cs. Thc missing data shall be submitted as soon as possible ia a supplementary rcport.

2. Reportable Occurrences Reportable occurrence, includ'nq corrective actions and measures to prevent reo( curxence, shall be reported co the NRc. Supplemental reports may be required to fully describe f inal resolution of occurrence. In case oi corrected or supplemental reports, a 1 i cens ee event report shall be complered ano reference shall be made to the oriqinal report date.

35I ~,

6. 0 AOMIHISTRATIVE CONTROLS (9} Per formance'f structures, systems, or components'that requires remedial action or corrective measures to prevent operation in a manner less conservative than 'assumed in the accident analyses in the safety analysis report or technical specif'cations bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development ot an unsafe condition.

Note: This item is intended to provide for reporting of potentially generic problems. (10) - The concentration of . radioac tive .material in liquid effluents released to unrestricted areas exceeds the concentrations specified in 10 CFR Part 20; Appendix 8, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. Concentration of dissolged or entrained noble gases exceeds 2 x10 Ci/ml total activity. (11) (a). The dose rate for noble gases equals or ~ exceeds 500 mrem/yr to the total body or 3000 mrem/yr to the'kin. '(b). The dose rate for all.radioiodines, for all. radioactive materials in particular form, and for radionuclides other 'than noble gases with half lives greater than 8 days exceeds 1500 mrem/yr to any organ. 354 6.0 ADMINISTRATIVE CONTROLS b. cccutceuces discussed belcw:hell be the "ubject cf written reports to the Director of the appropriate Reg ional Office w'hin thirty days of occurrence of the event., The written report shall include, as a minimum, a completed cooy of a licerrsee event report forms Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to piovide complete evplanation of the circumstances surrounding the event. Reactor protection system or engineered safety feature instrument settings which are found to be less conservative tnan those established by the technical speci'ications but wh'ch do not prevent the fulfillment of the func" ional requirements of a fectqd systems. (2) Conditions leading to,operation in a degraded mode permitted by a limitirrg condi ion for operation or plant shutdown required by a limiting condition for operation. Note: Routine surveillance tes t ing, instrument calibration, o preventat've maintenance which require system configurations as desc ibed in items 2. b. (1) and 2.b. (2) need not ce repor" ed excect where test results themselves revea' degraced mode a'escribed above; (3) Observed inadequacies in the imolementat'on of administrative or orocedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems. (rr) Abnormal degradation of systems other than those specif'ied in item 2.a (3) above designed to contain radioactive material resulting from the fiss'ion process. Note: Sealed sources or calibration sources are not irrcluded under t)ris item. Leakage of valve packing or gaskets within the liorits for identified leakage set forth in technical specifications need not be reported under this item. (5) . An unplanned offsite release of 1) more tl>an 1 curie oi radioactive ~raterial in liquid eHluents, 2) more than 150 curies of noble gas in gaseous effluents, or 3) more than 0.05 curies of radioiodine in gaseous effluents. Tire report of an unplanned offsite release of radioactive material shall include the following information;

l. A description of the event and equipment involved.

2. Cause(s) for the unplanned release,

3. Actions taken to prevent recrrrrence.

4. Conseqrences of the unplanned release.

355

6. 0 ADMINISTRATIVE CONTROLS Anomalou Heasuremencs -Radiolo ical Environmental Monitorin (1.) If, during any, 12-month report period, a measured Jevel of radio-s rrctivity any environmental medium other than those associated in vith gaseous radioiodine releases cxcecds tea times the control station Value, a written notification vill be submitted vithin one veek advising the NRC of this cbndition." This'notification should include an evaluacion of any release conditions, environ-mental factors, or other aspects necessary to ex~lain the anomalous result.

(2.} If, during any 12-nonrh score,per'iod, e nessurrd level of radioactivity in any environmental medium other chan those associated vith gaseous radioiodine releases exceed" four times the control station value, a written notification mill. be submitted W thin 30 day advis'ng the HRC of thirs condition. This notifica ion should inclufle an eveluap iron rgf any release conditions, environmental factors, or other aspec"s necessary to explain the anor~lous results If individual milk samples sho- I-'31 concentrations of 10 picocurics p r ~ ~ ll lite. or grea er a pl sflr be submitted vithin 10 days advising the NRC of the proposed action to ensure the plant related annual doses v'll be within the desigu obgective of 15 mrer3/yrIrcactor to cl..e thyroid of acy ind' idua1. (.,

4. If m lk samples collec ed over a ca..(; ':

~ 'gua'.r'; ~ velage concentrations of 6.0 picocur$ es per incor cr r,re".ret,' plan shall be submitted vithin,30 day,, adv" in" cnu N'c'.0 o the proposed action co ensure chc plant-rela ec anr.ua'oses v'1l be w'chin che design ob)ective of 15 m:ea/yr/rcacrllr ro ch>> thyroid of any individua'.

In the case of a tentar ivenly anomalous value for rociost:oar ium, a conriwcory reanalysis o. the origin. 1, a cuplicatc or a acw safuplc macy be desirable. Ire this it:s agree the resu's of the conf ir ncory analys's s .al1 bi comp'<<<<'"- c'...e c rl'est time consi" ten vitl: thf: .ca lysis, and i -he higa valu

~ ~ e r I::e.., c';,e re>gnrt to t.ee hRC "hall be submitted mthin one week following this alla ysis. (5.) If such levels as discussed in 6.7.2.c.3 and 6.7.2.n.d cne be definitely ahovn to result from sources other than the Brovnu Ferry Nuclear Plant, the reporting action called for in M6.3(a)3 and 5.6.3(a)4 need not be taken. Justification for assigning high levels of radioactivity to sources other than the Brovns Ferry Nuclear Plant must be provided ia che annual report. 355a

6. 0 ADMINISTRATIVE CONTROLS 6.7.3 Uni ue Re ortin Re uirements A. Radioactive Effluent Release Re ort A report on the radioactive discharges released from the site during the previous 6 months of operation shall be submitted to the Director of the Regional Office of Inspection and Enforcement within 60 days after January 1 and July 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents released and solid waste shipped from the plant as delineated in Regulatory Guide 1.21, Revision 1, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B thereof.

The report shall include a summary of conditions concurrent with the the'eterological release of gaseous 'effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1, with data summarized on a quarterly basis following the format of Appendix B thereof. Calculated offsite dose. to humans resulting from the release of effluents and their subsequent dispersion in the atmosphere shall be reported as recommended in Regulatory Guide 1.21, Revision 1. Doses to individuals outside the site boundary (UNRESTRICTED AREA) shall be calculated in accordance with the ODCM. Source Tests Results of required leak tests performed on sources i the tests reveal the presence of 0.005 microcurie or more of removable contamination. Special Reports (in writing to the Director of Regional Office of Inspection and Enforcement). Reports on the following area" shall be submitted as noted:

a. S>>conlary Containment 4 7 C ~ ~ within 90 Leak Rate Testing (5) day.. of completion of each test.

b. Fatigue Usage 6.6 Annual evaluation Opera ting Report C. Seismic Instrumentation 3.2.J.3 Within 10 days I nope ra bi 1 i ty after 30 days of inoperabi i ty 1

356

6. 0 ADMINISTRATIVE CONTROLS

2. Prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding THE LIMIT(s) and defines the corrective action(s) to be taken to reduce the releases of radioactive material in liquid effluents during the remainder of the current calendar quarter and during the subsequent'hree calendar quarters so that the average dose or dose commitment to an individual from such releases 'during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include:

(1) the results of radiological analyses of the drinking water sources (if applicable), and (2) the radiological impact on finished drinking, water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act. (Applicable only if drinking water supply is taken from the" receiving water body.) See item 6 below.

3. Prepare and submit to the Commission within 30 days, a Special Report which includes the following information:

a. Identification of equipment of subsystems not OPERABLE and the reason for nonoperability.

b. Action(s) taken to restore the non operable equip-ment to OPERABLE status.

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

4, Prepare,and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and'efines the corrective actions to be taken to reduce the releases of radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents during the remainder of the current calendar, quarter and during the subsequent three calendar quarters so that the average dose or dose commitment to an individual from such releases during these four calendar quarters is within 15 mrem to any organ. See item 6 below.

5. Prepare and submit to the Commission within 30 days, a Special Rcport which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous ef fluenL. during the remainder of the current calendar quarter and duri n:. cCce subsequent three calendar quarters so that the average dose during these four calendar quarters is within LO mrad for gamma radiation and (20) mrad for beta radiation.

See item 6 below. 356a 6.0 ADMINISTRATIVE CONTROLS

6. Prepare and submit to the Commission a Special Report which includes an analysis demonstrating that radiation exposures to all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard.

Otherwise obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard. 356b UNIT 3 a protective trip function. Arip system may require one or more instrument channel trip signals related.to one or more plant parameters in order to initiate, trip system action. Ini.tiation of protective action ma require the tripping of a single trip system or the conincident tripping of two trip systems.

7. Protective Action - An action initiated by system when a limit is reached. the'rotection A

protective action can be at a channel or system level.

8. Protective unction - A system protective action which results from the protect'ive action of the channels monitoring a particular plant condition.

9~ Simulated Automatic Acutat on - Simulated automatic acutation means applying a simulated signal to the sensor to actuate the circuit in question.

10. Logic - A logic is an arrangement of relays, contacts, 'and other components that produces a decision output.

from channels and produces decision outputs to the actuation logic. (b) Actuation -' logic that. receives signals (either from initiation 'logic or channels) and produces decision outputs to,accomplish a protective action. 1'1. Channel Calibration Shall be the adjustment, as necessary, of the channel output such that it. responds with necessary range and accuracy to known values of the parameters which the channel monitors. The channel calibration shall encompass the entire channel including alarm and/or trip functions and shall include the channel functional test. The channel cali-bration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. Non-calibratable components shall be excluded from this require-ment, but will be included in channel functional test and source check.

12. Channel Functional Test Shall be

'. Analog Channels - the injection of a simulated signal'nto the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b. Bistable channels the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

13. Source Check -'hall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive sources or multiple of sources.

W. Functional Tests - A functional test is the manual operation or initiation of a system, subsystem, or component to verify that it functions tolerances ( e.g., the manual start ofwithin design to verify that volume of water). it runs and that it pumps the required a core spray pump Xe Shutdown << The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed. Yo En ineered safe uard An engineered safeguard is safety system the actions of which are essential toa a safety action required in response to Downtime - The cumulative downtime accidents.'ulative safety components and systems whose downtime isforlimited Z~ those to 7 consecutive days prior to requirinq reactor shutdown shall be limited to any 7 days in a consecutive 30 day period. AA. Solidification Shall be the conversion of radioactive wastes to conform to the license requirement of the receiving burial ground.'B. Offsite Dose Calculation Manual (ODCM) Shall be a manual describing the environmental monitoring program and the methodology and parameters used in the calculation of release rate limits and off-site doses due to radioactive gaseous and liquid effluents., CC. Unrestricted Area All area beyond the site boundary access to which is< not controlled for protection of individuals from exposure to radiation and radioactive materials. TABLE 1.1 SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours. D At least once per 24 hours. At least once per 7 days. At least once per 31'ays. =. At least once per 92 days. SA At least once per 6 months. At least once per 18 months. S/U Prior to each reactor startup. N.A. Not applicable. LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RFOUIREMENTS .3.2.K Radioactive Gaseous Effluent 4.2.K Radioactive Gaseoua Effluent Monitorin Instrumentation Monitorin Instrumentation

1. The radioactive 'gaseous l. Each of .the radioactive effluent monitoring instru- gaseous effluent monitoring ments listed in table 3.2.K instruments shall be'demon-

.'hall be operable at all strated operable by perfor-times with their alarm/trip mance of tests in accordance setpoints set to ensure that with table 4.2.K. the limits of specification 3."S.B.1 are not exceeded.

2. The action required when the number of operable channels is less than the Minimum Channels Operable requirement is specified in the notes for table 3.2.K.

56a TABLE 3.2.K RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument Parameter, Action

1. Stack Noble Gas Release Rate A/C Activity Monitor Measurement

b. Iodine Installed

.Cartridge

c. Particulate NA Installed B filter

2. Reactor /turbine Building Ventilation

'/C

a. Noble Gas Release Rate Activity Monitor Measurement

b. Iodine Monitor Release Rate B/C Measurement

c. Particulate Monitor Release Rate B/C Measurement

3. Turbine Building Exhaust

a. Noble Gas Release Rate A/C Activity Monitor Measurement

b. Iodine Monitor Releas'e Rate B/C Measurement

c. Particulate Monitor Release Rate B/C Measurement

3.2.K (Continued) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument Parameter, Action

4. Radwaste Building Ventilation

a. Noble Gas (l) Release Rate A/C Activity Monitor b.. Iodine Monitor (l) Release Rate Measurement B/C

c. Particulate Monitor (l) Release Rate B/C Measurement

NOTES FOR TABLE 3.2.K

During releases via this pathway.

ACTION A 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 7 days provided a tem-porary monitoring system is installed or'grab samples are taken and analyzed't least once every .4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . A(TION B 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 28 days, provided samples are continuously collected with auxiliary sampling equipment for periods on the order of seven (7) days and analyzed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the end of the sampling period. ACTION C A monitoring system may be out of service for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for functional testing, calibration, or repair without providing temporary monitor or initiating grab sampling. 87c TABLE 4.2eK RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Modes In Which Instrument Source Channel Functional Surveillance Instrument Check Check Calibration Test Re uired

1. Stack

a. Noble Gas M Q(1) M(2)

Activity Monitor

2. Reactor/Turbine'uilding Ventilation

a. Noble Gas M Q(1) M(2)

Activity I Monitor

b. Iodine Monitor Q(1) M(2)

c. Particulate Monitor Q(1) M(2)

3. Turbine Building Exhaust Noble Gas Q(1) M(2)

Activity Monitor

b. Iodine Monitor Q(1) M(2)

c. Particulate 'Monitor D Q(1) M(2)

4. Radwaste Building Ventilation

a. Noble Gas D Q(1) M(2)

Activity Monitor

b. Iodine Monitor D Q(1) M(2)

c. Particulate Monitor D Q Cl) M(2)

NOTES FOR TABLE 4 '.K

During releases via this pathway.

(1) The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Bureau of standards radiation measurement system) radioactive source (s) positioned in a reproducible geometry with respect to the sensor. (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following'conditions exist:

l. Instrument indicates measured levels above the alarm/trip setpoint.

2. Instrument indicates an inoperable downscale failure.

3,07b The operability of the seismic instrumentation ensures that sufficient capability, is available to promptly determine the magnitude of a siesmic event and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for Browns Ferry Nuclear Plant. The instrumentation provided is consistent with specific portions of the recommendations of Regulatory Guide 1.12 uInstrumentation for Earthquakes.~'he radioactive gaseous effluent instrumentation is'rovided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases'f gaseous effluents. The alarm/trip .setpoints for these instruments will be calculated in accordance with plant approved procedures to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The most likely case would be to stipulate that'ne channel be tested, and restored, and then immediately following, 'ypassed, the second channel be bypassed, tested, and restored. This i.s shown by Curve No. 4. Note that there is no true minimum. The curve does have a definite knee and very little reduction in system unavailability is achieved by testing at a shorter interval than computed by the equation for a single channel. The best test procedure of all those examined is to perfectly stagger the tests. That is, if the test interval is four months, test one or the other channel every two months. This is shown in Curve No. 5. The difference between Cases 4 and 5 is negligible There may be other arguments, however, that more strongly support .the perfectly staggered tests, including reductions in human error. The conclusions to be drawn are these: A 1 out of n system may be treated the same as a single channel in terms of choosing a test i.nterval; and

2. more than one channel should not be bypassed for testing at any one time.

The radiation monitors in the refueling area ventilation duct which initiate building isolation and standby gas treatment operation are arranged 'i:n two 1 out of 2 logic systems. The bases given for the rod blocks apply here also and were used to arrive at the functional testing frequency. The off-gas post treatment monitors are connected in a 2 out of 2 logic arrangement. Based on experience with instruments of similar design, a testing interval of once every three months has been -found adequate. The automatic pressure relief instrumentation can be considered to be a 1 out of 2 logic system and the discussion above applies also. A The criteria for ensuring the reliability and accuracy of the radioactive gaseous effluent instrumentation in listed in Table 4..2.K. LIMITING CONDITIONS FOR OPERATION ~ SURVEILLANCE REQUIREMENTS 3.8 RADIOACTIVE MATERIALS 4.8 RADIOACTIVE MATERIALS A licabilit A licabilit 'I Applies to the controlled release of 'Applies to the periodic test and record radioactive liquids and gases from requirements and sampling and monitoring the facility. 'ethods used for facility effluents. ~Ob ective Ob ective To define the limits and conditions To ensure that radioactive liquid for the releaseof radioactive and=gaseous releases from the facility effluents to .the environs to assure are'aintained within the limits that any radioactive releases are specified by Specifications'3.8.A and as low as reasonably achieveable and 3.8.B. within the limits of 10 CFR Part 20. S cification A. Li uid Effluents A. Li uid Effluents The concentration of radio- 1. Facility records shall be active material released at maintained of radioactive any time from the site to concentrations and volume unrestricted areas (see before dilution of each Figure +.f.A- I shall be batch of liquid effluent limi.ted to the concentrations released, and of the average specified in 10 CFR Part 20, flow and length of 'ilution Appendix B, Table II, Column time over which each discharge 2 for radionuclides other occurred. than dissolved or entrained noble gases. For dissolved 2. Radioactive liquid waste or entrained noble gases, the sampling and activity analysis 'concentration shall be of each liquid waste batch to limited to 2E-4 uCgml total be discharged shall be performed activity. prior to release in accordance with Table 4.8.A.

2. If the limits of 3.8.A.1 are exceeded, appropriate action shall be initiated to bring the release within limits.

Provide prompt notification to the NRC pursuant to Section 6.7.2.a.

3. The dose or dose commitment 3. The liquid effluent radiation to an individual from. radio- monitor shall be calibrated at active materials in liquid least quarterly by means of a effluents released from each known radioactive source(s). The unit to unrestricted areas monitor shall also have an (See Figure 'f.>.k l ) shall instrument channel functional be limited: test monthly and an instrument check daily.

299 I LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8.A Li uid Effluents 4.8.A Li uid Effluents

a. During any calendar quarter to

<1.5 mrem to .the total body and to <5 mrem to any organ and,

b. During any calendar year to 3 mrem to the total body and~10 mrem to any organ.,

4. If the limits specified in 3.8.A.3. The operation of the automatic a6b above are exceeded, prepare and is'olation valves and discharge tank submit Special'Report persuant to selection values shall be checked Section 6.7.3.C.2. annually.

5. The liquid radwaste system shall be 5. 'he accuracy of the radwaste maintained,and operated to process effluent flow rate monitor shall liquid radwaste when it appears be checked at least monthly.

during quarterly operation that the releases to unrestricted areas (see - Figure 4.t Aal ) when averaged over 31 days would exceed 0.06 mrem to the total body and 0.21 mrem to any organ.

6. During a quarter if radioactive 6. Cummulative quarterly and yearly liquid waste must be discharded with-, dose contributions from liquid out treatment after the limits effluents shall be determined as specified in 3.8.A.5 above are ex- 'pecified in plant approved pro-ceeded, prepare and submit the cedures at least once every 31 days.

Special Report pursuant to Section 6.7.3.C.3.

7. During release of radioactive wastes 7. Doses due to liquid releases from the radwaste processing system, to unrestricted areas shall be the following conditions shall be met: projected at least once per 31

~ days.

a. Liquid waste activity and flow rate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge valve before exceeding the limits specified in 3.8.A.l. above. If this requirement cannot be met, continued release of liquid effluents shal!. be permitted only during the succ~e~ing 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period, two independent samples o each tank shall be, analyzed and two station personnel shall independently check valving before 'the discharge.

300 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8 RADIOACTIVE MATERIALS 4.8 RADIOACTIVE MATERIALS B. Airborne Effluents B. Airborne Effluents

1. The dose rate at any The gross 8/f and time in the unre- particulate activity of stricted areas (see gaseous wastes released Figure +-<<.I ) due to to the environment shall radioactivity released be monitored and recorded in gaseous effluents from the site shall be limited to the follow-ing v'alues:

a ~ The dose rate a. '.For effluent limit for noble streams having con-gases shall be tinuous monitoring <500 mrem/yr to capability, the the total body activity and flow and ~3000 " rate shall be mrem/yr to the monitored and skin, and recorded to enable release rates of gross radioactivity to be determined or an hourly ba'sis using instruments specified in Table 3.2.K;

b. The dose rate b. For =effluent strear limit for all without continuous radioiodine s for monitoring capa-all radioactive bility, the activity materials in shall be monitored particulate for and recorded and and for radio- the releases throu/

nuclides other these streams shal] than noble gases be controlled so with half lives that the release greater than 8 rates from all days shall be streams are within 1500 mrem/yr to the limits speci-any organ. fied in 3.8.B

2. If the limits of 2. Radioactive gaseous waste 3.8.8.1 are exceeded, sampling and activity appropriate corrective analysis shall be performi action shall be ini- in accordance with Table tiated to bring the 4.8.3.

releases within 'limits. Provide prompt notifi-cation t'o the NRC pursuant to section 6.7.2.a. 301 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

3. The air <<<e in unre- 3. Cumulative quarterly and stricted areas (see yearly dose contributions Figure 4K 8, I ) due to shall be determined as noble gases released specified in plant approve in gaseous effluents procedures at least once per unit shall be every 31 days.

limited to the follow-ing: a ~ During any calendar quarter, to ~ 5 mrad for gamma radiation and ~ 10 mrad for beta radia-tion;

b. During any calendar year, to ~ 10 mrad for gamma radiation and (

20 mrad for beta radiation. 4 ~ If the calculated air 4. Doses due to gaseous dose exceeds the limits releases to unrestricted specified in 3.8.~ 3 F areas shall be projected above, prepare and at least once per 31 days. submit a special report pursuant to section 6.7.3. C.5 The dose to an indivi- 5. Sampples of of fgass dual from radioiodines, effluents shall be ana-radioact,ive materials lyzed at least, weekly to in particulate form, determine the identity and radionuclides other and quantity of the than noble gases with principal radionuclides half lives greater than being released. 8 days in gaseous effluent released per unit to unrestricted areas (see Figure ) shall be limited to the following:

a. D~ing any calendar quarter to ~ 7.5 mrem;

b. During any calendar year to, 15 mrem; 302

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

6. If the calculated doses exceed the limits of 3.8.B.5 above, prepare and submit a special re-port pursuant to section 6.7.3. C.4

7. During operation above 50% power the dis-charge of the SJAE must'e routed through the charcoal adsorbers when the projected gaseous effluent re-leases to unrestricted areas (see Figure 'f.$'.8.

J ) when averaged over 31 days would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation.

8. With gaseous wastes being discharged for more than 31 days with-out treatment. and in excess of the limits of

3. 8.B . 7 above, prepare and submit a special report pursuant to section 6. 7. 3.C . 3 303

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8.C Radioactive Effluents Dose 4.8. C Rad ioac tive Ef fluents Dose The dose or dose commitment to a real 1. Cumulative dose contributions individual from all uranium from liquid and gaseous sources is limited to ~ 25 mrem fuel'ycle effluents shall be determined to the total body or any organ (except in accordance with specifi-the thyroid, which is limited to ~ 75 cations 3.8.A. 3, 3 '.B.3, and mrem) over a period of 12 consecutive 3.8.B.5. months. 2; . With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of specification 3.8.AD', 3.8.B.3, or 3.8.B.5, prepare and submit a Special Report to the Commission pursuant to specification 6.7.3.C.6 and limit the subsequent 'releases'uch that the limits of 3.8.C.1 are not exceeded. D. Mechanical Vacuum Pum

1. The mechanical vacuum pump shall At least once during each be capable of being automatically operating cycle verify automatic isolated and secured on a signal securing and isolation of the or high radioactivity in the mechanical vacuum pump.

steam lines whenever. the main steam isolation valves are open.

2. If the limits of 3.8.C.1 are not met, the. vacuum pump shall be isolated.

304 3 ~ 8 RADIOACTIVE MATERIALS 0 ~ 8 RADIOACTIVE MATERIALS Miscellaneous Radioactive ~ E. Miscellaneous Radioactive Materials Sources Materials Sources

1. Source Leaka e Test Surveillance R uirement

" Each sealed source Tests for leakage containing and/or contamination radioactive material shall be performed by in excess of those the licensee or by quantitiee of other persons byproduct material specifically listed in 10 CFR authorized by the 30.71 Schedule 8 and Commission or an all other sources, agreement State, as including alpha follows: emitters, in excess of 0.1 microcurie, a~ Each sealed . shall be free of ? source, except 0.005 microcurie of startup sources r emovabl e subject to core contamination., Each flux, containing sealed source with radioactive removable , material, other contamination in than Hydrogen 3, excess of the above -'." with a half-life limit shall be greater than immediately withdrawn thirty days and from use and (a) in ~any form either decon'taminated other than,gas; and repaired, or (b) shall be tested disposed of in for leakage '-accordance with and/or Commiesion contamination at regulations. intervals not to exceed six months. The leakage test be capable ~'hall of detecting the presence of

0. 005 microcurie of radioactive material on the test sample.

305 TABL~ 4.8,.A RADIOACTIVE LI UID WASTE SA!fPLIHG AND ANALYSIS PROGRtQf LIQUID RELEASE SA! fPLIHG MINI!fUM ANALYSIS TYPE OF ACTIVITY LOVER LIMIT OF DETECTION TYPE FRE UENCY FRE UENCY ANALYSIS LTD uCi/ml) Batch Haste Each Batch Each Batch Principal Gamma Releases prior to release Emiqters 4 5 E-7 One Batch Monthly Dissolved and per Month Entrained Gases 1 E-5 Monthly Tritium *1 E-5 Proportional Monthly Composite Gross a 1 E-7 (2) P-32 Quarterly Sr-89, Sr-90 5 E-8 Proportional Quarterly Composite Fe-55 1 E-6 (2) TABLE NOTATION - TABLE 4.8.A (1) A batch release is the discharge of liquid wastes of a discrete volume. (2) A proportional composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant. (3) For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radio-nuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations. Under these circumstances,'it will be more appropriate to calculate the con-centrations of such radionuclides using observed ratios with those radionuclides which are measurable or the lower limit of. detection may be increased proportionally to the magnitude of the gamma yield (i.e., 5 E-7/I where I is the photon abundance expressed as a decimal fraction), but in no case shall the lower limit of detection as calculated in this manner be greater than 10X of the MPC value specified in 10 CFR Part 20, Appendix B, Table II, Column 2. (4) The principal gamma emitters (those expected to account for ~95X of the total activity present) .for which the LLD specification will apply are exclusively the following radionuclides: Cr-51, Zn-65, Co-60, Cs-137, Zr-95, Nb-95, I-131, Na-24, Mn-54, Co-58, Ag-110m, Cs-134, I-133, Cu-64, Mo/Tc-99, and Fe-59 for liquid releases. This list does not mean that only these nuclides are to be detected and reported. Other nuclides which influence accounting for ~95X of the total activity, together with the above nuclides, shall also be identified and reported as being present. Nuclides which are below the LLD for the analysis may not be reported as being present at the LLD Level for that nuclide. When unusual circum-stances result in LLD's higher than required the reasons shall be documented in the semi-annual effluent report. 307 TABLE 4.8.B RADIOACTIVE GASFOUS WASTE SAHPLING AND ANALYSIS PROGRAH Loner Lxmit Gaseous Hinimum of Detection of Release Tvv e Sampling Analysis Freauenc Type Activity Anal sis ~ci (LLD) (ml ) A. Containment Each Purge Each Purge Pr inc ipa 1 Gamma Emit ters (3) 1E-4 Purge -. Grab Sample H-3 1E-.6 B~ 1. Stack Principal Gamma Emit ters (3) lE-4

2. Building Vent- Grab Sample Honthly H-3 1E-6 ilation

a. Reactor/Turbine

b. Turbine Exhaust

c. Radwaste Charcoal I-131 1F.-12 (2)

O'All Release Continuous Points listed Sample Meekly I-133 1E-10 in. B. above Continuous Particulate Principal Gamma Emitters (3') 1E-11 (2) Sample Meekly Continuous Composite Gross 1E-11 Particulate-Sample Honthly Continuous Composite Sr-89, Sr 90 1E-11 Par ticulate Sample Quarterly TABLE NOTATION 4.8.B (1) For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near their sensitivity limits 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 observed ratios with those radionuclides which are measurable or the lower limit of detection may be increased proportionally to the magnitude of the gamma yield I (i.e. 1E-4/I where is the photon abundance expressed as a decimal fraction), b'ut in no case shall the lower limit of detection as calculated in this manner be greater'han 10% of the HPC value specified in 10 CFR Part 20, Appendix B, Table II, Column 1. (2) When samples are taken more often than that shown, the minimum detectable . concentrations can be correspondingly higher. (3) The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, M0-99, Cs-134, Cs-137, Ce-141, and Ce-144 for parciculate 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 should not be reported as being present at the LLD level for that nuclide. When unusual circumstances resu1t in LLD's higher than required, the reasons shall be documented in the semi-annual effluent report. The principal gamma emitters ( those expected to account for a 95% of the activity present) for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, and Cs-137 -for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other nuclides which influence accounting for 95% of the total activity together with the above nuclides shall also be identified and reported. Nuclides which are below the LLD for the analyses may not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in the LLD's higher than required, the reason shall be documented in the semi-annual effluent report. 309 <<<<<<r<<<<<<<<%<<r w<< "~ '<<i a'/<<; Pa I ~ ~ / / I / S JYI TCIIVARP I I I I PARR/iVC I TRAIISFORIIER VARD Iw I ~W I I I SER V TURD///E <<~ I ecDc DLDC <</ A g OO S TO/I ARE'AS ACE OFFICE IYASTE eCOC REACTOR ecDc I//TAP'E PIIIIP!IIC S TA TIOiV <<~ STACI/ <<~ r ~ SEIYACE TREATJIEIIT P/.A!IT +g<<

V.:-,~ -<<.<rp

<<p

y$~WWW pru-<<<<<<g"..fPWj<<<<<<~. w <<<<> D/SC//A ACE $

-<":.)>i<<g8p -:::<<s'Y//EE C ER<<<'l,RESERVOIR.-+ -~P:V'p"4Wig+. i-.+ .. =- gp rrr '<<<<<<INN<A~~W~~~N <<P ~.% - '%Ã$MAa<<<<<<<<M~~<<<<: "%~MA%'~~ <<<<m~~i%~A&mAC+~ FlGURE 4.8.A<<1 Assumed Liquid Effluent Restricted Area 310 l'"" s I ] I )J )$ p I, ~ ) t I s ~ ~ ~s s ~s JorsII 3 ~ s o ) s ', Y 'I y N//)I ': I 's7:.): ),, ... '""I.s!'s":i'I'0l ( r .s,r J s "-"-"( s s \ sl ' /I gs X. o ~ )~ ' ~~ f,", s 'Ir ~, 5N Is ~~ ~ !Ir~

.'

~

o Isrr 24 s t)'jh~gl,i.i 2

.i;)

' sg ,(

14 ssOROrsIsS 22RRf JAR pWs)I s

~psst sss n r 4q ~ ~

j>;()(jV ':

<o.

's

(

I

~~ $ 1.

4r 0 pssW2224L i~:. Isrs 21$

~ 2'r LH'I 171

\

\ 1

~o o '.

". 1 tlyw 23 'Ir ~r 19 Irss s ~ I

"".I 1". 20 :i s

19 1: I

\ 4 s "/)',>~-)). ~'- ~s:!,I..'hV , )'1 ~

s

~ D RrrIsp)s $

~ ss

't; Js1.

war l I

,:: l

.'r ss I

' 's 2 r sP ~

I ~ t I . Iso

,X) 1

) ' FIGURE 4.8.8.1 Airborne Effluent Restricted Area

~

<; r.."g'.-.

I ~s-- ~ ~

+i r,.

CIQ r- n g;.r r:: s lwjq~

sO ~ Or, l s 29

~ .iP..s 1

3.8 BASES Radioactive waste release levels to unrestricted areas should be kept "as low as reasonably achievable" and are not to exceed the concentration limits specified in 10 CFR Part 20. At the same time, these specifications permit the flexibility of operation, compatible with considerations of health and safety, to assure that" the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than design objectives but still within the con-centration limits. specified in 10 CFR Part 20. It is expected that by using this operational flexibility under unusual operating conditions, and exerting every effort to keep levels of radioactive materials released as low as reasonably achievable, the annual releases will not exceed a small fraction of the annual average concentration limits specified in 10 CFR Part 20.

3.8.A LI UID EFFLUENTS Sp cification 3.8.A.l is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II. This limitation provides addi-tional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures within (1) the Section 11.A design objectives of Appendix I, 10 CFR Part 50, to an indi-vidual and (2) the limits of 10 CFR Part 20.106 (e) to the population. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection gCRP )

Publication 2.

Specification 3:8.A.3 is 'provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides sht forth in Section 11.A of Appendix I.

Specification 3.8.A. 4 provides the'equired'perating flexibility and at the same time implement the guides set forth in Section .IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents wi11 be kept "as low as is reasonably achievable".

Also, for fresh water sites with" drinking water supplies which can be potentially affected ~plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in "section III.A of Appendix I that conformance with 311

3.8.A LI UID EFFLUENTS (cont'd) the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially under-estimated. The equations specified in the ODMC for calculating the doses due to the actual release rates of radioactive materiaIs in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1..109, "Calculation of Annual Doses to Man from Routine Releases of. Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the. Purpose .

of Implementing Appendix I," April 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.

Specification 3.8.A.5 requires that the appropriate portions of the liquid radwaste treatment system be used when specified. This provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable."

This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design

.objective Section 11.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section 11.A of Appendix I, 10 Cfr Part 50, for liquid effluents.

Specification 3.8.A.6 requires submittal of a special report if the

.limiting values ot Specification 3.8.A.5 are exceeded and unexpected failures of non-redundant radwaste processing equipment halt waste treatment.

Specification 3.8.A.7 requires that suitable equipment,to control and monitor the releases of radioactive materials in'he liquid effluents are operating during any period when these releases are taking place.

3.8. B AIRBORNE EFFLUEiÃiS Specification 3.8.B.l is provided to ensure that the dose rate at any-time at the exclusion boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR 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. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the exclusion area boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)0. For individuals who may at times be within the exclusion area boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the ex-clusion area boundary.

312

3.8.B AIRBORNE EFFLUENTS (Cont'd)

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 exclusion area boundary'o~ (500) mrem/

year to the total body or to ~ (3000) mrem/year to the skin. These release rate limits also restrict, at all times. the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to ~ 1500 mrem/year for the nearest cow to the plant.

Specification 3.8.B.2 requires that appropriate corrective action gs) be taken to reduce gaseous effluent releases are exceeded.

if the limits of 3.8.B.l Specification 3.8.B.5 is provided to implement the requirements of Section II.C, III.A, and IU of Appendix I, 10 CFR Part 50. The limiting conditions for operation are the guides set forth in Section XI.c of Appendix I.

Specification 3.8.B.6 provides the required operating flexibility and at the same time implement the guides set forth in Section IU.A of Appendix I to assure that the releases -,of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable."

The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section IIX.A of Appendix I that confor-mance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially under-estimated. The ODOM calculational methods approved by NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, "Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision I, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"

Revision 1, July 1977. These equations also provide for determining the actual doeses based upon the historical average atmospheric conditions.

The release rate specifications for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man in the unrestricted area.

The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

Specification 3.8.B.o requires that a special report be prepared and submitted to explain violations of the limiting doses contained in Specification 3.8.B.5.

313

AIRBORNE EFFLUENTS Specification 3.8.B.7 requires that the offgas charcoal adsorber beds be used when specified to treat gaseous effluents prior to their release to the environment. This provides reasonable assurance that the releases of radioactive materials in gaseous effluents'ill be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appen-dix A to 10 CFR Part 50, and design objective Section IXD of Appendix I to 10 CFR Part 50. The .specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections XX.B and XI.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

Specification 3.8.B.8 requires that a special report be prepared and submitted to explain reasons for any failure to comply with Specification 3.8.B.7.

Specification 3.8.B.3 is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in

..Section IV.A of B of Appendix X.

Specification 3.8.B.4 provides the required operating flexibility and at the same time implement the guides set'orth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will'e kept "as low as is reasonably achievable." The Surveillance Requirements imolement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data, such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODOM for calculating the'oses'ue to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents'n Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.'he ODCM equations provided for determining the air doses at the exclusion area boundary will be based upon the historical average atmos-pheric conditions. NUREG-0133'rovides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. Specification 3.8.B.4 requires that a special report be prepared and submitted to explain violations of the limiting doese contained in Specification 3.8.B.3.

3.8.D 4.8.D Mechanical -Vacuum.Pum The purpose of isolating the mechanical vacuum pump line is to limit the r'elease of activity from the main condenser. During an accident, fission products would be transported from the reactor through the main steam lines to the condenser. The fission product radioactivity would be sensed by the main steam 1ine radioactivity monitors which initiate isolation.

314

~ ~

4.8.A AND 4.8.B BASES The surveillance requirements given under Specification 4.8.A and 4.8.B provide assurance that liquid and gaseous wastes are properly controlled and monitored during any release of radio-active materials in the liquid and gaseous effluents. These surveillance requirements provide the data for the licensee and the Commi'ssion to evaluate the station's performance relative to radioactive wastes released to the environment. Reports on the quantities of radioactive materials released in effluents shall be furnished to the Commission on the basis of Section 6 of these technical specifications. On the basis of such reports and any additional information the Commission may obtain from time to time require the licensee to take such actions as the Commission deems appropriate.

3.8.E and 4.8.E BASES The objective of this specification is to assure that leakage from byproduct, 'source, and special nuclear radioactive material sources does not exceed allowable limits.

6 0 AON I N I STj'(ATIVK C:ONTROLS (b) ~ Annual 0 eratinp Re oct A tabulation on an annual. oasis- of the number of s trl tion, utility and other personnel (includinq contractor") receiving exposures greater than 100 mremJ'yr and their associated man rem exposure according to work and job

~, functions,'.g., reactor operations and surveillance, inservice inspection, routine maintenance, special aiaintenance (describe maintenance), waste processing, and refueling.

The 'dose assignment to various duty functions may be e. timate" 'based,on pocket dosimeter, TLD, or film badge measurements. Small

.xposure 'otalling less than 204 of the

~ ind'vidual total dose need not be accounted for In the aggregate, at least 80% of the

~

total whole body dose received from external sources shall oe assigned to speci fic major work functions.

c. monthly 0 erati n< Re ort. Routine reports of ope" acing statistics and shutdown experience shall be submitted on a monthly basis to the Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, washinqton, C.C. 20555, with a copy to the appropriate Regional Of,ice, to be submitted no later than the tenth of each month following the calendar month covered by the report A narrative summary of operati>>g experic>>ce sigil be submitted in the above schedule.

Any changes to the Offsite Dose Calculation Manual of Spccii:ication 6.10 shall be submitted with the Monthly Operating Report within 90 days in which the change(s) was made effective.

381

4 0 hl)tsINISTRATIVK CONTROLS

d. Radiolovical Env9.ronmental Nonitorin 3.'. TVA shall prepare a report cn" tied "Environ=ental R~dio-activity Levels - Brouas Ferry Nuclear Plant - Annual Report."

Tne rcport shall cover the previous 12 months of oper ticn and shall'be submitted to the Director of the ETC Region II Of fice (with a copy to the Director, Of fice of Nuclear Reactor Regulation) uithm 120 days af ter January 1 of each year.

The rcport format shoMn in Regulatory Guid>> C.S Title l shall be used. The 'report shall include cummacics, interpretat'ons.

and evaluations of the results of the raJiolo cital environmental surveillance activities for the rcport period, including a comparison with preoperational studies and/or operational controls (as'appropriate), and an assessment of the observed impacts of thc plant operation on xhc environment. lf harmful effects or evidence of irreversible damage arc detected by the monitoring, the liceasee shall provide an analysis of th problem and a proposed course of action to alleviate

,the problem.

2. Results of all radiological environmental camples taken shall be summarized and tabulated on an annual basis. In the event that some results are not available within thc 120-day period, the report shall be submitted notini. and explain@,ing the reasons for the missing results. Thc missing data shall.

be submitted as soon as possible ia a supplementary rcport.

2. Reportable Occurrences Report able occurrences, includ'q corrective act ions and measures to prevent reoccurr ~nce, shall be reported to the Hf(C. Supplemental reports nay be required to fully describe f inal resolution oi occurrence. Xn case oi corrected or supplemental report,">, a licensee event report shall be completed and reference shall be made to the oriqinal report date.

381 a

"'.O ApmNrSTry Try'. CONTROr.S (9) Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical spec'fications bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

Note: This item is intended to provide for reporting of potentially generic problems.

(10) The concentra tion o f radioactive ma teria 1

'in liquid effluents released to unrestricted areas exceeds the concentrations specified in 10 CFR Part 20, Appendix 8, Table XZ-,

Column 2 for radionuclides other than dissolved or entrained noble gases. Concentration of dissolged or entrained noble gases exceeds 2 x10 Ci/ml total activity.

(11) (a). The dose rate for noble gases equals or exceeds 500 mrem/yr to the total body or 3000 mrem/yr to the skin.

(b). The dose rate for all radioiodines, for all. radioactive materials in particular.

form, and for radionuclides other than noble gases with half lives greater than 8. days exceeds 1500 mrem/yr to any organ.

384

6.0 ADHXNXSTRATXVE CONTROLS T~hirt -o~aMrittso Reports. The'eportable occurrences di cussed below shalJ. be tne subject of written reports to the Director of the appropriate Regional Office w'hin thirty days of occurrence of the event. The written report shal'nclude, a a minimum, a completed cooy of a licensee event report form. Xnformation provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances

,surrounding the event..

(1) Reactor protection system or engineered safety feature instrument settings which are found -o be less conservative than those established by the technical speci" cations but wh'ch do not prevent the fulfillment of the func=ional requirements of affected systems.

(2) Conditions leading to operation in a degraded mode pexmitted by a limiting condi" ion, for operation ox'lant shutdown required by a limiting condition for operation.

Note: Routine surveillance testing',

iristrument calibration, or p evt.ntat'e.

maintenance which require system configurations as described in. items 2. b. (1) and 2 b. (2) need not ce reported excect whe test results themselves revea' cegraced tmode as describec above.

(3) Ohser'ved inadequacies in the imolementat'on of administrative or orocedural controls which threaten to cause reduction'of degree of redundancy provided in reactor protection systems or engineered safety feat ure systems.

Abnormal degradation of systems other than tho -e specified in item 2. a (3) above designed to contain radioactive material resulting from the fission process.

Note: Sealed sources or calibration sources are not included under this item. Leakage of valve packing or gaskets within the limits for identified. leakage set forth in technical specifications need not be reported under this item.

(5) An unplanned offsite xelease of 1) more than 1 curie of xadioactive ~>aterial in liquid effluents, 2} mote than 150 curies of noble gas in gaseous effluents, or 3) more than 0.05 cuxies of radioiodine in gaseous effluents.

The report of an unplanned offsit:e release of radioactive material shall include the following information:

l. -

A description of the event and equipment involved.

2, Cause(s) for,the unplanned release.

3. Actions taken to prevent recurrence.

4. Consequences of the unplanned release.

385

6. 0 ADMINISTRATIVE CONTROLS Anomalous Hcasuremencs -Radiolo ical Environmental Monitorin (1.) If, during any 12-month report period, a mcasirred devel of radio-dctivicy in any environmental medium other than those associated vith gaseous radioiodine releases cxcecds tca times chc control sta'tion value, a vritccn notification vill be submittr:d vichin onc veek advising the NRC of this cbndi.cion." This notification should include an evaluation of any relea e conditions, environ-mental factors, or other aspects necessary to c>plain the anomalous result.

r (2.) If, during any 12-nanna ra",orr period, n rnnaurnd 1ovnl of radioactivity in any environmerrcal medium other <han those associated vith gaseous radioiodine rclcasrs cxcceds four times thc control station value, a v:;itccn notification vill be submicccc v" thin 30 day" advis r.g the llRC oi =his condition.

This notifica ion should inclurle an cvelua jr n of any release

~

conditions, enviror.mental factors, or othe'r aspec-s necessary to explaia the anomalous rcsulcn (3.) If individual milk samples sho-'-'31 concentrations of 10 picocurics p r 1>> tcr or greater, a pl ra s'>>'.i 1 ti<<submitted vithin 10 day" advising the hRC of chz p:oposed action to ensure the plant related annu" I doses vi}.1 be vithin thc dcsigu oh)ective of 15 mrem/yr~rcaccor to the thyroid of any ind'vidual.

(4.) If m lk samples collcc;ed over a calf "..;".: rluarcf..!. s .-.~ .verage~

concentrations of 6.0 picocuries per 1 tor or 'r,.".r;, a plan shall be submitted vic..in 30 days advi!:in'cnu Nf'.C o action co ensure thc plant-rela ere .,n..uaa dose vill chi'roposed bc v'thin che design ob)ective of l5 rfr:cm/yr/rcacr.iir ro rhc thyroid of any individua'.

+In the case of a trncativcly anomalous va luc f or ac ios c" ontium. <<-i conii~scory rcanalysi o. the origin-l, cuplic t c or a acv sainpic may bc dcsirabl Ir, tn s resu'.

~

ins aircc the the conf ir~co ry a;1aa 1V5 n S Se a b.

t ime consiscen vt.tl: ch<<a.".a lys'>>, and Xf Ceie hi ga V 2!u . -,.1:,, c';,e r;rinrt to t. e

~

hRC shall be submitr,cd vithin one veek folioving thi" a l!a lys is ~

(5) beIf such levels as discussed in 6.7.2.c.3 and 6.7.2.c.4 can definitely shovn to result from sources other than the Brovnr>> Ferry Nuclear Plant, the reporting action called f'r in 5.6.3(a)3 and 5.6.3(a)4 need not be taken. Justification for assigning high lcvcls of radioactivicy to ources othrgr than the Brovns Ferry Nuclear Plant must be provided ia the annual rcport.

385a

Uni ue Re ortin Re uirements A.. Radioactive Effluent Release Re ort A report on the radioactive discharges released from the site during the previous 6 months of operation shall be submitted to the Director of the Regional Office of Inspection and'nforcement within 60 days after January 1 and July 1 of each year. The report shall include a summary of the quantities oi radioactive liquid and gaseous effluents released and solid waste shipped from the plant as delineated in Regulatory Guide 1.21, Revision 1, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Mater-Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B thereof.

The report shall include a summary of the meterological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1, with data summarized on a quarterly basis following the

'ormat of Appendix 8 thereof. Calculated offsite dose to humans resulting from the release of effluents and their subsequent dispersion in the atmosphere shall be reported as recommended in Regulatory Guide 1.21, Revision 1. Doses to individuals outside the site boundary (UNRESTRICTED AREA) shall bd calculated in accordance with the ODCH.

B. Source Tests Results of required leak tests performed on sources i'he tests reveal the presence of 0.005 microcurie or more of removable contamination.

C ~ Snecial Re-"orts (in writing to the Direc'or of Regional Office -of Inspection and Enforcement) .

Reports on the following area" shall be submitted as noted:

a. S~.'con iary Containm~nt 4 ~ 7.C Within 90 Leak Rate Testing(5) days oE completion oi each test.

b. Fatigue Usage 6.6 Annu al Fvaluation Operating Report 386

6o0 ADHXNISTRATEVE CONTROLS

2. Prepare and submit to the Commission within 30 days, a Special Report which identifies the cause{s) for exceeding TllE LIMIT{s) and defines the corrective action(s) to be taken to reduce the releases of radioactive material in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose or dose commitment to an individual from such releases during these four calendai quarters is within 3 mrem to tlie total body and 10 mrcm to any organ. This Special Report shall also include:

(1) the results .of radiological analyses of the drinking vater sources (if applidable), and (2) the radiological impact on finished drinking water supplies with regard to t'e requirements of 40 CFR 141, Safe Drinking Mater Act. (Applicable only if drinking water supply is taken from the receiving water body.) See item 6 below.

3 ~

Prepare and submit to the Commission within 30 days, a Special Report which includes the following information:

a. Identification of equipment of subsystems not OPERAl3LE and the reason for nonoperability.

b. Action(s) taken to restore the non operable equip-ment to OPERABLE status.

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

4, Prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases of radioiodines, radioactive materials in particulate Eorm, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents during the. remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose or do'se commitment to an individual from such releases during these four calendar quarters is vithin 15 mrem to any organ. See item 6 belov.

Prepare <<nd submit to the Commission vithin 30 days, a Special Report vhich identifies the cause(s) for exceeding the limit(s) an1 systcas are being chlorinated., samples viU. bc taken daily frow the RC4'ystem+ and analyzed for chlorine residual. Records of thc daily sa~ling and analyses vill be naintained and submitted to the NRC staff fo" their revicv foUoving thc end of the special study period.

Chlorine feed rate and cauivalent RCM concentration vill be reported for he special studi cs period.

Sarpling during the special study period vill be consid red to satisQ the zLcnitoring requirecen s of Section 2.2.2 qf the cnvironr ntal technical sp~cific tions.

DEI.ETED

.0 ADMINISTRATIVE COllTROLS Ob!ce!.I I.

Thi section describes thc adninistrative and nanagercnt cont".ols established to provide cont'nuing protect on to the environment and to irplc<-ent the environ<a ntal tcchnical spec'ications. Measures to be specified in this sec ion include the assignmcnt of rcsponsibili.ies, organiiatipnal structure, operating procedures, rcvicv znd audi func <ons, end reporting requirements.

S ecificetions 5.1.1 Thc pover plant superintendent hes responsibility for operating thc plant vithin the lisd.ting conditions for operation (LCO).

5.1.2 The Director, Division of Environ=ental Planning, is responsible for the "environment<2. monitoring program outside the plant.

5. 2 Orr,"".' ation 5.2.1 The organic,ation of TVA management vhich directly relate" to operation of thc pic".. is shovn on Figure $ .2-1.
522 The principal divisions vithin TVA vhich are concerned vith environ-r<ental matters rcl"tcd to nuclear pover plant oper" ion ere thc Division of Pover Production (DPP), Division of Forest=y, Fisheries, and Uildlife Develop...cnt (Fr<<lD), Division of Pover Resource Planning (DPRP), and the Division of Environmentel Planning (DEP). The DPP and DPRP are in the Office of Pover. The Office of'Pover Quality Assurance and Audit 5taff is c sp ciel staff vithin the Office of Pover. Th Office of Pover, DiP, and FI r.'D rcppr to the General Jhnagcr. Thi" is depicted in Figu"e 5.2-2; 5.3 Revicv znd Audit
5. 3.1 The Directo, DEP, is'csponsiblc for reviev of'lcnt operation related. to KO to insure tha plant opere ion is heir." conducted vithin thc 1'ts defined in Section 2 of this doc<" nt.
532 The Office of Ppver Quality Assurance cnd Audit Staff shcU. conduct a periodic aud't of the environ=ental mpr itprir~ prod.~. ct least once per calendar year.
5o ao 3 The DPRP and/or DEP she'1 reviev znd con""'bute to thc folio;~-.g items:
a. Prepar.-'pn of the p oposed, environ=ental technical spc ificct<or Coord'.n t ion of envirpr=enteZ technical speci f jcat< pn dcvelp-- .
vith t.",'efety technical speci.ications to avoid conflict naintein corsistency.
C~ Propo" ed changes to the environ"entzl techni<eel specifications end the evaluated i=pact of thc ch nge.
d. Proposed written procedure, as described in Section 5.5 and proposed changes thereto which could significantly affect the plant ' cnv'ron=cntal impact.
c. Propos d change or '~odifications to plant systems or equipment vhich could significantly affect the plant's environmental impact and the evaluated impact of the change".
Results of the environmental monitoring programs prior to their submit al in each Annual Operating Report. Scc Sections.5.6.1 and 5.6.2.
Reported in.,tanccs of violations of environmental technical specifications. Vherc investigation indicates, evaluation and formulation of recommendations to prevent recurrence.
Act ion to be Taken if an Znviroturcntal LCO is Exceeded 5.4.1 Follow any remedial action permitted by the technical specifications until th condition can be met.
5.4.2 DEP vill conduct an independent investi'gation of the incident.
This investigation shall consist of the circumstances leading to and resulting from the situation together with recommendations to prevert a recurrence. The results of the investigation shall be reported to the Director, DPP.
5.4.3 Notification of the Director of the Regional Regulatory Operations Office, Pegion XX of NRC within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months shall be made as specified in Scc'tion 5.6.3, Reporting r'equirements for this paragraph ar' described in Section 5.6.3.
5.5 Procedures 5.5 ~ l Detailed crittcn procedu=es for the in-plant nonrad'ological monitoring program, including cheer-off I
lists, where applicable, shall be prepared Sy DPP and app".ovcd by the, plan superintendent (or his designee) and adhered to.
5.5.3 All procedure" de cribed in Section 5 5.1 and all changes thereto shall be revicved and approved prior to implementation and on an ammu~ basis thc caf tcr by the pl nt nanag~ent. Temporary changes to procedures vhich do not change the intent of the original procedure nay be vade, provided sucn cha-..ges are doc~==d xa6 a e approved by tvo of the.
folloving plant persoa~lr Superintendent Assistant Superintend Operations Supervisor Assistant Operations Supervisor Shift Engineer 5.6 Reooztin peouirccents 5.6.1 A rc or" sha11. be prepared by DEP ard cub-ittcd to DPP fo11oMicg the end of each 12-oontn period oi ope . ~, vhi& xM1 s~r results of .the nonradioiogical env~ caaentaL monitoring program m the 5.6. 2 Rou tine R" or(in a~ A summary report shall be prepared for both the inplant monitoring .prqgram .and the nonradiological monitoring progrnns and submitted to the Director of Division of Operating Reactors, AC, as part of the Annual Dperating Rcport vithin 120 days a ter December 31 of each year.
I
<<22 5.6.3 '.<ton-Routine Reports Nonradiolouical a ~ In the .event a limiting condition for operation is exceeded or an unu ual event with a potential for a significant envirocmental.
impact occurs, a repo c sha3.1 be made within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone or telegraph ca the Director of the Regiona3. Office of Inspection and Enforcement, Region II, followed by a written report vithin 10 days to the Director of the Regional Office of Inspection and Enforcement, Region X3'cony to the Director of Division of Operating Reactors).
Chant.es
1. Vherc a change to the plant design, the plant operation, or co proccdurcs is planned ~hich could have a significant adverse effect on the environment or which involves in environmental natter or .question not previously. reviewed and evaluated by the hRC, a request for the change sha31 be made to the NRC before imp3.cmencation.
2. Changes or add'tions to permits and cercific tes rcquircd for the protection of thc environment shall bc reported. @hen che requi ed changes are submitted to the coocewed agency for approval, they shall also be submitted to the Director, Dii~ision of Opera, ting Reactors, USHRC, for inform:ation.
3. gcquests for- changes in environ"eatal technical specifications shal3. be submitted to th'e Direcror, Division of Operating Reactors, US!<~C, for prior review and authorization.
5.7 Znriror .en a Records
.5.7.1 Operational information concerning the icplanc portion of chc cnviron-men al cechr <cal spec f ications shall bz kepi by DPP in a manner convcn'ent for rcv'ew, This includes plant records and<j'or logs as ind ica tcd be'w'.
a. Re'ated plant operations b, Related maintenance activities
c. LCO violacion
d. Updated, corrected, and as-built drawings of chc p3.ant Item (a) thi'ough (c) above shall'be retained for a period of at 1 six year and ice- (d) shall be retained for che 3.fe of
5.7.2 Records and/or logs ahall be maintained by DEP and(or DWH in a manner convenient fo" rcvicM. Tnis information concerning he environmental, onitorinp, program 's indicated below':
a. Checks, inspections, tests, and calibra ion of components and systems
b. principal maintenance activities associated with envixonmentM conitorS.ng equipment and sys ems.
c. 'Result'" of environmental monitoring surveys related to BFhP.
Xtcrns (a) and (b) shall be retained for a period of at least six y ar and item (c) shall be retained for the life of the plant.
Sources- of A:;cd C.".~=.icals end Rceultinr E"..d Prcduct Chc".<cela Maxim'e ultinS a ical i~'.~zixur. l'astc End End Product 8 stem Che MddC, Source Chc".ical Annuel i:sc Proauct Chc..ical Annua3:
lbs V.ean lbs Dailj Mslceup Mater Treatc:cnt Alm b Flaunt A12(SO! ) 18 H20 15,600 Al(ON)' 3,700 50i 6,8no Suspended solids 13i500 Soda Ash Na2 CO3 (100$ ) 7>900 Na 3,500
+
5odiujs 3i950 Na 260 Hypochloritc NaOC1. (21$ Solution) - OCl 570 Coegd.ation Aid. 590 Cong. Aid 590 Hakcup vatcr Sulfuric Acid 98~~ 270,000 SO)) 259s000 ~710 Trcatnent Plant Decincrali".cr Rcgcncration Sodi~ Hydroxide (50'). 205,000 598000 Auxiliary Stean Asrionia Variable d NH3 Generator Blovdovn Pgdr ax ino Yariable =-
lG!3 0.4 <0,001 Rav cooling vatcr Chlorine Yariablo OC1 and Cl Va"iable 1 i 620 Systea
a. 2ascd on 24-horn operation 365 days/ycer a. denonstra ed moxii~ujs capacity of equip@ nt b, Cuspended oatcriels that vill nake up the vatcr treatrcnt plant sludge, on aidry vciglt basis,
c. Estirat.cs frow suspended so].ido data ob"crvcd at T?-'1 300.3,
>~mnia vill bc eddcd as nccdcd to keep pH of systcn at 9.0.
e, Hydrazine vill be added as nccded as a DO ocavcnSer.
Table 3.1.2-2 SKPJBY Or CRB~ICA~ DISCl!ARGS Mast" b s.
6'.Xicr~e. Produr t Obscrv.d Total
~"anual Chemical Concentrations in Concentrations c xihx i?MS Discharg Contribution Reservoir Mater in River Allovab1e of Product, to Discharge at TRH 300.3 After 'Mixing Concentrations Vc.ste Product Chenical Concentrations rar/1 nr /1 in River Cher.:i cal lb mp/1 Avcrcrc i'mitch> ~Aveea e !'err!nun Sulfates 265,000 0. 031 15. 0 23. 0 15.027 23.027 250 (SO4 )
Sod! ua 62,700 0. 007 5.92 9..18 5.9263 9a1863
( +)
~ r Chlorides e 34,600 o.o68 14.0 21.0 14.060 21.060 250 A..-~on i a f nil 0. 02 0. 07 0.02 0.07 ill!
Total Dissolved 363,lo6 0.106 104.0 129.0 104.093 129.093 500 Solids aa Based on 24-hour operation. 365 days per yecr at demonstrated maxiraum capacity of equipment and chemical requirements.
b. Disc! arge flo>> based on 3-unit operation.
c. Concentrations basci!3on doMnstrcam riverflov of',000 ft /s. ~ Hovever, heat dissipation considerations will require reinisiua of 23,000 ft /s for open node.
d. No rpccific standard has been identified but contribution to dissolved solids has been included.
e. Co~potation is for chlorides since the chlorine demand of hc cooling uater is such that no residual chlorine vill be dischnrgcd. Chlorides and total dissolved solids reflect naxirrsss daily usc of chlorine in re coolinp vatcr.
knonia aid hydraiinc added to auxiliary steno generator for pH and dissolvod o ygcn 'control. Hydrazine conservati'cly ossuiic4 Lo decompose to arsnonia.
g. Alabama "<<ter I=pron ~cnt ".mmission Stress'tandards.
olodlAAY oC I.'Cloddy,ololoolcAL Y~OYITOO I~IC >co~llA nIIO.,VS Pf~ny )mCfpe Pr,yg Zooplankton> Chlorophyll Fro4uctfvfty Benthic 6tatfon %'stet 8:nf>les an~4P!i to~plankton G~c~ 1fng Vcn:nccncnlc Fnnnn ncdlncnd Ylcl>
Sccori C: cek "-b:)=eat Station 277.9S 283.9!> X Elk Afvcr Mba)~ent 6tatfon X 200.76 x" 29l.76 X 293.70 Xb X ~
295.S7 299.00
. 30fc06 307,52 X - In4fCatC>I at 1Ca:t Onc >luartCrly OesplC COllCCtCIf at %ho epCCif'JC4 ataWOn>
a. I fsh se~plfng ct a cpccfffc statfon vill bc by c'ithcr gill nct, traf> nct, rotc>noneI or clcctro."fshfnc. floucvcr>
Ccpcn4fnd-, upon the o~plfng ~ctbodf thc frcqucncy of sac:.pliny at each loCatfon wcv bo.lcs; than cuartcrly
b. A>alysfs <<Dfssolvc4 o.:yccn an4 tcmpcraturcd Cd inc!ysis - Dfscolvcll oxygen> tcn>pcraturc POD, COD,,I, alkQLnf',y> epccftfa conductance> Ra> 0I, cblorf4cc>
nf trc"cns (I.'It)>,I:02+Il0)> nn>'rcanfc) nn4 c if>Is (8'acolvc4> su)pcndcdfI an4 to'Lal)>
A1NE!i$ w'~b
~.'.:.P:~~. ~,-'.g
( cxzxzoi"sz'. MCUS~%'IUlLN1>LLiQXX'"J
. DRO<'ifJS I Ef<BY HUCLI'.IIH l'l..tII)l':~i<gi.
~ J f
El EXlSTlHG TEI!PERATURE MOHITOR F)gure 2. 1-1
.o" '
MONITORING LOCATIONS iV)SEELEH RESERVOIR I
~ )J'y I)~ g
~ ~
~
~
SCaLt$ OI'H'Ii.ES
HAVAGER OF POWER DIVISION OF POWER PRODUCTION CHIEF, NUCLEAR GENERATION BRANCH NUCLEAR PLAHTS BROWNS FERRY NUCLEAR PLANT TVA Office of Power Organizat'ion for Operation of Huclea' p)ants Figure 52-J
BOARD Cf DIRECTORS OFFICE OF THE GirNEUL H".!AGER At'DIT STAFF IttFOPHATION OFFICE UASHII!GTOtt OFF ICE EQlAL D!PLOYHENT OPPORTUNITY STAFf DIVISIO!t OF OI Yl 5 IO(t OF OIYISIO!c 'IVISION OF OF 01 VIS ION OF LAND BET"rD LAV PEPSCtulEL FIN dtCE PURC! IAS I!!G PRO?ERTY AND SERVICES THE LAKES 0 I V !5 ION OF OFFIC'E OF OFFICE OF POUER OFFICE OF 01 Y ISIOH OFFICE OF VATER ENGII!EERItiG DESIG't AGRICULTURAL AHD OF TRIBUTARY 01 V I 5 IOUS:
HA!taliEHEHT -
AND CO!ISTI!JCTION Ct!EHICAL OEVELOPHENT HEOICAL ARiA PO'itER RESOURCE PLN!NING SERVICE5 DEVELOPILrh7 Dl VIS IONS:
TIVJISMISSION Plhll!IIHG 0 1 Yl5 I ON 5:
Et!GINEERING DrS IGN Att0 ENGINE'ERING AGRICULTURAL OEYELOPHEHT DIYISION OF CONSTRUCTION PStER CONSTRUCTION CHEHICAI. DEVELOrHEHT, DIVISION DIVISION OF NAVISION, POls'ER PRODUCT IOH CHEHICAL OP ERAT IO!iS OF FORESTRT, OEVELOPH ttT- PO'4eR SYSTEH 0?ERATIO!IS EHY I RONHEt{TAL FISHERIES, ANO REGIONAL PstER UTILITAT IOtt PLANNIHG AND HILOLIFE UOI rS DFVELOP'HirNT STAFFS:
tlUALITY ASSURANCE AND AUDIT STAFF NUCLEAR SAFETY REVIEM BOARD BRINNS FERRY HUCLEAR PLANT PO'PER RESEARCH STAFf Orttentxatlon ef the Tennessee Valley Authortty FIGure 5~ 2-2
UNIT 2 7o demons rate the adcauacy.of veekly sampling of chlorine residuQ durin chlor'naton of the aaxiliary rev cooling vater oysters by demonstrating that, cnlorxne reszdu"1 xn aux" ary rzv cooling vater (RCd) sys ems re~a ns relatively con" tant d~ang chlorination.
SDecl f3.cQ.tion TYA villand,perform special studies during the fiist tvo p a fall period) of chlorination of the RCU riods (including a rpring systems after SeptexLb r 19/5, vhicb are of at 3.cast 3 vee'-s'uration. During the special studies period vhen the RCU systca~ are being chlorinated,, samples viU. bc taken daily frow the RC'W systems and'nalyzed for chlorin residual. Records of the daily sampling and analyses vill be naintained and su~tted to the NRC staff for their revicv fo13oving the end of the special study period.
Ch3.orine feed rate and eauivalent RCW concentration ~wll be reported for the special studies per'od.
Sarp3.ing during the special study period vill be considered to satisi3, the mc.".itoring requirements of Section 2.2.2 qf the environs nta3. technic@.
sp>ci fications ~
4.2 Radiolo ical Environmental Monitorin Pro ram DELETED
.0 ADMENLUSTRATIVE COltTRO[B Ob!act.lve Thi section descr"ocs thc administrative and manager:cnt controls established to provide contnu'ng protect on to the environment and to implcaent the environmental tcchnical spec'ication . Measures to 'be pecifi'ed in this section include the assicnncnt of responsibilities, organizational structure, operating procedures, rcvi v -nd aud't func".ions, and reporting requircmients.
S ecifications 5.3. Rcsnonsibi3.itv 5.l.l The pover plant superintendent has responsibility for operating the vithin the limiting conditions for operation (LCO). '3.ant 5,3..2 The Director, Division of'nviron=ental Planning, is responsible for the environmental'onitoring program outside 'the plant.
5, 2 Orr, ".i sat i on 5.2.l The organization of TVA management vhich directly relate to operation of the pie".. is shovn on Figure 5.2-l.
522 The principal divisions vithin TVA vhich ale concerned vith environ-mental matters related to nuclear povcr plant opera ion ere the Division of Pover Production (DPP), Division of Forestry, Fisheries, and 51ildlife Develop."..cnt (Fr>B), Division of,Pover Resource Plennirg (DPRP), and the Division of Environmental Planning (DZP). The DPP and DPRP are in the Office of Pover. The Office of Pover Qua3.ity Assurance and Audit 5taff is a sp cial staff vithin tbe Office of Pover. Th Office of Pover, DiP, and Fsv.'O rcpor to the General
~
Manager. This is depicted in Figu"e 5.2-2.
5,3 Reviev and Aud.it 5,3.l The Director, DEP, is rcspons'blc for reviev of plant operation rclat d to KO to insure tha plant opera.ion is 'bc'ng condu"ted vithin thc 3.i+its defined. in Section 2 of t?is docu"ent.
'.32 Xhc Office of Pover Quality Assurance and Audit Staff shall conduct a periodic audit of the environ=ental @or itorir~ pro~~a=. at least once per calendar year.
5 3 3
~ ~
The D?R> and/or DE~ "Na'~ reviev and con'r'bute to the foU.o.~-g items:
do Prepar t'on of the proposed engram.="ental t chnical spccificntior-.
Coord'.-.'."ion of cnviror-estab technical specification deyelo vith th" safety technical spocifications to avoid conflie " a".d maintain cor s i s te ncy.
c. Propo"ed changes to th>> enxCron=en 1 technical specifications the evaluated i=pact of thc change.
d. Proposed written procedures, as described in Section 5.5 and proposed changes thezeeo vhich could significantly affect the plant ' env'on=ental impact.
c. Proposed changes or modifications to, plant systems or cquipmene which could signif'cantly affect the plant's enviror~entaL impact and the evaluated impact of the changes.
Pesults of the environmental monitoring programs prior to their ubmit"'al in each Annual Operating Report. See Seceions.5.6.1 and 5.6.2.
Reported instances of violations of environmental technical specifications. Where investigation indicates, evaluation and formulation of recommendations to prevent recurrence.
5,! Action to be Taken if an Environmental lCO is Exceeded 5.4.1 Follov any remedial action permitted by the techni'cal specifications until the. condition can be met.
5.4.2 DEP wil1 conduct an independent investi'gation of the incident.
This investigation shall consist of the circumstances leading to and resuleing from the sieuation together with recommendations..
to prever.t a recurrence. The results of the investigation sha'1 be'reported to the Director, DPP.
5.4.3 Notification of the Director of the Regional Regulatory Operations Office, Pegion XX of NRC within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months shall be made as specified in Section 5.6.3. Reporting requirements for this paiagraph are described in Section 5.6.3.
5.5 Procedures 5.5. 1 De ailed xr t ten p.ocedu es for the in-plant no..zad'ol og cal monitoring p ogzan, includ ng check-of" lists, where applicable, shall be prepared
$ y Dpp ann happ ov.d by t the plant superintendent (or hiss des es x,knee)) and adhered to.
5.5.3 All procedures described in Section 5.5.1 and all changes thereto shall be revicved and pprov d prior to implementation and on an armuQ basis thcrcaL'ter by the plant '~nag~ent. ~porary'hanges to procedures which do not change the intent of the original procedure nay be vade, rovidcd such cha-..ges are she -=> m6 a e approved by tvo of the folloving plant per~l:
Superintendent A"sis tan t
'Supervisor Super'perations Assistant Operations Supervisor Shif t Engineer 5.6 Report in Requirements 3 6.3.
end of each 12-aoncn period oi cree . 'w ~ ~ ~Hm A repor" shal3. be prepa ec by DEP ard sub-itted to DP fojJowing the results 'of . the nonradiological env=~onmental monitoring program.
the 5.6.2 Routine Reoorcinc, a~ A summary report shall be prepared for both the inplant monitoring .program .and the nonradiological mozd.toring progr~ and submitted to the Director of Division of Operating AC, as part oz the Annual Operating vithin 120 days after December 31 of each year.
Reactors,'eport
5.6.3 Non-Routine Reports NonraC iol o~ical a ~ Xn the event a linfting condition for operation is exceeded or an unusual event ui,th a potential for a significant enviro~ental epact occur, a rcport shall be made within 21~ hours by telephone or telegraph to the Director of the Regional Office of Inspection and Enforcement, Region ZI, folio'~ed by a mitten report within 10 days to the Director of the Regional Office of Inspection and Enforcement, Region II (copy to the Director of'ivision of Operating Reactors).
Ch lopes
l. Vnere a change to the plant design, the plant operat foie, or to procedures is planned vhich could have a significant adverse effect on the enviro~ent or'w'hich involves in environmental natter or .question not previously.reviewed and evaluated by the NRC, a request for the change sha]1 be made to the NRC be f ore impleaenta t ion.
2. Charg'es or additions to permits and certific-"te required for the protection of the env tronmen t hall bc repor ted. Men the required changes are subm'tted. to the coocerned agency for approval, they shall also be subnitted to the Director, Division of Operating Reactors, US!QC, for inforcation.
3. Requests for changes in environ"ental technical specif" cations shal'e submitted to the Director, Division of Operating Pcactors, USURC, for prio revimc and uthorization.
5. 7 Znviror=.en 'ecord s 5,7.1 Operational information concerning the icplant portion of thc environ-mental terhr 'cal spec'fications shall be kept by DPP in a manner.
ccrven'ert for rev'ei, This &eludes plant records and/or logs as indicated belou:
a. Related plant operations
b. Related naintenancc activities
c. LCO viol,"cion
d. Updated, 'corrected, and as-built drauings of thc pl (a) through (c) ab..ve shall be retained'or a period of t le eined .or thc 1ife of thc \ I ~
5.7.2 Recozds and/or logs ahall be maintained by DEP and(or DMH ia a manner conveni nt fo" rcv/eM. Tnis information concerning 'the environmental one toring progzam is indicated below':
n. Checks, inspections, tests, and calibra ion of components and sys tems.
b ~ Principal ~intenance activities associated with environmentM monitoring equip=ent and systems.
c. 'Result'" of enviro~ental monitoring surveys related to BFhP.
Items (a) and (b) ohall be retained for a period of at least six year and item (c) ahall be retained for the life of the plant.
Sources of S. lc<')'.c..icals cnd Rceultinc End Prcduct Ch ".iccls ll&ximn Resulting a Cl:e" ical Nazi.:ur. i'ante End End Product Annucl l'.ean Daily
~)st em Added Source Chc .ical Annual l. 5 e Product Chc..ical lbs lbs Makeup Mater Treatrcnt Alter Plant Al (SO4)3 18 H20 15,800 Al(0!I) 3)700 3
Soi 6,8oo
')c Suspended solids. 13,500 '437 Soda Ash Na2 C03 (1005) 7)900 Na 3) iJOO
+
Sodiun 3)950 Na 26o llypocl)lorite Naocl (21$ Solution) OC1 570 Coe~lation Aid 590 Co~. Aid 590 Ha>eup vatcr Sulfuric Acid 98~~ 270,000 SOJ, 259)000 ~710 Treatc.ent Plant Denincrali er Rcgcncration Sodi~ Hydroxide (5o'). 205,000 59,000 ~160 Auxiliary Stean As@ionia Verieble liH3 6 ~0. 02 Generator Blovdovn P~draxino Variable lfl)3 0.4 ~0.001 Rav cooling vater Chlorine Variablo -
OC1 and Cl Variable . 1,620 SJI'stet)
a. 2ascd on 24-hour operation 365 days/year a. herons.ra.ed moxii~un cepac5.ty of equip@ nt.
Cuspcnded a tcriels that vill nake up the va cr treatr cnt plant slud)".c) on a)dry vciglt be"ia.
e. Estimates fron suspended solids data observed at T?-'J 300.3.
PJ)ionia vill be added as nccdcd to keep pH of systcn at 9.0.
e, Hydrazine vill be added as needed as a DO acavcnSer.
Table 3 l. 2-2 SU!!JBY OF CIIB~ZCAL DISCIIAIIG S Vast" b Produc t, Obsc..r v".d Total c
~nual Chcioiccl Conccntraticno in Concentrations ~ibmirm8 Dischorg Contribution Reservoir Mater in IIivcr Allovable of Product to Discharge at TIII4 300.3 ~
After i~!ixing Concentrations Vestc Product Cherd.cal Conccntratzons r:r./1 rn! /i in River Cher.:I col lb ru./1 Avcrarc I'mir.:ua ~Avcra c !'oxiraN!
Sulfates 265,800 0.031 15.0 '3.0 15.027 23.027 250 (so Sodju~ 62,700 0. 007 5.92 9.18 5.9263 9.1853 (i:=+)
e Chlorioes 34,6oo 0.068 lb.0 21.0 lb.060 21.060 250 t, ~on ja f 6.4 nil '0. 02 0,07 0.02 0.07 i%I!
Tote.l Dissolved. 363,106 0.106 104.0 129.0 104.093 129.093 500 Solids
a. Baaed oo 24-hour operation 365 deya pcr yec.r at demonstrated rmximun capacity of equipaent and chemical requirements.
b.'ischarga flcrrs based on 3-unj.t operation.
c. Concentration bascd3on dounstrcom riverflov of 5,000 ft /o. Ijovever, heat dissipation conaiderationa ~ill require r.inij".ua of 23,000 ft /s for open rode'.
elf ic standard has been idcntj.fied but contribution to dissolved solids hao been included.
Cownutrc,ion io for chlorides since thc chlorine demand of hc cooling eater ia such that no residual chlorine >ill No Gp be dischorgcd. Chlorides ond Cotal di oolvcd solids reflect vaxinaas daily uac of chlorine in ram cooljnp eater.
conservative>y
f. tu-..ionia u>d hydrazine added to auxiliary steal generator for p11 ond dio"olvad o~gcn 'control. Hydrazine o" usicd to dccoi!ipooc to armoni.a.
g. Alabcxo "uter T.=pros~ant ",mniaaion Stream Standards.
c siltieY N ):0:rl.,MourzC~t, Y~a'llypll i~<4 pCC~nb.
BIO".IIS'FfTtflY lNCiI'.All Pf.Qfg Zooplarf.ton, Chlorophyll Fr oduc tiv i ty. Benthic Station ~'ates Sar.'plea rn~dph toplank<on G~mling Vcueure>santa Fauna 'uc4ieent 3'I.sh
IC>
Seeori Creek Z-bey=eat Station 2l7.9S X 283;9I X Elk River Nba)~ent Gtation X 200.76 X 291.7 Is X X 293.70 x' X ~ X. X
.295.07 X 299.00 301,06 307 52 X - In4fcatco at 1ca:t ono qua'tcrly aassplc collcctc4 at the epccific~l 04tf oq<
a, Pish sa."..pliny at a apccific station sii)l bc by cithc?'lD hot, tralI nct> rotcIIOILCI OV Clcctro."iohirQ ]lou(VCr>
depending upon thc a~pliny nctho4 thc frequency of aceplinG at oach lcCation Iscv bC 1cs than ouartc."ly
b. Aiclysis - Dis:olvcd o.':yGcn an4 tc~pcraturc ~
c lnalysis - Dis olve4 oxygen, tca~pcrctuLc 20D C0Dp Is aBQLni;y, cpccitia con4uctancc, g
Hc., 0I,, chlorides~
nitre"ens (i.'II,,I'0>+I'0>~ an4 organic) and a lids (8'a:olvcL, suspcndc4I en4 totnlj>
EXlSTlHG TEh/j EBATURc b)OHITOR l>l " I ' (.Pl' I ~< "u" -Y~
f)gure 2.1-1 <'"..'S, MONITORING LOCATIONS iV13EELER BFSEB'lJ'OlR SCAL15 OP HllCf d>>
IC?ltFYI CX'C7 J 4
VANAGER OF. PO'tER DIVISION OF POWER PRODUCTIOtt CHIE,"-, NUCLEAR GENERATION BRANCH NUCLEAR PLANTS 8ROWNS FERRY NUCLEAR PLANT TVA Office oF Power Organization for Operation of 'tUclea." )lants fi'gure 5.2-$
BOARD OF DIRECTORS OFFICE OF THE Gr,!ERAL NAGGER AUDIT STAFF IHFOi~.'STION OFFICE kQHI'IGTOH OFF ICE EQ/AL Efl?t OYHEHT GP?CRTUHITY STAFF DIVISIG!I OF DIYISIC!I OF GIYISION OF DIYISIO'I Or DIYI SIGH OF LAND DEr;EEN LAY PERSCI:t!EL F IHi'd!CE PURCHAS I!IG PRG?ERTY YUiD SER" ICES THE LAKES DIVISIQI OF OFFICE OF OFFICE OF PCUER OFFICE OF DIVISION OFFICE OF VATER ENGIIIEERIIIG DUIG'I PLAYTHING 01 VISIONS: AGRICULTURAL AHO OF TRIBUTARY
!IAK'u EIGHT AND CO'ISTRJCT ION CIIEHICAL OEVELOPHEHT HEDICAL AREA PG'iIER RESOURCE PLAHHIHG DIVISIONS! DIVISIONS: SERVICES DEVELGPILrhT TRi'JISXISSIOM EHGIHEERIHG DESIGN NID EHGINEERIHG AGRICULTURAL DEV ELOPHENT DIVISION OF COHSTRUCTIOX POdrR CO'ISTRUCTIO'I CHEHICAL DEVELOrHEHT Dl Y I SIC!I OIY IS I OH OF NAYIG(I ION PGI'ER PRODUCT IGH CHDIICAL OPERATIC!IS FORESTRY, DEVELGPHEtIT POUrR SYSTEH 0?ERATIGHS EHYIRGHHENTAL FISHERIESi ANO REGIC'IAL PQI R UTIL12ATIGII P'.Nt,'I I HG AND IIILGLIFE S IUD I rS STAFFS: DEVELOPS!IT GUALITY ASSU!UUICE AHD AUDIT STAFF NUCLEAR SAFETY REVIEW GOARO 8RQ'lNS FERRY HUCLEAR PLAIT PO'~ER RESEAIICH STAFF Orgcnfza tfon of the Tennessee Valley Authorfty F'fgure 5.2-2
UNIT 3 0
S'0" c4 al S udice dcaon "rate thc adcnuacy of veel'ly a~D1xnG of chio"ine residual d~ing ch3o.ina 'on of the auxiliary rav cooling vater pystens by demonstrating that chlorine residual in aux'3.iary r v cooling vater (HCii) systems rema:ns rc3.ativc3.y constant dwwng chlorina'ion.
Soeci fication gVA vi3.1 p rforn special studies during the first tvo p riods (including a.
spr ng and a fall period) of chlorination of'he RCW systems after September 197$ vhich are of at least 3 veeks 'uration. During the special studies p
period vh n the RCU system.are being chlorinated, samples vi13. bc taken daily frow the RC'll system@ and analyzed for ch3orin residual. Records of thc daily s~ling and analyses vill be maintained and. submitted to the NRC staff for their revicv folloving the end of the special study period.
Chlorine feed rate and eauivalent QCM concentration ~>11 be reported for he special studies per'od.
Sorpling during th special study period vill be considered to satisfy the gc.-.itoring requirecents of Section 2.2.2 qf the cnvironr ntal tcchnicg.
sp~cifications.
DELETED
.O ADMIllISTPATIVECOllTROLS 0 b ! c c t ! 'I e Thi section describe thc a&nistrative and nanagercnt controls established to provide cont'nung protection to the cnvironr'ent and, to irplc<".ent the cnvfronsa n al tcchnical pecifications. l"lcasures to be specified in this sec ion include the as iCnacnt of rcsponsib'ities, organizational tructurc, operating procedures, rcviev "nd audi func -ions, and reporting requirements.
S ccifications 5
5.1.1 Thc pover plant superintendent has responsibi3ity for operating thc plant vithin the li<aiting conditions for operation (LCO).
5.3..2 The Director, Division of Environ"ental Planning, is responsible for the environment<J. monitoring program outside the plant.
5,2 Or<<~ .'"ation 5.2.1 The. organization of TVA r>>anageracnt vhich directly relates to operation of thc plant 's shovn on Figure 5.2-3..
5.2.2 The principa3. <'ivisions vithin TVA vhich are concerned vith environ-ncntal mat crs rel"tcd. to nuc3.car povcr plant oper ion ere the Division of Pover Production (DPP), Divis'on of Forest y, Fisheries, and hfildlife Develop.".. nt (FF>TD), Division of Pove. Resource Planning (DPRP), and the Division of Environmental Planning (DEP). Thc DPP and D. RP are in the Office of Pover. Thc Office of Pover Quality Assurance and Audit 5taff is a sp"ciel staff vithin the Office of Pover. Th Office of Pover, DiP, and Fi~:D rcpor to the General Manager. This is depicted in Figu e 5.2-2.
5.P Rer'e>>: and Audit propre=.
5.3.1 The Dirccto., DEP, is rc ponsiblc for rcviev of p ant operation related to LCO to in ure ti a plan operation is being condu"ted vithin t.he 1: its defined in Section 2 of th's docu=ent.
5.3 2 'Xhc Off:ce of Pover Quality Assurance and Audit -S a"f shel3. conduct a periodic aud>> t of thc environ= ntal d'or itorir~ at least once per calendar year.
5 Qo 3
~
DPRP and/o DEP sha' reviev and contr'b"tc to the folio; itc~s:
a. Preparat>>ion of the proposed environ"ental technical speci ficatior- .
Coord>>:".a~:i'on of cnviror"enteZ tcc"aice3. spe ifjcat>>on dcvelo vith t.".'afety technical spocifications to avoid conQicts e.d naintcin consistency.
c. Propo"cd changes to the environ=en al techni<ccl specifications thc evaluated i=pact of thc chang
d. Proposed written procedures, a described in Section 5.5 and proposed change- thereto which could significantly affect the plant' env'ron=ental. impact ~
c. Proposed changes or modifications to plant systems or equipment vhich could signif'cantly affect the plant's enviror~ental impact and the evaluated impact of the changes.
Pesults of the environmental monitoring programs prior to their ubmittal in each annual Operating Report. See Sections.5.6.l and 5.6.2.
Reported instances of violations of environmental tcchnical specifications. h'here investigatio'n indicates, evaluation and formulation of recoumendations to prevent recurrence.
if an A
Action to be Taken Envirorurental LCO is Exceeded 5.4.1 until ¹ Foilov any remedial action perraitted condition can be met.
by the technical specifications 5.4.2 DKP vill conduct an independent investigation of the incident.,
This investigation shall consist of the circumstances leading to and resulting from the situation together'with recommendations to prevent a recurrence. The results of the investigation shall be reported to the Director, DPP.
5.4.3 Notification of the Director of the Regional Regulatory Operations Office, Pegion XX of NRC within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months shall be made as specified i.. Section 5.6.3. Reporting requirements for this par'agraph are described in Sec tion 5.6.3.
5.5 Procedures Detaz~ed wri ten procedu"es for the in-plant nonradiological monitoring program, including check-of f lists, where applicable, shall be prepared Qy Dpp and app-.aved by the plan" cuperintcodent (or '
( r his'esignee) ) and
5.5.3 V3. rocedu'res described in Section 5.5;1. and all changes thereto uha11.
be revieved and approved prior to implancntation and on an annu~D basis thcreaf ter by the pl nt ~nag~cnt. Temporary changes to procedures which do not change the intent of the original procedure nay be made, rovided sucn chan".,es are M~-- M > a approved by re of the folloMing plant pe=sorwl=
Superintendent Assistant Superintende Operations Supervisor lwsistant Operations Supervisor Shift Engineer 5.6 Reoortin Peauirecenrs 5.6.1. A repor" shall be prepared by DEP a 2 sub-itted to DPP fo11oMicg the end of each 12-oontn period oi o7e.d~ +hi& iM. ~rLm the results of . tile nonradioiogical env~ onmenta monitoring program 5.6.2 Routine R oorcin A summary report shall be prepared for both the inplant monitoring program..and the nonradio1ogica1 monitoring progr~ and submitted to the Director of Division of Operating Reactors, hRC, zs part of the Annuai Operating Repo'rt vithin 120 davs after December 31 of each year.
5.6,3 Non-Routine Rcnorts Nonrnd ioloaical In thc event a liniting condition for operation is exceeded ox an unusual event with a potential for a significant enriro~ental epact occurs, n rcpo t shall bc made vithin 2~i hours by telephone or telegraph to thc Director of the Regional Office of Inspection and Enforcement, Region II, folio+ed by a mitten report within 10 days to the Director of the Regional Office of Inspection and Fnforceraent, Region I7'cony to the Director of Division of Operating Reactors).
Chanc:e s
l. 'Vhere a change to the plant design, the plant operatioii, or
'to procedures is planned vhich could have a significant adverse effect on the envirorment or vhich involves in environ~ental natter or .question not previously.revieved and evaluated by the NRC, a request for the change sha) 1 be made to the NRC be fore imp3.cementation.
2. Changes or add'tions to permits and certif c tes required for the protection of the environnent shall be reported. When thc required ch ages are subnitted to the concerned agency for approval, they shall also be subnitted to the Director, Division of Operating Reactors, USllRC, for inforcation.
3. Requests for changes in environ"ectal technical specifications sha].l be subnit ted to the Director, Division of Operating Reactor, US<<RC, for prio revie~ and authoriza tioa.
5 7 Fnvizor e~- 'eco ds 5,7.3. Operational infomation concerniag thc icplant portion of the environ-mental techr 'cal specifications shall bz kept by DPP in a canner ccrvcn'ent for review, This i"-eludes plant records and/or. logs as indicated helot:
a. Re'ated plant operations b, pelatcd maintenance activiti'es
c. LCO violation
d. Updated, corrected, and as-built d aiings of thc plant Iten (a) thiough (c) ab >v shall be retained for a period of (4) shallbe ret
5.7.2 Records and/or logs shall be maintained by DEP and/or DMN in a manner convenient for rcvicM. Tnis information concerning the environmental
=onitoring program is indicated below':
a. Checks, inspections, tests, and calibra ion of components and sys tems
b. Principal maintenance activities associated with environmenta1 monitoring equip=eat and systems.
C~ Result" of cnviro~ent'al monitoring surveys related to 3FhP.
Items (a) and (b) shall be retained for a period of >>at least six years and item (c) shall be retained for the liEc of thc plant.
3.1.2-1
- Sources of f. ;cd Chc.-.icals cnd Rcsultinr End wcduct Chc".<cela Resulting Che ical Added ii.Qz i:QLK; Annual Usc l'ante- End Product
'laxi~a End Product Annual.ean Daily S stem Source Chc .ical g Ch('.ical lbs lbs Hwteup Mater Treatc.cnt Alm Plant A ( o4) ~ 8 15,600 Al(OH) 3,700 3
SOi 6,800 Susp=rded solids. 13,500 Soda Ash Na2 C03 (100') 7,900 Na 3,F00 SodiuJa 3>950 Na 260 1iypochlorite NaOC1 (21$ Solution) OC1 570 CoegQ.ation Aid. 560 Co~, Aid Hakcup vater Sulfuric Acid 98~~ 270,000 SO)) 259,000 ~710 Treatment Plant Derincrcli cr RcScncration Sodi~ liydroxidc +
(50" ). 205,000 lia 59,000 Auxiliary Steoa Asrionia Yarieble NH3 ~0.02 Generator 31ovdovn P~drax inc Yariable Bl!3 0.4 ~0.001 Rav cooling vater Chlorine Varieblo- OC1 and Cl Variable 3.,620 System
a. Eased on 24-hour operation 365 days/year "a. Qeronstrrted mnxii~ua cepecity of equi~ant,,
b, Suspended s "tcric3.s that vill deke up the vatcr treatt"ent pscnt slud-e, on aid~ v vefght beis,
e. Estirat.cs from suspended solids data ob crvcd at T?-'1 300.3,
>n-..onia vill bc added as nccdcd to keep pH of sy tcn at 9.0.
e, hydrazine vill be added as nccded as a DO ocavenSer.
~ .
Table 3.1.2-2 SUrPJZY OF CIIB~ICA~ DlSCIIABC S b
Vast uz xinm~ Product Obscrv rd Total Ar.null Chemical Conccntraticns in Concentrations c ~ihxinuH Dischorp Contribution Reservoir Mater in River Allovablc of Product to Dischnr~e at TR!4 300.3 After i~!ixir.g Concentrations Vcs te Proiluct Chemical Concentrations r.-.r:/1 mp/1 in River Cher.ical lb mp,/1 Average i"mimum ~kvara a Voxinun l Sulfates 265,000 0. 031 15. 0 23. 0 15.027 23.027 250 (SO4 Sodiu 1 62,700 0.007 5. 92 9..18 5.9263 9.1S53
(
~~
+)
Chloriocs e 34,600 0.066 14.0 21.0 14.060 21.060 . 250 I
A-...~oni a 6.4 0. 02 0. 07 0.02 0.07 Vl I
ilif'3 Tota1 Dissolved 363,106 0.3.06 104. 0 129. 0 104.093 129.093 500 Solids a., Baaed oa 24-hour operation 365 daya per yecr at demonstrated maximum capacity of equipment and chemical requirements.
b. Discharge f)eris based on 3-unit operation.
c. Concentrations bascd3on dounstrcam rlverflov of 5,000 ft /s.
ninimum of 23,000 ft /s for open node.
&never, heat dissipation conaidcrationa vill require
d. Ho specific standard has been idcntificd but contribution to dissolved solids has been included.
e. Computation is for ch'oridcs since thc chlorine demand of he cooling vater ia such that ro residual chlorine viU. be discharged. Chlorides anil total di. oolvcd solids rcflcct maximus daily uac of'hlorine in rav coolini; voter.
hnonio end hydrar.inc added to auxi3.lazy steam generator for pH and dissolved o ygcn 'control. Hydrazine conservatively o" suacd to decompose to arwonf,a.
g. Alabc o "iiter Tnpromucnt ".canLisaion Stream Standards,
'EaMc 4,1-1 Sln" NsY CF ):4'ril,blOICCICSt Y~SVIICII I~I4 flCCll~h.
WlO'.illS 'FBlflY llUCLRhll Pf.Qlg Zocplarh!Con, Chlorophyll pro4uc tivi ty Bcnthie titian Fatsoo4:nlsl.s ans ptvtopi an&on "~on 1ln Moonnsssonts Faana oodlntot Flsl 4lu!
Scccnk 6 cek E=bay.ant Station Xb X 283.94 X Elk River Mba)~ent Gtation X 206.78 X 291.76 X 293.70 X 295 GT X 29).00 30l.06 307,52 X - Xn4icatca at 1ca:t ono quarterly ocssplc collcctcd at thc epccifiC4 atat5onF
a. Fish sa~plfnG at a opccific station vi)l bc by cithcr gill nct, trap nct> rotcDone> 0?'lcctro."iohirc, lto<c'ierq 4cpcnd'ng upon thc aw:plin~ nctho4 thc frcqucncy of smplinG at oach location rsav 5e loser than auaetcrly,
b. 'ialyais - Dis:olvc4 o."ygcn an4 tcnYpcraturct c )ne!ysis - Disaolvc4 oxygen, tcmpcrcturc ROD, COD,,<, alkdini',y, cpccifia con4uctancc, Ha, 0>,, chlori4csq ni t cc" cns (l')I3 ~,l n'nt organic) an4 a lids {Bz:olvcL, suspcndc4 an4 total j 4 g
02 +KOAN<
axxzc1u ~ax:~aaCUXt:~En)
~ tDt'rn>taCxrz- J ORQVIHS I EHBY NUCLFAH f'l.AHl
~
p) lU EXlSTlHG TEh/PERATURE MONITOR Ffgurt. 2.1-1 MONITORING LOCATIONS WHEELEB BESEHVOlR
$ &ltJ at'XLCS
h!AHAGER OF PO'HER DIYISIOH OF POWER PRODUCTION CHIEF, HUCI EAR GENERATION BRANCH NUCLEAR PLANTS BROWNS FERRY NUCLEAR PLANT TVA Office'of Power Organizat'ion for Operation of Huclea". Plants Figure 5.'2-J
8"ARD OF DIRECTORS OFFICE OF THE GENERAL H"(AGER AUDIT STAFF It(FO(t.'(ATIOtf OFFICE 'kQHI((GTOtt OFFICE FIN EQJAL EHPLOYMEHT OPPORTUNITY STAFF DIVISIO(l OF DIVISICti OF OIVISIOI( OF Di VIS IO.'i OF DIVISIOH OF LAtiD BETVEEN P ERSC(:t(EL "(CE PURC((AS I((G PROPERTY JU(0 SERVICES THE LAKES DIVIS IO( OF OFFIC'E OF OFFICE OF POVER OFFICE OF DI V IS 10'I OFFICE OF VATER EHGlt(EERlt;0 DESIGN AGRICULTURAL ANO OF TRIBUTPAV 01 VIS I ON 5:
HA(LLQEtiXKT AHD COi(STRJCTION QIEHICAL GEVELOPHEHT MEDICAL ARiA PO'i(ER RESOURCE PLJU(NING DIVISIONS( SERVICES DEVELOPMENT Tfb'J(SHISSIOH PLA!(t(IHG 01 VIS I OHS EHGINEERIHG ANO EHGINE'ERIHG AGRICULTURAL OEVELOPHEHT DIVISION OF I ON DESI'Ot(STR(JCT POVER CO.'(STRUCT ION . "CHEJIICAL DEVELOPMENT 01 V I S IO'I DIVISION OF NAVIGUI ON POVER PRODUCTION . CHEHICAL OPERATIONS OF FORESTRTs.
OE'VE LOP ME(ir POVER SYSTEM 0?ERATIO!(S EHVIRONHrt(TAL FISI(ERIES, AHD REGIC'(PL Ps(ER UTILIZATIO(( . PLAtU(IHG AND VILOLIFE STUDIES DEVELOPMENT STAFFS:
OUALITY ASSURANCE AND AUDIT STAFF NUCLEAR SAFETY R VIEV BOARD BRO'lHS. FERRY H(JCLEAR PLANT POVER RESEARCH STAFF Orpantsat(on of the Tennessee Valley.Author(ty FIpure 5.2-2
ENCLOSURE 3 qoovo66~
0 TENNESSEE VALLEY AUTHORITY BROWNS PERRY NUCLF~ PLANT TECHNICAL INSTRUCTION 47 OPFSITE DOSE CALCULATION MANUAL (ODCM)
Approved:
ant Superintendent Date: June 21, 1979
6/21/79 TABLE OF CONTENTS
1. Gaseous Effluents.................................................l
'a 1.1 Alarm/Trip Setpoi,ts ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 1 1.1.1 Release Rate Limit Methodology pCi/s '
..................1 A. Noble gases-assumptions and equations.........'...0...1 B. Radionuclides and particulates- assumptions and equations00 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ \ ~ ~ ~ 00 ~ 0\ ~ ~ ~ ~ ~ 00 ~ 0 ~ ~ ~ 0 ~
N 0\ ~ 0 ~ ~ 01 1.2 Monthly Dose Calculations................................'.15 1 .2.1 Noble Gases................'. ~ . .........;...;......15
~
1.2.2 Iodines and Particulates.................. ........20 1.3 Gaseous Radwaste Treatment System Operation...............22 1.3.1 System Description........ ........................23 1.3.2 Dose Calculations..........'.............. ~ ~ 0 ~ ~ ~ ~ 0 ~ ~ 23
2. Liquid Effluents................... ~ ~ ~ ~ 0 0 ~ ~ ~ ~ 00' 00049 2 .1 Concentration....'.........................
2.1.1 RETS Requirement....................................49 2.1.2 Prerelease Analysis..........'..............
2.1.3 MPC-Sum of the Ratios... ~ ~ ~ ~ ~ ~ ~ ~ 49 2 .2 Instrument Setpoints..
2.2.1 Setpoint Determination........................,....50 2.2.2 Post-Release Analysis ~ ~ ~ ~ ~ ~ ~ ~
51 2 03 Dose 0 ~ 0 ~ ~ 0 0 ~ ~ ~ ~ ~ ~ 0 0 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 51 2.3.1 RETS Requixement........................... ~, ~ ~ ~ 0 ~ ~ 51 2.3.2 Monthly Analysis........-.-.--........-.... ~ ~ ~ ~ ~ 52 2.3.2.1 Vater Ingestion............................52 2.3.2.2 Fish Ingestion.......... .................53 ~
2.3.3 Annual Analysis. .. , ~ ~ ~ ~ ~ . ..
~ ~ ~ ~ . . . . .. . ....54
~ ~ ~ ~ ~ ~ ~ ~ ~
2.4 Operability of Liquid Radwaste Equipment.................055 2.4 1 Release Limit.......,...,... ~ ~ ~ ~ ~ ~ ~ ~
6/21/79 TABLE OF CONTENTS (Cont'd) 3.0 Radiological Environmental Monitoring..............................56 3.1 Monitoring Program....................................;;..... 56 3.2 Detection Capabilities..............'.............'.....'....... 57 0 ~
~ ~ ~
' ~ t 'I
~
~
l.~ Caseous Ef Eluents Page l I
BF TI 47 1.1 Alarm/Tri Set pints 6/21/79 Specification 3.8.B.1 requires that the dose rate in unrestricted
'gP areas due to gaseous effluents from the site shall be limited at all times to the following values:
1, 500 mrem/y to the total body and 3,000 mrem/y to the skin from noble gases.
2 1,500 mrem/y to any organ from radioiodines and particulates.
Specification 3.2-K.l requires gaseous effluent monitors to have alarm/
trip setpoints to ensure that the above dose rates are not exceeded. This section of the ODQi describes the methodology that will. be used to determine these setpoints.
The methodology for determining alarm/trip setpoints is divided into tvo ma)or parts. The first consists of backcalculating from a dose rate to v
a release rate limit, in ]ICi/s, for each nuclide and release point. The second consists of using'he release rate limits to determine the physical settings on the monitors. The methodology for the latter is contained in Technical Enstruction 15.
1.1.1 Release Rate Limit ."!ethodolo v pCi/s
~Ste 1 The first step involves calculating a dose rate based on the design ob]ective source'term mix used in he licensing of the plant. Historical meteorological data used are in this calculation.
Doses are determined for (1) noble gases and (2) iodines and particulates.
Depending on the pathway involved, either air concentrations 'or ground concen-trations 'are calculated.
A. Equations and assumptions for calculating doses from noble gases are as follows:
Page 2 BP TI 47 6I21(79 Assu= tions
1. Doses to be calculated are total body and skin.
20 Exposure pathway is subnersion within a cloud of noble gases.
30 Noble gas radionuclide nix is based on the. expected source tern given in Table 1.1.
Basic radionuclide data are given in Table 1.2.
Releases are treated as ground-level, split-level, or elevated.
6 Heteorological data are expressed as joint frequency distributions (JED's) of wind speed, wind direction, and atmspheric stability for the period January 1974 to Dec'enber 1975 (Table 1.3). Releases fron the turbine building are treated as 100 percent ground level, whereas stack releases are considered 100 percent elevated. Releases fron the reactor building and rad-aste 'building are treate6 as split-Level; i..e.,
partly e1evated and partly ground level.
Raw neteorologicaL data for ground-Ieve1 releases consist of wind speed and direction neasure=ents at 10 n and te=perature neasurenents at 10 =
and 45 n. The ground-level portion of the spLit-level JH) was based on wind speeds and directions neasured at the 10 n level. and temperature neasuremnts at 10 and 45 n. The elevated portion of the split-level JPD w~ based on wind speeds and directions neasured at 46 n and tenpera-ture measure=eats at 45 and 90 m. Rind speeds and directions for elevated releases vere neasured at 93 n. Stability class D was assuned to persis-during the entire period for elevated releases.
8. Dose is to be evaluated at the offsite exposure point where naximm concentrations are expected to exist.
9. Potential naxirun-exposure (Table 1.4) considered are the nearest site boundary points in each sector.
0 Page 3
.BF TI 47 6/21/79
10. A semi-infinite cloud model is used.
',I
11. No credit is taken for shielding by residence.
12. Plume depletion and radioactive decay are considered.
13. Building wake effects on effluent dispersion are considered.
14. A sector-average dispersion equation is used.
15. The wind speed classes that are used are as follows:
Number Ran e (m/s) Mid oint (m/s)
<0.3 0 13 0.3-0.6 0.45 0 7-1-5 1.10 1.6-2.4 1.99 2.5-3 3 2.80 3.4-"5-5 -
45 5.6-8.2 6 '1
>10.9'3.00
16. The stability classes that will be used are the standard A through G classifications. The stability classes 1-7 will correspond to A 1, B 2, . ; ., G 7.
17 Terrain elevations are considered.
Eguations To calculate the dose from radioactive effluents discharged from a given release point for any one of the 16 potential maximum-exposure points,
the following equations are used.
For determining the air concentration of any radionuclide:
~ \
Page 4 BF TI 47
. 9 . 7 6/21/79 2 a/z
~Qu i Uj
~
(2xx/n) 5a kal exp -h /2cf (1 1)
X ~ air concentration of radionuclide i, pCi/m .
f ~ joint relative frequency of occurrence of ~ds in wiadspeed class j, stabiU.ty'lass k, blowing tovard this exposure P
point, expressed as a fraction.
~ average release z'ate of radionucLLde i, pCi/s-p ~ fraction of radionuclide remaining in pl~,
Figure 1.1.
E ~ vertical dispersion coefficient .for stability class k <<Sich
/a includes a building ~ake adjust=ent, E xk
~ a zk w 0.5U~"
+here a k is the vertical dispersion coefficient for stability class 'k (n), and A is the minirnm building cross-sectional area (2,350 m ), m..
u ~ midpoint value of wind speed class intezval j, m/s.
x ~ dovnvtnd distance, m.
n ~ number of sectors, 16.
~ radioactive decay coefficient of radionuclide i, s 2ltx/n ~ sector width at point of interest, m-h ~ effective release height, m.
For effluents exhausted from release points that are higher than t~Cce the height of adjacent structures (elevated releases) the effective release height is determined by he ~h s +h pr -h t -c (l.la)
Page 5.
BF TZ 47 6/21/79 where c ~ correction for low relative exit velocity, c 3(1.5-Wo/u) d, where Wo ~ vertical plume exit velocity (m/s), u mean wtndspeed (m/s), and d ~ inside diameter of the release point, m.
h plume rise above release point, m.
pr h8 physical height of release point, m.
h maximum terrain height between release point and receptor location (h can be any real number), m.
Por effluents released from points less than the height of adjacent structures, a ground level release is assumed (h ~ 0).
Por effluents released"'from points at the level. of or above ad]acent structures, but lower than elevated 'release points, releases are treated as follows:
Case 1 - elevated if W /u > 5 Case 2 - ground-level (he o) if W 0
/u < l.
Case 3 - split-level if 1 < W 0
/u
~
< 5.
Under Case 3 a split-level dispersion approach is implemented using a model that requires for each release point two JFD's, one for elevated releases and one for ground-level releases. The. summation of the elevated and ground-level JFD's account for the total period of record. Releases are considered to be elevated 100 (1-E ) percent of the time and ground-.
percent of the time where the entrainment coefficient, level 100 E t E ,
is defined by E
t ~ 2.58. - 1.58. (W o
/u) for 1 < W o
/u < 1.5 (1.1b)
~ 0.3 - 0.06 /u) for 1.5 < /u < 5 (l.lc)
E t.
~
(W 0
W 0
~I Page 6 BF TI 47 6/21/79 For deteraining the total body dose rate
~ 1x10~ X DFB DTB
+here D ~ total body dose rate, ~en/y.
X ~ air concentration of radionuclide i,, pCi/cL3 .
.DFBi ~ total body dose factor due to E
g~ radiation, nrem/y per pCi/a (Table 1.5). C ixlO pCi/pCi'conversion factor.
For deteruining the skin dose rate D ~ ~05 .X [DFS + 1.11 DFy ] (1.3) where D
S
~ skin dose rate, exea/y.
X ~ air concentration of radionucI'de i, ~+Ci/a .
DFS skin dose factor due to beta radiation, ="e=,'y per pCi/a (Table 1.5).
DFy i ~ gmm-to-air dose factor for radionuclide i, me=/y per pCi/m (Table 1.5) .
M.O ~ pCi/pCi conversion factor.,
The above dose calculations are repeated for each release point (vent or stack) and then su=ed to obtain aaM-m total body and s~ dose rates.
The maxinun total body and skin does rates vill then be. used in step '2.
Page 7 BP TX 47 6/21/79 B Equations and assumptions for calculating doses from radioiodines and particulates are as follows:
hssum tions
l. Dose is to be calculated for the critical organ, thyroid, and the critical age group, infant.
2. Exposure pathways from iodines and particulates are milk inges-tion, ground contamination, and inhalation.
r
3. The radioiodine and particulate, mix is based on the.-
expected source term given in Table 1.1.
4 Basic radionuclide data are given in Table"1.2.
5; Releases are treated as ground-level, split-level, or elevated.
6 Meteorological data are expressed as )oint frequency distri-P butions (JFD's) of wind speed, wind direction, and atmospheric stability for the period January .1974 to December 1975 (Table 1.3). Releases from the turbine building are treated as 100 percent ground level, whereas stack releases are considered 100
~
percent elevated. Releases from the reactor building and rad-waste building are treated as split-level; i.e., partly elevated and partly ground level.
a
7. Raw meteorological data for ground-level releases consist of wind speed and direction measurements at 10 m and temperature measure-ments at 10 m and 45 m. The ground-level portion og the split-level JFD was based on wind speeds and directions measured at the 10 m level and temperature measurements at 10 and 45 m. The elevated portion of the split-level JFD was based on wind speeds and directions measured at 46 m and temperature measurements at 45 and 90 m. Mind speeds and directions for elevated releases
Page 8 BF TI 47 6/21/79 vere measured at 93 m. Stability class D was assumed to persist during the entire period for elevated releases.
8. Dose is to be evaluated at the potential offsite exposure point vhere maximum concentrations are expected to exist.
9 Real cow and garden locations are not considered.
10. Potential maximum-exposure points (Table 1.4) considered are the nearest site boundary points in each sectors
11. Terrain elevations are considered.
12 Building wake effects on effluent dispersion are. considered.
13. Plume depletion and radioactive decay are considered for air-concentration calculations.
Radioactive decay is considered for ground-concentration
~P calculations.
15 Deposition is calculated based on the curves given in Figure 1.2.
. 1'6.; A milk cow'obtains 100 percent of her food from pasture grass.
1T No credit is taken for shielding by residence..
~Euatians To calculate the dose from radioactive effluents discharged from a given release point for any one of the potential maximum-exposure points, the following equations are used.
1. Inhalat ion Equation for calculating air concentration, X, is the same as in the Noble Gas Section, 1.1.1.A.
For determining the thyroid dose rate:
Page 9 BF TI 47 6/21/79 g DFI BR ~ 0-4) where:
\
D~ ~ thyroid dose rate due to inhalation, are=/y.
X ~ air concentration of radionuclide i, pCi/n .
DFIi ~ infant in'.mlation dose factor, arm/pCi (Table 1.7).
BR ~ infant breathing rate, 1,400 a /y.
IxIO ~ pCi/"Ci conversion factor.
2. Ground Cont~nation
For determining the ground concentration of any ne'chide:
G i ~ 3 15xl0 Q. DR (2N x/n)
(1.5) where G ~ ground concentration of radionucIide i,'Ci/a .
k ~ stability class.
f ~ ]oint relative frequency of occurrence of vinds in stability class k blowing te:ard this exposure point, expressed as a fraction.
~ average release rate of radionuclide i, pCi/s.
DR ~ relative deposition rate, n (Figure 1.2). The choice of figure is g'overned by the effective release height calculated by equation l.la. A linear. interpolation is used for effective release he-ghts that fall in between the given curves+
x ~ doMnvind distance, a.
a ~ nu=ber o sectors, 16.
4 2rx/n ~ sector width at point of interest, a.
~0 Page 10 BP TI 47 6/21/79 i ~ radioactive decay coefficient of radionuclide i, y ~ .
t ~ tine for buildup of radionuclides on the ground, 35y.
3.15x10 ~ s/y conversion factor.
For deternining the thyroid dose rate from ground cont~nation:
D~G
~ (8,760) (lxlG ) G DFG (1. 6) vhere:
D G
thyroid dose rate. due to grou"-d contanination, are=/y.
G ~ ground concentration of radionuclide i, gCi/n .
DFG i ~ dose factor for standing on co=t~nated ground, nrem/h per pCi/n (Table 1.8).
80760 occupation ti=e, h/y. ~ ~
~0 pCi/MCi conversion actor 3 Milk Ingestion For detemining the concentration of any nuclide (except C-14 arid H-3) in and on vegetation:
7 fk i DR frtl exo Q r (-3L
=i te ) +
(2Hr/n) >
Y CR Bi [1-exp (-X. tb)]
p Xi vhere:
CV i ~ concentration of radionuclide i in and on vegetation, llCi/kg.
k ~ stability class.
fk ~ frequency of this stability class and wind direction coabination, expressed as a fraction.
Page ll'F TX 47 6/21/79 average release rate of radionuclide i, pCi/s.
1 DR ~ rel'ative deposition rate, m (Figure 1.2. The choice of figure is governed by the effective release height calculated by equation l.la. A linear interpolation is used for effective release heights that Sall << between I
the given curves.
x ~ downwind distance, m.
n ~ number of sectors, 16.
2m@/n sector width at point of interest, m.
fraction of deposited activity retained on vegetation (1.0 for iodines, 0.2 for particulates).
effective removal rate constant,, AEi 0 ~
X. + X W , where Xi is the radioactive decay coefficient, h , and X W
is a measure of physical loss by weathering (A .0021 h i), h period over which deposition occurs, 720 h.
Y V
~ agricultural yield, 0.7 kg/m .
B iv transfer factor from soil to vegetation of radionuclide i (Table 1.6).
radioactive decay coefficient of radionuclide i, h 1 tb time for buildup of radionuclides on the ground, 3.07xl0 h (35y).
P ~ effective surface density of soil, 240 kg/m 3,600 ~ s/h conversion factor.
Page 12 BF TX 47 6/21/79 Por determining the concentration of C-14 in vegetation:
14
~0 X14 (0.11/0.16 (1.8) where CV 14
~ concentration of C-14 in vegetation, pCi/kg.
14
~ air concentration of C-14, pCi/m 3 . ~ ~
~ ~
I O. IL ~ fraction of total plant mass that is natural carbon.
0.16 ~ concentration of natural carbon in the atmosphere, 3
g/m .
1x10 ~ g/kg conversion fac'tor.
For determining the concentration of H-3 in vegetation:
CV ~ lxl0 X (0.75) (0.5/H) {1.9)
P\
where CV T
~ concentration of H-3 in vegetation, gCi/kg.
X ~ air concentration of X-3, pCi/m 3 .
0.75 ~ fraction of total plant mass that is water.
0.5 ~ ratio of tritium concentration in plant water to tritium concentration in atmospheric water.
H ~ absolute humidity of the atmosphere, g/m .
1x10 ~ g/kg conversion factor.
Page 13 BF TI 47 6/21/79 For determining the concentration of any nuclide in cow's milk:
CM CV FM 'Q exp
(-X i t f) (1.10) where CM concentration of radionuclide 'i (including C-14 and H-3) in cow's mi:
Pci/1.
, CV concentration of radionuclide i in and on vegetation, pCi/kg.
FM i transfer factor from feed to milk 'for radionuclide i," d/l.
Q f~ amount of feed consumed by the cow per day, kg/d.
i ~ radioactive decay coefficient of radionuclide i, d tf ~ transport time of activity from feed,to milk to receptor, 2 days.
For determining the thyroid dose rate fromingestion of cow's milk:
~ \
D ~ lx10 CM DFINGi UM (1. 11) where D~ ~ thyroid dose rate due to milk ingestion, mrem/y.
CM i ~ concentration of radionuclide i in cow's milk, pCi/1. "
DFINGi ~ infant ingestion dose factor from Reg. Guide 1.109 (Rev. 1),
mrem/pCi (Table 1 7),
DM ~ infant ingestion rate for milk, 330 1/y..
lxl0 ~ pCi/WCi conversion factor.
4. Total Th roid Dose Rate For determining the total thyroid dose rate from iodines and particulates:
TH THI THG THM (1.12) where D ~ total thyroid dose rate, mrem/y.
Page 14 BF TI 47 6/21/79 D ~ thyroid dose rate due to inhalation, mrem/y.
D G
thyroid dose rate due to ground contamination, mrem/y.
D ~ thyroid dose rate due to milk ingestion, "mrem/y.
~ ~
The above dose calculations are repeated for each release poi'nt and then summed to obtain thyroid dose rates. .The maximum thyroid dose rate will then be used in step 2.
~Ste The dose rate limits of interest (10CFR20) are Total Body ~ 500 mrem/y Skin ~ 3,000 mrem/y Maximum Organ ~ 1,500 mrem/y Dividing the above limits by the appropriate dose calculated in step 1 yields a useful ratio.
Dose limit R Dose step 1 This ratio, R; represents how far above or below the guidelines the step 1 calculation was. Multiplying the original source terms by R will give release rates that should correspond to the dose limits given above..
Release rate limits in QCi/s for each nuclide and release point are now ayailable.
Page 15 BF TI 47 6/21/79 1.2 Monthl Dose Calculations Dose calculations vill be performed monthly to determine compliance vith specifications 3.8.B.3 and 3.8.8.5. These specifications require that the dose rate in unrestricted areas due to gaseous effluents from each reactor at the site shall be limited to the folloving values:
Por noble gases, During any calendar quarter, 5 mrad to air for gamma radiation,and 10 mrad to air for beta radiation.
20 During any calendar year, 10 mrad to air for gamma radiation and 20 mrad to air for beta radiation.
For iodines and particulates,
3. During any calendar quarter, 7.5 mrem to any organ.
2 During any calendar..year, 15 mrem to any organ.
This section of the ODCM describes the methodology that vill be used to perform these monthly calculations.
Doses vill first be calculated by a simplified conservative approach (step 1). If these exceed the specification limits, a more realistic calculation will be performed (step 2).
1.2.1 Noble Gases
~Ste 1 4 F
Doses vill be calculated using the methodology described in this step.
If any limits are exceeded, step 2 vill be performed.
Equations and assumptions for calculating doses from releases of noble gases are as follows:
Page 16 P BFTI47 6/2l/79 Assum tions
1. Doses to be calculated are gamma and beta air doses.
.2. The highest annual-average )(/Q based on licensing meteorology for ground-level releases for any offqite. location will be used
3. No credit is taken for radioactive decay.
4. For gamma doses, releases of Xe-133, Xe-138, Kr-85m, and Kr-88 are considered.
5. For beta doses, releases of Xe-133, Xe-138, Kr-85m, and Kr-88 are considered.
6. Dose factors are calculated using data from TVA's nuclide library.
7.. The nucU.des considered are expected to contribute at least 90 percent of the total dose. However, the calculations extrapolate doses assuming 1
that only 90 percent of total dose was 'contributed.
8. A semi-infinite cloud model is used.
9. Building wake effects on effluent dispersion are considered.
~Ruat fons For deteunining the gamma dose to air:
Y 0 9 i i (1.13) where:
D gamma dose to air from continuous releases, mrad.
x/Q- highest annual-average relative concentration, 2.26 X 10~ s/m 0.9 ~ fraction of total gamma dose expected to be contributed by these nuclides (actually 0.94).
Q i ~ monthly release of radionuclide i, Ci.
DPfi ~ gamma-to-air dose factor for radionuclide i, mrad/s per Ci/m (Table 1.5).
'I Page 17 This equation then reduces to BF TI 47.
6/21/79 D ~ 2.51xl0 ~
(1.14)
Y For determining the beta dose to air:
i DFg
@here:
D ~ beta dose to air, mrad.
X/Q ~ highest annual-average relative concentration, 2.26xlO
~ ~
s/m3.
0.9 ~ fraction of total beta dose'xpected to be contributed by
'these nuclides..(actually -.0.90);
Qi
~ monthly release of radionuclide i, Ci.
. DFgi ~ beta-to-air dose factor for radionuclide i, mrad/s per Ci/m (Table 1.5).'his equation then reduces to:
D~ . 2.51xlO DFg (1.16)
~Ste 2 This methodology is to be used if the calculations in Step 1 yield doses that exceed applicable limits.
Page 18 BP TI 47 6/2LI79 Equations and assumptions for. calculating Y
doses to air from releases of noble gases are as follows:
Assum tions
1. Doses to be calculated are gamma and beta air doses.
2. Dose is to be evaluated at the nearest site boundary point in each sector.
3. Historical onsite meteorological data for t;he appropriate months from the period 1974-1975 will be used.
4. All measured radionuclide releases are considered.
~ ~
5. A semi-infinite cloud model is used.
6. Radioactive decay is considered.
7. Building wake effects on effluent dispersion are considered.
8. Dose factors are calculated using data from TVA's radionuclide library.
~cCuations Equation for calculating air concentration, X, is the same as in Section 1.1.1, step 1, part A. Air concentrations are calculated for the site boundary in each sector.
For determining the gamma dose to air D tm (1.24) where:
D ~ gamma dose to air for sector n, mrad.
~,
Page 19 air concentration of radionuclide i in sector n, 6 21 79 Ci/m .
~
DFf< g~-to-air dose factor for radionuclide i, mrad/s per Ci/m (Table 1.5) .
t ~ time period considered (1 month, but number of s/mo is variable), s.
- ~
For determining the beta. dose to air:
D~~t ~ DFBi where:
D~ ~ beta dose to"air for sector n, mrad.
i air concentration of radionuclide in sector n, Ci/m
~l DF>>"i a beta to air dose factor for radionuclide i, mrad/s per Ci/m t ~ time period considered (number r
of seconds in this month),
The sector having the highest total dose is then used to check compliance with speci ication 3.S.3.3.
Page 20 BF TI 47 6/21/79 1.2.2 Iodines and Particulates
~SCe 1 Doses will be calculated using the methodology described in this step.
If any limits are exceeded, step 2 will be performed.
Equations and assumptions for calculating doses from releases 'of iodines and particulates are as follows:
1. Dose is to be calculated for the critical organ, thyroid, and the critical age group, infant.
2. Exposure pathway considered is milk ingestion~
3 The hi'ghest annual-average D/Q based on licensing meteorology for ground-level releases for any real cow location will be used for I-131 and I-133 doses. "-'.
The highest annual-average X/Q based on licensing meteorology. for ground-level releases for any cow location will be used for C-14 doses.
5. No credit is taken for radioactive decay.
6. Releases of I-I31, I-133, and C-14 are considered.
7. The radionuclides considered are expected to contribute at least 99 percent of the total dose. However, the calculations
Page 21 BF TI 47 6/21/79 extrapolate do=es assn.~g that only. 90 percent of the total dose vas contributed.
8. Releases of C-14 are based on the expected. source term.
9 The cov is assu=ed to graze on pasture grass for the +hole year.
~Eaatiaaa'or determining the thyroid dose from milk ingestion of I-131 or I-133:
DF 131(133) 131(133) D/Q
~1(133) 3 15x107 Mere:
131(133)
~ thyroid dose from I-131(I-l33), mrem.
Q131(133)
~ monthly release of I-131(133), Ci.
131(133)
~ I-131(133) milk ingestion dose factor to infant, mrem/y per Ci/m -s.
2 D/Q ~ relative deposition rate, 5.66x10 9 m
3,15x10 s(y.
For determining the thyroid dose from milk ingestion of C-14:
m , - Q14 "14 X/Q 3.15%10 (1.27)
+here:
DTH ~ thyroid dose from C-14, mrem.
14" 14
~ monthly release of radionuclide i, Ci.
14 C-14 milk ingestion dose factor, mren/y per Ci/m 3 .
X/Q- rel~tiue dispersion factor, 2.26xl0 6 s/m 3 .
3.15x10 ~ s/y.
a For determining the total thyroid dose from releases:
~ ~
Page 22 BF TI 47 DTH131 + DTH133 + DTHI4 6/21/79 (1.28)
0.9 where
thryoid dose, mrem.
dose from release 'hyroid of X-131, mrem.
133 .
thyroid dose from release of I-133, mrem.
DTH14 ~ thyroid dose from release of C-14, mrem.
0.9 ~ fraction of total thyroid dose expected to be contributed by these radionuclides (actually I
0.99).'his
~St a 2 methodology is to be used if the calculations in step 1 yield doses that exceed applicable limits.
~
Doses for releases of iodines and particulates shall be calculated
~l +\ ~ ~
using the methodology in Section 1.1.1, step 1, part B, vith the folloving exceptions:
1. All measured radionuclide releases wil1 be used
2. Dose will be evaluated at real cov locations and vill consider actual grazing information.
The receptor having the highest total dose is then used to check compliance with specification 3.8.B.5.
1.3 Gaseous Radwaste Treatment S stem 0 eration The gaseous radwaste treatment system (GRTS)'described below shall be maintained and operated to keep releases ALA%.
I ~
'Page 23 BF TE 47 6/21/79 1.3.1 S stem Descri tion A flo~ diagram for the GRTS is given in Figure 1.3. The system includes the subsystems that process and dispose of the gases from the main condenser air ejectors, the startup vacuum pumps, and the gland seal condensers. One gaseous rad~aste treatment system is provided for each unit. The processed gases from each unit are routed to the. plant stack for dilution and elevated release to the atmosphere. The air ejector off-gas line of each unit and the stack are continuously monitored by radiation monitors.
1.3.2 Dose Calculations Doses vill be calculated monthly using the methodology described in Section 1.2. These doses Wll be used to ensure that the
~ \
GRTS is opera-ting as 'designed.
ETLDE74 J ~ 1
'EXPECTED ANNUAL ROUTINE ATHOSPUHKC KELEASES FROH ONE UNIT AT BROWNS FERRY Page 24 BF TI 47 NUCLEi& PLP4~T Ci/ /~unit STACK 6/21/79 REACTOR RADWASTE TURBINE GLAND CONPLEX BUILDING BUILDING SEAL AND TSOTOPE VEST VEVTS OFFGAS Kr-85m 6 2 1e10 E4 0 Rr-87 6 CL 95 873 0.
Ãr-88 9 102 1.22 E4 0 Kr-89 1. ~
34 503 0. 0.
Xe-133m 0 60 7 0 633 0 Xe-133 103 294 '" 581: 5.40 E4 300.
Xe-135m 111 667 464 1212 0 Xe-135 173 328 672 868 200.
Xe-137 78 113 386 .0 0 Xe-138 12 2 1179 1483 0 X-131 I 0.0594 0 0 0156 0 0041 0 0085 I
0050'.
X-132 0.594 050 .0 1786 0 0469 0 0973..
I-133 I 0.297 0. 025 0.1231 0.0671 I
'~0323 X-134 1 485 0 125 0 0267 0 0070 "0 0145...
X 135 I 0 594 0 050 Oi1231 0 0323 0 0671
. I-131 0 0.0316 0.029 0 0065 0 0332 0.2741
~ .'-132 0 0.316 0 290 0.0744 0 3801 3 1384 I-133 0 0.158 ,0. 145 .0.0513 0 2619 2 1626 X-134 0 0 790 0 725 0 0111 0.0568 0.4687 I-135 0 0.316 0~290 0 0513 0 2619 2 1626 Cr 51 3 E-3 9 EW 1 E-3 1 E-4 0 Mn 54 3 E-3 5 E-3 2 E-3 4 E-5 0 Co 58 2 E-3 4 E-4 9 E-5 2 E-5 0 Fe 59 1 E-4 8 E-4 4 E-4 2 E-4 0 Co 60 3 g-2 6 E-3 3 E-3 1 E-5 0 Zn 65 3 E-3 ~ 2 EW '4 E-4 9 E-5 0 Sr 89 ~ ~
1 E-2 3 E-1 0 Sr 90 2 E-3 4 E-3 0 Nb 95 3 E-4 2 E-4 9 E-6 8 E-5 0 Zr 95 1 E-4 1 E-4 8 E-6 8 E-5 0..
Ru 103 3 E<<5 1 E-4 .
'2 E-4 -. 1 E-4 0 Ag 110m 7 E-6
0 Sb 124 3 E-5 3 E-4 6 E-5 8 E-5 0 Cs 134 5 E-3 3 E<<4 E-4 2 E-5 0 Cs 136 2 E<<3 5 E>>5 1 E-4 9 E<<8 0 Cs 137 7 E-3 4 z-4 2 E-3 7 E-4. 0 Ba 140 . 4 Z-3 5 E-4 2 E-2 8 E-3 0 Ce 141 4 E-4 2 E-4 2 E-3 ~ 2 E-5 0 Ce 144 5 E-6 *
4 E-6 0 Ar-41 ~~
25 0 0 0 0 C<<14 0 , 0 ,0 9o5 0 H-3 0 9o5 g' 0 0.
~Not available X denotes nonorganic iodine (eleaental, particulate, HXO) 0 denotes organic iodine
hUC IOE ~ hA F F AM A T 6AMM Page 25 (OAYS) (1/S) .
(ME.V/OIS) (MKV/OIS) (1/S) TI 4 7 TAITIUM 101 4.495 03 '1,799.-09~2'. 5,455-03 o.o 'oooo -o 6/31/79
'9f
~
1 2 C'4 604 2 06 3 '4K-]2 "
2 1 5 ~ ]7E 02 '0 ~ 0 0~0 3
4 M
O]9 13 804 3 ~ 36E 04 2 '9E OZ 2 4
1 ~
U9M 02E 00
~2.MQ 1 ~ ObE 00 La.O.QM?
l.~ Opf 02 62c'-02 CASSE-01 5 F ]Bi 902 7 Q5K-04 C ~
9 4 6 hA 24 1104', 6 '3E-Ol 1 ~ 27E"05 5 4 ~ 12E 00 OOE 04 7 P 32 8 AA 41 1504 1805 7 1 ~
~
43K 01 63K Qc 5
1 ~
']E OSE 07 04 6 ~ 95K 01 3 '3K-01 1 '8E 00 0~0 1 ~
0~0 00 -04 9 CA 51 54 2405 2.78E Ol 3 '3E 02 2 89E- 7 2 '5E 08 755- 3~3 55-93 4 ~ 17E 03 8 ~ 36E 01
~l}5~4 OOE 04 ll )3h 56
]2 FE 59 2509 2604
]%07K 4 '0E Ol 01 7 '0E-05 1 ~ 78K-07 1
7 93E 01 1 ~ leE-01
~ 76
~ 19E OD 1 ~
0 1 ~ OOE-04 4
]3 co-58 2706 7 ~ ]3E Ol 1 ~ 12E 07 2%05K 01 1
9 'af-0] ' 1 ~ QQE 04 14 CO 60 270'8, 1 %92E 03 4 ~ 18E 09 9% c}e K-02 2 '0E 00 ~ OOE-04 15 Zh 69N 3007 5 75K-0 1 ~ 39E 05 0~0 4 '55" 0 095-94 6 '~69 3006. .3 '6E Oi 2 '3E 04 5 3 ~ 19E, 01 0 ~ 0 . 1 ~ OOE 04
]7 BR 84 3516 2 ~ 2]E-02 3%63E-04 '
%2&K 00 ~ 68K Qoc 04 18 BR 85 35 1'8 2 '8E 03 3 '6E-03 04E 00 8 ~ 40E-Ol OOE-04
~
1 ~ 1~
19 KA 85N 3611 1 ~ 83E 01 4 '8E 05 2%53E-Ol ]%5'JE-0] 1 ~ OOE-ll 20 KR 85 3610 3 '3E 03 2 ~ 04E-,09 2%5]E Ol 2 ~ 2]E-03 1~ 0pf-11 5 '8K '3K-0 21 KR 87 22 KR 88 23 'KA 89 24 RB-ea 3612 3613 3614 3713 1~
2 1 ~
]7E-01
'124E-0203 02 6
3 6
1%52E-04
'6E 63
'7E-04 05 03 2
1 ~ 32E 00 3%75E-01
'6K 3
00
'V 6 7
1 ~ 9of, 00
'6E-01 1 ~
1 00 1 ~ QOE-1 1
'00
%PQE 04 25 AB-e9 3714 1%07E-02 7 ~ SOE 04 0%0 2%40E 00 1%00E-04 A 26 SR 89 3808 5 ~ 20E 01 1 ~ 54K-07. 5%73E-Ol 1~ 36K-04 2 '7E-07 27 SA 90 3810 ]%03K 04 7%79E- 0 ~ 96E 0 0 0 67 -07 A 28 SR 91 38)) 4 ~ 03E 01 99E-05 5 6.bpf-pl 6 ~ 95E-01 2 '7K-07 H 1 ~
9 SR 92 3812 1% 3K 01 7 0 Pc-5 9c 4 7 D
30 SR 93 31 Y 90 3813 3916 5
2
'6E
'7K 03 00
]%44K-03 3 ~ OOE-06
].elE 00 9 ~ 36E 01 6
0
'df-0]
~ 0 2 '7E-07 QOK-04 O 1 H 32 Y 91M 3919 3 ~ 47E-02 2 ~ 3]E-04 5 0~0 5 '6E-01 1 eppf-04 33 Y-91 3918 S.aef 01' 1 ~ 36E 07 5 6 '6E Ol 3%6 E 0 00 04 34 Y~92 3920 ~ 47E-01 5 '6K-05 1 ~ 44E 00 2 'OE-Ol 1 ~ OOE-04
~ 0 35 36 Y 93 ZR 95 37 he 95M 3921 4014 41]5 4
6 3~
'9K Ol
'0E Ol 75E.'C.',
1 ~ 87E 1
Oc 23E-07 2 ~ .14E-06 1
1~
2%85K-0]
17E 00 20E-0]
8 7
5
'4K
'bE-Ol
'7f-02 02 F 00 -04 1 ~ OOE 04 1 ~ OOE 04 38 NB 95 4))4 3 '0K.O] 2 '9E-07 4obpE 02 64E u]
7 AROSE-01 1 ~ OOE 04
'6E 39 MO 99 4209 2 '9E 00 2 '7K-06 3 Ol 1 ~ 62K-01 1% OOE-04 4 C 99(o 43]4 2 ~ SOE 01 3~ 2]f-05 4 'SE 03 1%43E-Ol 1 ~ OOK-04 41 TC-99 4313 7 '4K 07 1%04E 13 8 '8K 02 0%0 %00 -04 42 TC-104 4320 1 ~ 25K-02 6 '2E 04 5 0~0 0~0 1 ~ OOE-04 43 RU 106 4407 3 '7K 02 2~ 19E-08 5 1 ~ 01E-02 0~0 1 ~ OOE 04 44 TE 132 5223 3 '4K 00 2 '8E-06 1 ~ OOK-01 2 1 ~ OOE-04 45 I 129 c315 6 2]f 09
~ 1 29E-15 4 '2K 02 3%77 -03 5%00 06 46 1-131 5317 8 '5E 00 9 '6K-07 ]%94K 01 3%8]E-01 5%00E-06 47 )RI-]3] 15317 8%05F 00 9 '6K 07 94 8 a 48 1-132 5318 9 '8E-02 8 ~ 37E 05 5 ~ 14E-01 2 '3K 00 5 ~ OOE 06 49 N I 132 15318 9 '8E-02 8 '7E-05 4 5.14E-O] 2 '3K 00 5 OOE 06 50 I"133 5319 8 '5K"01 9 ~ 17E Ob 4 '()K-0] 6~ ]pf-Oi 5 ~ Opf-06 51 NI 133 15319 8%75E-01 9% 17E<<06 08E-Q 1 6.]n -0 5 QQK-06 52 1-134 5320 53"0 F 6]f-02 2 '2E-04 (3%]PK-0] 2 '9F 00 5 ~ OOE 06 3 N 134 3 6 04 0 54 1-135 5321 2 '9K-01 2 '7K-05 3 68E '0] ]%5VE 00 5 ~ OOE-06 5'5 >I 135 15321 2 '9E-01 2 '78-05 3 '8K-01 ce
,56 XE-13]M 5412 le]8E Ql 6 ~ 80E-07 1 1 Ol 2 0 1 K 02 1 OOE 1]
57 Xf 133M 54]4 2926KQC 3.%,55E 06
,58 Xf-133 54 13 5 '7E 00 1 ~ S2E-06 1 1 ~ 3bf-01 4~ Sif 02 1 ~ ppf-] ]
.59 Xf 135M lepeE 02 '3K-04 9 ~ 50E-02
'0 XE-135 5416 5415 3 '3E-01 7]E-03 7
2 '9E-05 2 ~ 96E-03
] ] 3% 17E-01 4 ~ 32E-01 2 ~ 47E-01 1 ~
1 ~
OOE-11 Opf-11 61 Xf-137 5417 2~ ] 64E 00 94E OOE-11 it~3~~45 1 1 ~ 0
~5.
1 ~ 1 1 ~
Pt \ \OF O2 4 595-oo- e.pef-pl 1 ~ 18E 00 OOE-] 1 93-'0E 1 ~
63 CS-134 5510 7 4ef 02 1%07E-08 5 eb7E-01 ~ 04E 00 1%00E-04 Ko Co=13~5}'~ ~
lOE 99 9.29~ 1 1
7~4 1
0~0 1 ~ OOK 04 65 CS-136 5514 1 30E 6%]7E-07 1%0]E-01 2 00 1 ~ OOE 04 66 CS-] 5515 1 ~ ]OE 04 7 ~ 29K 1 p 2eb2E 0] 5 '7E-0] 1 ~ Opf-04 67 CS-138 5516 2 24E 02.. 3 Sef-04 1 ~ 23E 00 2 '0E 00 1.00E-04
}t 54 130 54} 5 745 94 1 ~ 395-9 ~ 6.6~E-Q] 5 ~ OSE 02 OOE-04 69 BA-140 5616 1 2ef "] ' 27E-07 3%]5K-0] 1 ~ 95E>>Q]
1 ~
1 OOE-04 ro 1.A-]40 57]5 1.6ef QQ 4.77E-Q 5 '0E 0] 2.31E 00 ].QOE-04 71 CE 144 581 2 ~ 84K - 2982K 08 9%13K-02 3 '9K-02 1 ~ OOE-04
~2PR 143. 5912 },345 9 5 ~ 90F-97 3 '4K 0] 0 ~ 0 1 ~ Opf-04 73 PA ]44 5913 ]%20K 02 6 ~ 61K 1.23E 00 3% ].Of 02' ~ ppf 04 74 hP 239 93]0 2 ~ 35K 00 3 ~ 4]K 06 1 ~ 24E pl 2.08E 00 ].Opf-04
CEHIllGE EBEQUEttCIES QE tlIBQ QIBECIIQtt'ttllQ ttIUQ SBEEQ Etltt QIEEEBL51 516BILIIX CLtssSSES o ST4HILITY CLASS A
,.DELTA Tc>-I ~ V OEG ~ C/100tt BROWNS FERRY NUCLEAR PLANT HETKOHOLOGICAL FACILITY4 JAN. 15 74 OEC 315 75 9 ~ - 4 It I HO ...IIINO SPEED(HPII)
QIBKCXIQtt 'Qak=lah la5 "3ak 3a53ah 5a5 "Zaf Za5=12a.k IRa5=166 1Ba5=2olat ZEK5 IQI&L
' ' ll ' '
N NHE, 0
0 '
0 0 04 0 ~
F 13 ..
0 ~ 17 F 15 0
0
~ 20 25 0 F 04 0 F 04 0
0 '.. 0 0+52
'1
.. 0.02 0 0 HE EHE 0 '
O.O 0 '4 F
O.OS F 10 O.O4 .
0 F 07
.O.02.
0 F 0 .
0 '
0.0 0
..O.O 0 '
O.O 0 '3
. . . . O.OT E 0,0 0,01 0,03 0,02 0 I 0,0 O,D ' 0 0 0,06 0 Q D II5 0 19 0 ~ 14 . Q 05. 0 0 0~0 D
' 43 0,26 I ~ 35 3II 0,10 0,0 0,0 2,09 SE 0~0 Q
....:0 0..., 0 0 5
5 5lt sf.
5sw.
w$ w 000 0?.0010,010,01,0 0 0 0 0
~
0,02 0,0?
0 ~ 10 0,13 D
0,09 01 .
0 ~
0,01 0,05 02 ~
~
0,0 0,0 0~0 D....oo..o,o.oil 0~0 0,0 0~0 0~0 0,0 1~ 14 0,14 0 ?9 wHW N'w ~
0,0 0~0 0~0 0 01 0,02 0 '
0,06 O.II6 0 F 02 '
O,OI 0
'20312
~ .
0,0\
0,18
. 0 '6 Il.ol, 0.01, 0,0 F 14 0 ~ 01 0 F 01 D~
O,D 0 '
0 0,10 0,\6 Oo'55 HHw .0 ' 0,0 0 02 0 ... 0 09 . 0 12 .. .0 ~ 0 O,D 0,26 MQDTQTOL~,~ 55 3.Jl 1.60 . 1~ 30.~ 41 0,03 0,0 M.54 CALH 55
. 08.0.1
~ ~ ~ ~I 1337 SJAttlLJTYSLtssSS 4 OCCUBHKNCFS.OUT OF. TOTAt 16559VALID TEHPKRATURE5IFFKHENCC READINGS IOO6 VAI.IO yIND OIttFCTION - ItlNO SPEED HEADINGS OUT OF TOTAL 1337 STABILITY CLASS A OCCURRENCES At.L,COLUHN5 ANO CAt.H TOTAL 100 PEHCKNT OF NET VALID HEAOlNGS aHETFOROLOGICAL FACILI>Y LOCATKO 0.70 HILKS FSE OF HHOWNS FFRHY NUCLKAR PLANT ~ ~ .'It 0I..
TEHPKRATUHK IHSTRUHFNTS 33 ANO 150 FEET AHOVE GROUND 0QS RAOWASTE 801LOIHG-GIIOUHO l.EVEt. RELEASE 33 FEET ItINO .INFOHH4TION ....wH
'9t
~'
Sheet 1 of 10
'I nb le 1. 3 (C I no ed) 51QQIX~EBCCIIZgCE EBEQUEBCIKS Qf 55laJQ QIBCCILQ 65Q ylgQ SREEQ EQB QIEEEBEBI S?ABILIIX CLASSES ~
STARILIZY CLASS R I ~ 9< OEI.TA Tc> 1 ~ 7 OKGo C/IOOM
~ a
/OWN/ FKRIIY NUCLEAR PLANT METEOROLOGICAL FACILITY55 JAN. 15.74 OKC 31 ~ .75 III NO IIINO, SPEED IHPM)
QIRKCIIM Jla5=lak la~"2D 2a"DA Sa5" Zah Za~-12'2aS" Mak 145" 2%6 25&5 IQILL ~
~
N NNK 0 '
Op 0 0 '3 -'
0,06 '
~ 15 12 F 11 0,12 0 '316, 0 0 '2 0,01 0
0 0 '
0 '4 0 F 47
~ . 0 NE 0 0
' 0 02 0 ~ 01 0 ~ 01 .0 ~ 0.
0' 0'
0' 0'
0
...0
'708 K
ESE 0
0'
' 0 '3 .
0 ' 0 ' 0 '
0.0 0'
0.0 F
0 F 08 0 ~ 18 SE 0' 0 '5 0 ~ 26 'E 00100' 0 '
0 0 F 00
'3 SSE 0 01 F : 23 0 02 ~ 1 ~ 0 ... 0~0 0 5 0' 0.13 0 ~ 31 0 05 0 F 01 0 0' 0 ' 0 F 50 SSN 0' 0 '4
'7 0,07 .
F 0,03 0 0 0 0 0' . 0 ' 0 ~ 14 SV VSV 0'
0.0 0 0 ~
Il,24 II
',07 0,01 0 ~
0.09 01 0 0 0.01 0
0 0
0 '
0,0 0 '0 0,45 II
'MNW 0 '
0 ~ .0 0 ~ 01 0 02 013020033009 0 ~ 12 0.12 0.09 - 0.02 0,01 0 '201 .
0,0
.0 '
0,37
...0 '9
'8 69 NM 0 ' 0 F 01 0 03~
11 0.15 0.40 0.1'0 0 0 ' 0 2~
~ ~
'2 F
NNM 0 ' 040t 0 ~ ~ 12 0,34 D,ll 0001 000 0 SUBTOTA 0 F 01 1~18 2434~ 74 ~
0 ~ 36. 0 05 0 0 6 ~ 90 CAL I 52 0 '
~47 STABILLI~AS~KQIBBf5~1ILJ}F XOIALM6559. VALIO f TEMPERATURE.. Olf KRKNCK ~KAOINGS 1119 VAI.IO IIINO OIRFCTION, 4IINO SPEFO REAOINGS OUT.OF TOTAI. 1147 STABII.ITY CI.ASS B.OCCURRENCES.
ALL COLUMNS ANO CaLM TOTAL~OO~ERCENT OF NKT VALIO READINGS 4
TEMPERATURE INSTRUMENTS 33 ANO 150 FEET AHOVE OROUNO RAOKASTE RUI'LOlNG GROUND LEVEL RFLEASK 33 FEET 'NINA INFORMATION'0 oMETEOROLOGICAL FACILITY LOCATKO 0 ~ 78 5IILES ESE OF BROGANS FERRY NUCLEAR PLANT
~H v Q
0 '
Table 103 ( tinued)
~ .
QIBLZEBCE?IlbQE EBEQllEHCIES QE. EIBQ QIBECIIQH 65Q MI?IQ SBEEQ
'EQB QIEEEBEUI S16BILIIX CLASSES 4 STA81LITY CLASS C 1 ~ 74 DELTA-t<> 1 ~ 5 DKG ~ C/100H BROGANS FERRY NUCLEAR PI.ANT HETEOROLOGICAL FACILITYES
..JAN lE 74 - OEC 31'5 IINP ~INn SPEED(HPH)
QIBECIIQM IIak=ld ld "3A 2a."daK S S=Zd ZaS=lZak 12a5=1Bd - lk S=24ak 2524aS N 0~0 0 ~ 02 0F 08 0 ~ 09 0 ~ 17 '4 0 F 40 0~
0 0 ~ 0 0~0 NNE O.O O.O4 ..O.or ... O.O6 0 ~ 07 ..0 ~ 02 0 ~ 26 NE 0~0 '3 0 ~ 04 0 F 01
. . 0 ~ 0 0~0 0 F 08 0~
0 0~0 0 0~0 0~0 0~0 01 .0 ~ 03. Ol ENE
'62105 0 ~ ~ 0 ~ 0~0 . . 0~0 0~0 0~0 0 F E 0,0 0,01 0 04 . 0,01 0~0 I 0~0 0~0 0~0 0
~ 04 0 ~ 10.. 0 ~ 06 0 F 01 .. 0 ~ 0. 0 ~ 0.. 0 ~ 0. 0 ~
SE 0~0 0.20 0.21 0.05 0 F 02 . 0~0 0~0 0~ o.se S
0. ~
0~0 0 0.21 0 ~ 15.
0 0.
~
12, 12 0 ~ 01 0 ~ 01 0~0 090
... :0 ~ 0 Io ~ 0 0~0 0.0 0~0
~
0'..0 0 0 0~
'428 SSV 0~0 0 ~ 02 0 F 04 0.0 I 060 .. 0 ~ 0 .0 ~ 0 ...0 ~ 0 0 F 07 0.02 '
SV VSM 0~0 0,0~,10 0 F 07 0 ~ 14 0
0.06 0 09 0 F 01 0 ~ 02 o.or 060 060 b.oe 0~0 0 ~ 0.
0~0 060 0~0 0~0 0
0 '03610
~
KNV NN 0,05 0.0 l 0 11 0 ~ 09 : 0F
~
0,13 07 0
0~
'223 . .
bo08 0 F 08 0 ~ 04 0 F 01 FI 0~0 0
0 0
0
'3
~
'9 NNV 0 07 0 ~ 06 0,10 0 ~ 27 , 0 ~ 15 0 F 01 0 ~ .0 0 F 61 .
UGTO A 2 ILII .0 99 .~ 43 ... ~ ~ 06 ~ II 4,60
~ALH 22 0 TAIIILELVV:LAS!~ISEURRENOES.OUT.OE TOTAL 16559VALID TEIIPERATURE tlIFFERENOE READINGS 739 VALIDWINO DIRECTION !INO .SPEED READINGS OUT OF TOTAL 757.STABII.ITY CLASS C.OCCURRENCES ALL COLUHNS..AHD CALH TOTAL.300 PERCEHT OF NFT VALID HEADINGS
~ ~
03 tent %
4HETKOROLOGICAI. FACILITY I.OCATEO 0 ~ 78 HI%.ES FSE OF 8ROWNS FERRY HUCLEAR PLANT QO TKHPERATURE IHSTRUHEHTS 33 ANO 150 FKKT AHOVE GROUND l9 (D RAOMASTE 8UJLDlHG GRquND LEVKL~ELEASE 33 FEET NIND INFORHATIOH. H '
E45 CO
~)
V
~ 1+04 NOWT IWNAOWSO41 VH040~ INN~ 160~ ~
E:I004nE 0 FSF 1h
gogle 1.3 (ieuoe)
JDIDI "EZCC.I AuL "E2L'fIE.S D <lb'2 DIB ZIDMWD CITED h"L D Lu" DrEEEBENI alamLLIIU CLASSL~ ~
STABILITY CLASS D 1 ~ 5< OELT4 Tc=-0 ~ 5 OEG ~ C/IOOH BROXNS FERRY NUCLEAR PLANT HETEOROLOGICAl. FACILITY+
JAN 1 ~ 74 DEC 318 75 KINO KIND 5PEFOlHPH)
QLBECEIQB Iles"la4 145=344 3494% 545=744 ZD=lZa4 12e5=1hd 1ILL5=24ak ~*& 5 xazw N 0 '4 0 ~ Ol 0631 0 F 42 0 F 41
'830 0 '3
'8 0 '9 0 ~ 35 0 ~ 12 II F 02 0 ' 0.0 0,0 2e30 NME 0 0 0~0 ~ 66 NE 0
'201 0 '0 tlat 0~
',II2-0 12 0 ~ 06 D~ Ol 0~0 0
.1 0 ~ 90
~D
'5 F ~
0 0,36 0 ~ 22 0,03 0 ' . 0,0... 0,0 0 E 0,02 O,OI O,DS 0,23 9,3~.,34 I 44 0 ~ 22 I 45 0 ~ 04 0 ~ 36 0 58 0.02 0.28 I 0 0 0..
03
=0 '0~0
~ 0 0
.0
~
0~.90 0 .0,53 SE 0 ~ Ol 0 '706 0 35 0 ~ 04
'2 ....~0 , 0 0 ....0 ' ..
0 0
0 0 0 3890
'26965 I~
~ ~ ~ .1 ~
5 0 ~ 01 1 ~ 0 ~ 75 0~18 0 EO ~ 0 0 0' 2 SSN 0,01 0 33 23 0 DT 0801 0 ' 0 ' 0' 5 It KSK 0,02 0~01 0,33 0,54 II,64~0,56 0 ~ 23 D,D3
,22 0
0 F 01 23
0 ~ 0 0 ~
0 '
~ 0 0.0~
0 ~ 0 0 '2ftl
,0 ~
x 0 35 0 05 0,51 15 0,0 0,0 2 ~ 51
'xNK Nx QNO 0 '
0 F 01 0
0
'8.
10 0
0
'2
~
'4 0 0
'2
'0 F 62 0,85 D~
0.36 0 40 0 F 05 03 0,0 1 0 ~ 01 2,06 2,04 NN'l4 0 ~ 01
~
g 0 '6 3 1.26 O.SO DE O,O I O.O 2,16 0~8
~ 8 5,59~ Tl 9,09 0 Oll CALH EE 0 F 01 4640 ST481 TTY C ASS D OCCURRENCES OUT OF TOTAl j6559 YA~D TEMFERATURf OTFFERENCEJ3EAOTNOS 4564 VALID 'KINO DIRECTION KINO SPEED READINGS OUT..OF. TOTAl. 4648 STABIl.ITY CLASS O OCCURRENCES Al,l. COLUHNS AND CAI H TOTAl .)~OPERCENT PF NgT VAI.IO f\EAOINGS 4HETEOROLOG!CAL FACILITY LOCATEO 0 '8,HILES ESE OF BROXNS FERRY NUCl.EAR .Pl.ANT TEHPERATURE,INSTRUMENTS 33 AND 15ll FEET ABOVE GROUND RaOKA5TE BUILDING-GROUNO LEVEL RELEaSE 33 FEET KIND INFORMATION'Eannt lo nf 1 A
Table 1.3 (lOCInued) ~ .
IBI~CE5IKGE EBEQllQCIES QE. ElBQ QIBECIIQU hlQ RIBQ SBEEQ CQB QIEEEBEHI SIhBILIIX CL8R'KR ~
DEGAS STAR ILITY CLASS E'
'dl DELTA TC+ 1 ~ 5 C/100H BROMNS FERRY NUCLEAR PLANT HETEOROLOGICAL FACILITY>
JAN ID 74 OEC 315 75
. MINP MIND SPEED{HPH)
.QIBKCIIQB Qak=lak Ia5=2ak 24Uak 5D.5=44 Z6=12ak 12D.'R=l.hd 145=hat iiL4.R IQI8L N
NE 0
0
'6 0,07 10 ',77'5 0 0,47 0 '2 0 ~ 5II 0 ~ 45 0
0
'726
~ .. 0 '6 0 ~ 13 0,05 0
0,0
~
~
Ol Ol 00-00177 0 '
0 '
1 ~ 77
'20810 0
'874 0 0
'53114 02, 1 ~
10 0 0 ~ 15 .. ' ' ' '
E 0 '3
~
0 ~ 0 ~ 44.
. . 0 0~
0 0~
. 0
'0 ~ 0 0
0 ~ 0
. 0 0~0 0
1 ~
SE 0 '3 0, 22~ 00 2,31 I ~ 07
'6 1,01
'1 0,53 0,0 "
0~0 O,D 5,95 5 S.F.
14 '4
~ 0
'4 . 0
'318, . 0
'3 F 09 . .;0
0 '
~ 0 .... 0 '
.. 0 '
2 16 S 0 0 .,
~
0 0 0
'8
~ 0 0 F 78 SSM 0
'234 . .. 0~
'412 0 F 08 . 0 ~ Ol. 0 ' ., ' ' 1930 SM
'25~4.,56~ '6 0
0 0 0 ~ Ol 0~ ll -0 '
..0 ~ 02.
0' 0 ~ 0
, 0' 0.0 0 '2 1.19 M
'MNM NM 0
0 0
'4
'5 0
0,15 0,15 0.65 0,16 0 21, 0
0
~
~
0,09 13,0 25 0 ~ 15
~
0,26 13 '
)04
'9 ..
~ 06
~
00 0~0 00 0~0 167 0 ~ 67
'6, '9 3~
0 0 0 F 85 50 0 . 0 0 '1 , 0, ~ 04....... 0 ' .,
0 0 ' F 88 53 . D ~ 20 .D 11..0 0~0,76
~ 9
~4764 TA TT 4 33ERRIEECED DUJ~F 70744 16559 VALID TEMPERATURE qIFFEREMCE READINGS 4700 VALID MIND DIRECTION MIND SPEED. READINGS OUT OF TOTAL 4764 STABILITY CLASS E.OCCURRENCES ALL COLUHNS AND.CALH TOTAL.100 PERCENT OF NET VALID READINGS 4HETEOROLOGICAL FACILITY LOCATFO 0 ~ 78 .HILES ESE'OF BROMNS FERRY NUCl EAR Pl ANT Ch.td d TEMPERATURE INSTRUHENTS 33 ANO 150 FEET ABOVE GROUND 'WM O3 00 RAOMASTE BUJLOING"GROUND.IEVEL RELEASE, 33 FEET WINO INFORHATION~ w&$
44 H EOS O 0
Sheet 5 of 10
TOMO l. 3 ((Odauad) olQIQI-LLBCKUlbUL KBKDJUKBCIK5 QK 'KIJQ QIBKCEIQ dUQ tlUQ SLEKQ LU28 QILKLUKUI SE4QILIIX CL4SSLi STABILITY CLASS F 185'.,UFLTA TC ~ 4 ' OKG ~ C/IOOH BROEENS FERRY NUCLEAR PLANT HETKOROLOGICAI fACILITYEe JAN 1 ~ 74 OEC 31 '5 VINO HPH Qldd~CIIM 9ah=l44 la5=344 ZaKQA WINO SPEFO h*5"Ia4 Zah=lZA 1Zal=lhat 145=2tak 2 Kl IQIhL
'4 N
NNE NK 0
0 0
~ 10 12
~ 10 0 F 45 0 ~ 85 0 51 0
.0 ~ 36..
0 ~ 15 0 ~ 12 0 ~ 10 0 '2 .. 0 '2 '
0~0 0~0
~ 0~0
~
0~0
0. 0~0 0~
0~0 0'... 0~0 0
0
~
0 ...,1 1 ~
0 03 43.
'875
~
ENF 0 09 0 F
40 0 06 . 0 0 0 ~ 0....-.0 0 . 0~0 0 0 0 ESF.
SE 0,06 0 F 07 0 '5 0,93 0,72 1.34 0 36 0,20 0,61 0~ 0 0,04 0 ~ 23 0 ~
0,0 O.D8 0
'.0 0~0 0,0 0~0 0~0 0,0 0~0 0~
0,0 0~,73 1 ~
2851 35 SSE 0 ~ 14 0 ~ 10 ~ 0 0 0 0~0 1 23 5 0 F 09 0.50 0.43 0.30 0.20 ,0.0 0.0 0.0 1.52 SS'N 0 06 0 16 0,07 0,07 ' ' '0 ' 0,0, 0,0 0,30 SW WSV 0 '4 F
0.05
~
0 ~ 15 0 ~ 10 0 ~ 0
~ 0 ' ~ 0 0~0 0 '0 4 ~ 17
'402 ' '913 WNW 0
0 0 0 ~ 02 0,03 0,01 0 F 01 0
0 '.0 0 0 0 ~,0..
~ 00~
0 ~ 16 0 ~ 119
'8 Nod NNW 0 ~ 04 0 F 08 0
0
~ 12 33~034 0 ~ 10
'0 ll 0 F 01
~
0~0
.0 ~ Ol 0 F 01
.0 ~ 0 0 ~
0.0 0 060 0,0 0
0 ~ 87 3,41 3;lz 0.42 .
o.o~.o .o ~ 0~3.5 CALH Eo 0807
~206 97 EEUETY~45,'~FgU~RRFM ~I~FDT4~6559~1djl 7ENPE2A7URE 377FFJJlENDEJ\EAO7585 2267 VAIJD MIND OJRggTQON ~ WINO SPKEO READINGS OUT OF TOTAL 2286.STABILITY CLASS f'CCURRENCES A~OLUHUNS APP gg.H TATAlggl} PQRgENT OF NET, VALIO READINGS
~ +HKTKOROLOGICAL FACILITY. LOCATEO 0 ~ 78 HILES KSE OF BROGANS FERRY NUCLEAR PLANT TEHPEPATURE INSTRUDEENTS 33 ANO 150 FEET ABOVE GROUNO RAOodASTE 8UILOING GROUNO LEVEL RFLEASE 33 FEFT IINO INFORHATION~ .
Y))l)le l. 3 (C2)>><)V21)
MQIUIAEQCEMIAQf. EIIL'QUEUCIES QE KLUQ QIGECIIQB AIIQ IIISQ SKEQ EQ)I QLEEEIIEUI SIAIIILIIXCLASSt.S CLASS O 'TA)IILITV DELTA T )' ' DEG ~ C/100H BRO)IHS FERRY HUCLEA)I PI.AHT HFTEOROLOGICAI. FACILITYED JAN 15 74 DEC 31 '5
. Iilllb OIOO 'iOEED(OPIII lllflECE105 11 b=l 5 1 5=3 5 2453 5 5 5=7 5 2 5-12 5 22 5-25 5 20 5 20-1 2 25 5 IQIAL H
.HNE 0929 0 ~ 20 0 '3 ...
I ~ 28 0017 D ~ ID 0 ~ 04 0 ~ 02 0 ~
.0 ~ 0 0 0 ~
000 0 0~0 0~0 00 0 0~0 1 ~
1,60 43 o.n '
NE ENE.
0 ~ 14 0 ~ 09 .
0 F 07 0
0 0
'24466
~
.. 0 a ~ 02
'2 0015 0~0 0~0 0
0 I 0 0
.o.a
~ 0 0
0 0
~
~
0 0
0~0 0 ~
09 0 0
0 0
F
~
EBB 60 63 .
F. 0
~ 0
~
F ~
04 0 35 0 ~ 01 ...0 ~ 0 0~0
' 0 ' 0 0 0 0 0 40 OE F
0,15
,19 '
- DE
~
F 74 41 0,09 0 13 0
0
'3
'4
~I ~
0 ~ 01 0 ~ 02 ..
0 ~ 0 0~0
~
000
.0 ~ 0 0~0 0~ 0...
F 1 ~ 0?
0 F 09 S 0 ~ 14 D 54 0,14 0006 0~0 . 0~0 0~0 0~0 ~
0 'B SSM 0,07 0,00 . 0,0 ' 0~0 ' 13 SW 0.00 0 '5 0.04
~
0,0.
0 0
0 ' 0~0 0
0 ~ 0 0~0 0~0 0~0 0 ~ 0 0 ~
0911
,0 ~ , , .090 ~ ~ ~~ ~ ewe 0 ~ 0 0 ~ 0 0 ~ 0 0~0 NOH D,OI D.04 -0 ~ 0 II ilk'N 0,07 0 ~ 06 0 F 01
....00,01 ~ 01 0
0
~
~
0 0
0~0
...0 ~ 0 .0 ~ 0 090
.0 ~ 0 ', 0~0 0~ 0, 0 F 06 0 ~ 14 NM 0,07 0 ~ 09 O+0 0~0 0~0 0~0 0~0 0 ~ 17 NHV 5430. 0 ~ .30 ...5 10 0 '4 0~0 0~0 ...,0 ~ 0 ,.09 0.. 0 '8 MllOIQI)IL"' s9Ct,... . 9 ~ 23 .... 0 '3 . 050 . >> 0 ' ' Os0 F 80 CALH P P>.0.9.
~679 STA)IILIZLCLASS~CCVRRENCES OUT DF .TOTAL 16559 VALID TEHPERATUHF. DIFFERENCE READINDS
$ 612 VALID,.MIND DIRFCTIOH IIIND SPFEO READINOS OUT OF TOTAL 1620 STABILITY CI.ASS O OCCURRENCES ALL COLUHHS AND. CALH.TOTAI. 100 PEHCEHT OF NET VALID READINGS
.- ~ -~tdA..
4HETEOROLOOICAL FACILITY.LOCA'TEO 0 ~ 78 HlLES ESE OF'RO'RNS FERRY NUCLEAR PLANT ~R OC) 07 TEHPFRATURE IHSTRUHENTS 33 AHO 150 FEET ABOVF. GROUND RAO'NAST+BUILOING (AOUNO I,EVEI RELEASE 33 FEET MIND IHFORHATION~
Sheet 7 of 10
Tal>10 1.3 ((NIaaod)
JOIt.1 P.E.RLt~IA4l I.. ' 5'Lcd ' "I'E.'=LLII'" Its) SPt.
OLLLLXL~SI SIAi.'ILIA LLASftf L'uL STAbILITY CLASS 0
-I 45< ItE LTA-T<i-045 DEG ~ CIIODtt BROitNS FERR Y hUCLEAR PLANT METEOR(tlliGI GAL FACILI TY4 JAtl l. ~ 74 - DEC 31 ~ 75 Mlkn 'MIND SP EEDIMPtt) 7IEEEEIIIIH 0 4=1M 2 4=3 4 3 S=S 4 5 3=2 4 2 3=12 I 12 h=lB t 1S '5=26 I' WZAW ZOZAL h 0.0 0 ~ 02 0 12 0 ~ 23 0079 0 ~ 92 0 ~ 31 0 01 2 40 NtlF NE 0 401 0 001 0 ~ 10 0 ~ 21 0 0
~
~
34...
20 I ~ 04 0 ~ 72 0 ~,'t
~ 4 6 0 ~ 32 0 '3
~
0 01
. 040..
~
040 7
I 45 ENE 0 ~ 01 0 03 0~07 E 0 ~0 0 04 0 11 0 17 0 19 t 0 ~ 01 0 ~0 0 0 0 52 n.l ESE Sb 040 0 ~0 0413 0 2Z 0 ~ 17 n.55 0 18 0 54 0 ~ 4424 Z5
'72 ')0 81
-07 0 ~ 48 0 02 0 19 0ll 9
4 ~ 04 S,S SS'M SM E'
'M 0 DJ 0 0 0+0 0 001 0~
0,32 0018 0 .II 0 ~ 24 7
040 0 ~ 26
&.,20 0,33 0
0.42 Oa31 47~4~ 75....0
.0.
II 20 22....0.54.
0..95 0 ~ 78 0 55 059 0 ~ 47 D 53 4
039 029 0.22 0 !8 015
.0.15 0 04 3 'U
..2.09.
Zal1 55 M 0 001 0 ~ 10 0 ~ 39 0 040 0.56 0.48 0 ~ 28 0 21 2 ~ 43 0 ~ 09 0 ~ 22 ~ 40 0~ 55 ...0 ~ 30 0 ~ 21 52.
MNM O ~
'058. 2 ~
NM tl AM 0a0 0010 0404 ~..21 '
Oa43 0047
.II ~ 20 1018
..Oi.73...,..
0092 La00 0
Q 0022 0007.
3 ~ 92 3024 SURTOTAL 0 ~ 07 1093 29 59 11 9 9 6 4 05 89 CALM ~ 0.01 6114 STABILITY CLASS D OCCURRENCES OUT OF TOTAL 16481 VALID TEMPERATURE (IFFEREttCE READINGS 6038 VALID ilIND DIRECTION - Mltln SPEED READINGS IEUT OF TOTAL 6114 STABILITY CLASS 0 OCCURRENCES ALL COLUMNS AND CALM TOTAL 100 PERCENT OF NET VALID READINGS 4METEOROLCGICAL FACILITY LOCATCD 0 78 MII.ES ESE OF BRUMNS FERRY NUCLEAR PLANT TfHP'ERATQtt E" lhSTRQME7I~H 'Q% 19D FRET'EN ~GtiUttn MIND ItiSTRUMENTS AT 300 FEET ABOVF GROUND 24l ~~ ~ 0 ~2- lh
'('nble 103 (, ntinued)
~ .
,LLa.CLbI IALLUaURLNCL L alLA.'>'LLD >
EIII: ALL JIIN(> LII(ECILI>L5 dROIIHS FF RII Y NUCLEAR PLAk( NET F(tRULOCI CAL FAClLlTYO JAN 1 ~ 74 - f>EC 31 ~ 75 It llto 32220>>0~ 5=2 A~ 5 3-5 5 5=5 5 It lko SP EEO(HPII) 5 5=3 5 5 ="22 5 12 5=18i4 1haD=24~L, ... &4~S . IUIAL.
N 0 ~ 02 0 ~ 23 ' ~ 29
. 0046 1 ~ 71 109h 0 .51 0.02 5 20 KHE HE 0 ~ 03 0 ~ nl O Zr V ~ ) '5 n.38 0 ~ 40, 0.!4 U ~ 4" F 04 1 ~ BU 2
)
'681
~
0 ~ 60 0~ 0 0 ~ 07 0 03
~
h ~ 30 5.7) t U ~ UJ U ~ 1'> V ~ 36 0 ~ '>6 1 ~ 25 UNe5 ~ 21 UNV) 3 ~ 37 F 0001 O ~ 23 0049 0 51 , ~ 1 ~ 07. 0 37 0 04 D.o, DA 2087 EKE SE
'S n.nj 0 004 0 ~ 08 0 ~ 03 0034 0 ~ 56 V 064 0 ~ 48 R
0 ~ 53 1 019 0099 0 ~ 83 0.58 1 ~
1 ~
1 ~
33 22 04 1
3 2
062 3063
'1
~ 7t>
10)2 2 174 2 ~ t>b 2 ~ 69
~ ~ ~
0 ~ 29 1 ~ 3')
~ 24
.n8
.. OAU5 0,'r 6 U.(
(>074 7
405(
11.4>4 10061 906)
~ 4U ~6 V ~ >r6 ? ~ )I 20$ ) 1 ~ 42 O."0 8 ~ 42 Sit 0 ~ 04 0 ~ 44 0 ~ 63 0 ~ (>7 1 0'77. ) ~ 8tt It 5 M 0 ~ 02 V ~ 37 0,90 0 ~ bb 1020 M
MKIt 0 ~ 03 0 ~ 27 0 77 0 '4 p . ~
1 ~ 36 0 003 0 ~ 18 0 ~ 42 0 ~ 89 1 39 0 ~ 90 0 ~ 42 0 ~ 26 4049 Hlt 0 ~ 02 0 ~ 31 II ~ 70 n.er 2 ~ 0(I 1 ~ 5 0 85 0.27 h.'%7 K(IM 0003 U ~ 23 0047 0 ~ 53 1 ~ 54 2 ~ 27 0 ~ 71 0009 5 ~ 87
'UAIU>AL b.>$ 5 ~ 27 '9+98 1 1 ~ 54 30.45 27 '5 10063 3098 99 ~ 88 XLH a g f
~
~
'.6850 VALlD klkD 5TAECTlok It)HO SPEED READ)k(S UUT OF 17520 TOTAL H(IVRS 0>
96 ~ 18 PFRCEk'T
~iL cui(Ki'S A5 aik Yo)AL iot) PE'acEHT oF'ET YAL)o REAO(N'Os'ETEDRIILO()CAL AC)LITY L(iCATCO 0 ~ 78 II)LES ESF OE 8R(IMHS FERRY NUCLEAR PLAkT NIRU IIISIRUNI 0~I>I 300 f>2 I ANIIV> >RUUNU I'hoot 1 A nF 1A
Page 35 BF TI 47 6/21/79 TABLE 1.4 BROWNS PERRY NUCLEAR PLANT LAND SITE BOUNDARY DATA Sector Distance m
~/'levated Elevated
~D/
Ground Ground D/I/
N 1,550 1.88(-10) 9.55(-10) 2.26(-6) 5.66(-9)
ENE 1,400 1,370 1,400 4.06(-ll) 3.51(-11) 1.65(-11) 7.71(-10) 5.72(-10) 4.14(-10) 1.02 (-6)
7. 93 (-7) 9.34(-7)
'. 2. 05 (-9) 65 (-9) 3.18 (-9) 1,570 6. 08 (-11) 4.73(-10) 8.04(-7) 3-34(-9)
ESE 1,470 2. 79 (-11) 4.27(-10) 6.81(-7) 3.39("9)
SE 5,460 9. 33(-9) 3.18(-10) 1.11(-') 3.83(-10)
SSE 2$ 740 1. 82 (-9) 5.99(-10) 7.03(-7) 1.90(-9) 25380 8., 43 {.-10) 5. 47 (-10) 1.19(-6) 2.51(-9)
SSW 2,410 1.08(-9) 6.61(-10) 1.32 (-6) 2.40(-9)
SW 2,160 4.93(-10) 5.60(-10) 8.50(-7) 1.45(-9)
WSW 3,120 1. 87 (-9) 3.16(-10) 4.90(-7) 6.11(-10) 2,350 5. 23 (-10) 2. 82 (-10) 8.83(-7) 1.37(-9) 3,120 2.66(-9) 4.34 (-10) 6.16(-7) 1. 38 (-9) 3,440 7. 97 (-9) 9. 76 (-10) 1.29(-6) 2.84(-9) 10620 1.73(-10) 1.09(<<9) 2. 20 (-6) 4. 84 (-9) s/m'.
m
3. 1.88(-10) ~ 1.88x10
TABLE 1.5 Page 36 BF TZ 47 6/21/79 DOSE FACTORS Ft'R SUB.'KRSTON I'.i bOBLE CASES DFBX DFS~ DFB Kr-85m 1.17 (+3) 1 21{+3) 1.46{+3) 3.86 (+3)
Kr-85 1.61(+1) 1-69 (+1) 1.34 (+3) 3.83 (+3)
Kr-87 5 92(+3) 6.05(+3) 9.73 (+3) 2.01 (+4)
Kr-88 1.47 (+4) 1.50 (+4) 2.37(+3) 5.72 {+3)
Kr-89 1.66(+4) 1 59(+4) 1.01(+4) 1.88 (+4)
Xe-13la .. 9.15(+1) 1.53 (+2) 4. 76 (+2) 2.18 (+3)
Xe-133m 2.51(+2) 3. 17 (+2) 9-94 (+2) 2. 90 (+3)
Xe-133 2. 94 (+2) 3.46 (+2) 3.06 (+2) 2. 06 (+3)
'I Xe-135m 3.12(+3) 3. 30(+3) 7.11(+2) 1.45 (+3)
V'.
Xe-135 1.81(+3) 88 (+3) 1. 86 (+3) 4. 84 (+3)
Xe-137 1.42 (+3) 1.48{+3) 1. 22 (+4) 2.50(+4)
Xe-138 8.83 {+3) 9.00 (+3) 4. 13 (+3) 9-25 (+3)
~
Ar-41 8. 84 (+3) 9. 76 (+3) 2. 69 (+3) 5.54 (+3)
1. are~/y per ~~Ci/u .
2. nraa/y per yci/n .
3. 1.17(+3) ~ 1.17xl0 .
TABLE 3.6 " Page 37 BF TI 47 6/21/79 STSKE ELEY~NT TP~!iSF& ATA B~v Ffir )
El&eII Ve /Sall ~Ni1k di c 8 T.CE-02 C 1.25-02 ha Qoc~ 02 4.CE-02 l.li C}
~
P 2 c=-C2 Cr 2~a r>
r.~ ta Fe ).25-C3 Co 1.CE-03 hi 1 c- <2 5.7E-C3 Co 1.25-01 1 C=-"2 Zn 3 g P'P F.b al Sr 1.75-02 P.G r
-C-'.
2.=5-"3 (-.5 Zr 'f~,~ wt 5.:E-"5 hb 9.-'i-"3 2.5E-03
. Yo 1.25-01 7.5E-C3 Tc 2 g 2.5K-C2 Ru 5.0E-C2 1.0E-C5 FA 1.3i G1 l.GE-C2
~a 5.0i-".2 1,3i 03 1.CE-C3 1 2 ~i-02 6.0 -03 Cs 1.CE-C2 1.2E-C2 Pa La 5 ii 2.=E-G3 03 4.0E-C>>
5.0i-"5 Ce 2.55-03 1.0 Pr ~ 2.52-93 -.'.0E-C5 hd 2.C -03 5.0.-~5 l.ii-o2 S.oi-i>>
hp 2.5E-03 S.OE-05
'2 Page 38 TABLE 1 BP Tl.47 6/21/79 DOS: FACTC":S I".FA.'T THYROID Radionucliie Inhalation (=re=lvCi) In estion (c.re=/ Ci) 8-3 4 62(-7) 3.08(-7)
W ~
C-14 3 79(-6) '.06 (-6)
Cr-51 4.u.(-8) 9 20(-9),
Te-132 1-99(-7) 1..52 (-5)
E-131 1 06(-2) 1.39(-2)
E-132 1.21(-4) 1..58(-4)
E-133 2.54 (-3) 3.31(-3)
E-134 3 18(-5) i 15(-5) 4 97..(-4). 6.49( ')
Table l.8 'T R!0 oosE FAcTons roR sTAxolxG Ox coxrhxtwATEo GRouxo Page 39 (mree/hr per pCI/m ) BF TI 47 6/21/79 Elephant
~Tota1 Bod 8-3 0.0 0.0 C-14 0.0 0.0 N-24 2.50E-OB '.90E-OS P-32 0.0 0.0 Cr-5'I 2.20E-10 2.60E-10 ra-54 '.80E-09 6.80E-09 r~-56 1.)OE-OS 1.30E-OS Fe-55 0.0 0.0 Fe-59 S.OOE-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-OS 2.00E-OS Xj-63 0.0 0.0 Xr-65 3.70E-09 4.30E-09 u-64 1.50E-09 1.70E-G9 fZn-69 4.00E,-09 0.0 4.60E-09 0.0 Br-63 6.40E-11 9.30E-11 Br-6$ ).20E-OB 1.40E-OS Br-85 0.0 0.0' Rb-66 6.30E-10 7.20E-10 Rb-ES 3.50E-09 4.00E-09 Rb-69 1.50E-OB 1.80E-OS Sr-89 5.60E-13 6.50E-)3 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-OS Y-90 2.20E-12 2.60E-12 Y-91H 3.80E-09 4.40E-09 Y-91 2.40E-) 1 . Z.70E-))
Y-92 f;60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Xb-95 5.10E-09 6.00E-09 ro-99 ).90E-09 2.20E-09 Tc-SR'I 9.60E-)0 1.)OE-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.2OE-09 Ru-)05 4.50E-09 5.10E-09 Ru-)C6 1.50E-09 ).SOE-09 A9-))C( 1.80E-OS , 2.)OE-OS Te-12% 3.50E-11 4.80E-11 Te-)27.". l.'IOE-12 1.30E-12 Te-127 .1.00E-11 '1.10E-11 Te-12'e-129 7.70E-10 9.00E-10 7.10E-10 8.40E-10 Te-1 31M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 ).70E-09 2.00E-09 1-130 1.40E-OB 1.70E-OB I-) 31 2.80E-09 3.40E-09
)-) 32 1.70E-OB 2.00E-OS 1-133 3.70E-09 4.50E-09 k-) 34 1.60E-OB 1.90E-OS 1-135 ).20E-I 1.40E-OB Cs-134 1.20E-OS 1.40E-OB Cs-136 1.50E-OS 1.70E-OS Cs-137 4.20E-09 4.90E-09 Cs-136 2.)OE-OS 2.40E-OB Ba-139 2.40E-09 2.70E-09 Ba-140 2. )OE-09 2.'40E-09 Ba- I41 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-OS 1.70E-OS la-142 1.50E-OB ).SOE-OB Ce-141 5.50E-'IO 6.20E-10 (e-143 2.20E-09 2.50E-09 Ce-144 3.20E-IO 3.70E-IO Pr-)43 0.0 0.0 Pr-144 2.00K-lO 2.30E-)0 M-)47 ).OOF-09 ).206-09 M-)87 3.)OE-09 3.60E-09 Xp-239 9.5OE-IO ). Inr.nn
1.0 0.9 0.8 D
z 07 z
0.6
~
2 0.5 z
0 o OA CC 0.3 0.2 0.1 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Plume Depletion Effect for Ground Level Releases (All Atmospheric
~ w 00e Stability Classes) ~'c o
rz% x.x comzmim) 1.0 STAB LE NEU TR AL (E,F;G) 0.9 0.8 D
0.7 U UNSTABLE 0.6 (A,B,C) 0.5 Z
0 k- 04 CC 0.3 0.2 0.1 0.1 1.0 10.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Plume Deptction Effect for 30m Releases (Letters denote Pasquill Stability Class)
PIGURE CONTINUED) 1.0 STABLE (E,F,G) 0.9 NEUTRAL su 0,8 (o)
D 0,7 UNSTABLE U (A,B,C) z 0.6 g
W pg z
0 o 0.4 K
LL 0.3 0.2 0.1 0.1 1.0 10.0 1DO.O 2004
+v PLUME TRAVEL DISTANCE (KILOMETERS)
Plume Depletion Effect for 60m Releases (Letters denote Pasquill Stability Class)
PIGURE CONTINUED 1.0 NEUTRAL (D) 0.9 0.8 D UNSTABLE (A,B,C) 0.7 .
Q STABLE (E,F,G) "
z. NO DEPLETION z 0.6 (FRACTION REMAINING 0) 0.5 zC3-0.4 0.3 0.2 0.1 0.1 1.0 . 10.0 100.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Plume Depletion Effect for 100m Releases (Letters denote Pasquill Stability CI'ass)
Page 44 FIGURE 1.2 BF TI 47 6/21/79
$ 0-3 lt."
W D
Ct:
10 5 10-6 10 7 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (K lLOMETERS)
Relative Deposition for Ground Level Releases (All Atmospheric Stability Classes)
4 FECURE 1. 2 (COaVl I?iUED A Page 45 BF TI 47 6/21/79 UNSTABLE (A,B,C)
I I l l f NEU TRAL
NEUTR Al I i STABLE I I I
~ ~
c I I
STAB L E (E,F, G)
I I 1.0 10.0 100.0 200.0 PLUME TRAVEL DlSTANCE (KlLOMETERS)
Relative Deposition for 30m Releases (Letters denote Pasquill Stability Class)
~
0 C'.VVACe 4, ~ C lrV;\l l ~ 4LLi)
Page 46 BF TZ 47 6/21/79 l
'Ui".STABLE (A,B.C).' ';
NEUTRAL (D) i ~ I I I I I
' I ~
~ 'i ~ i I ', i i e I I l II I ! e,'i
.ST~~ L CC NEUTRAL '
I-K o 10-6 I-t I ' ~
I i ~ I
~
i ~
I i '
I! III I-CC STABLE (E,F.G):
'I ~ '. i I r ~
I I II'0-8 0.1 1.0 10.0 100.0 200.0 PLUi11E TRAVEL DISTANCE (KILOi'1ETERS)
Relative Deposition for 60m Releases (Letters denote PasquiiI Stabiiity CIass)
FIGURE 1.2 (CONTINUED Page 47 BF TI 47 6/21/79 I UNST ABLE (A,B,C)
Ct:
UJ I- NEUTRAL (D)
K 10-6 I I i I
I I Lu O
tLl 0
l-tu S TABLE (E,F,G) ts:
NO DEPLET 10 7 10-8 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Relative Deposition for 100m Releases (Letters denote Pasquill Stability Class)
FIGUR .3 O.
GASEOUS RADWASTE TRHATHENT SYSTEM FLOW DIAGRAM eaaaaaaeueaao ISroutl a Otf FISSION OT OTH(R f a~~~l ~ail 4A'J RI(ohtaHIR (RAR(OIL STSb Navi colo(ks(k kv(I'(ll "~ (a
(+i+ j ~" INK(ak (OL ART iii WATC II 5(fata(ok f C.f. 10$ 0atoiA Iaaaavi aa LIa IaaaaI ~OVta Sl(AN Aik OL((0 ST(AN CATALTTIC R((ah(4k(R
((0 li Ia I) 1 5 vnfak (t R(40) ~ 4 jSNAII Coal liiC Wal(R 5 OII-Hvlllak l, f cas tlkl AIA ill(lok AS((halt t 5 I AN Cll(llkS off CAS (414(NS(k to( IRAT fR (t Rfo 0) ooiat to/T (oaoIHsat(
OIIIokaIIA To LIAIH J (Oal(HIIR COIIDIHSATC TRAIN
'to Halo Ckavit t Oualk (OHOIHSIR At 51ARIVf CRAVII1 okalllt Iaaf 5 Ar Stakr Vk )
4 (oaO(ts I( .----~ I I civ(4L siavnoN HO(Our fif(
OAAIN ((TISTQKe J Ref(A(a(c occvNt Ikaai(kf(ATION .L off cA5 TTTT(N tel(L ~ ~ 48c'Iolo StatACC fan ((O (RW) CoiL CLTCR CTISTOR'a 1 (LIH4 mal(R R(fIO((RATION Na(tail.
t A(O'O t(lukv 10 CORVIC v A tlat(k SIT(ol Hail RA(aaa(TIIC ARIA COIAINT(0 CIT(4L fOW(t Svf(LT (05$
5 SfANORT CAR STRIP TR(AIN(Nf fACI(llT QH(AT(RS CHANC CAL I Rfa(IOR (R TVROIHC CLOC t
AOSORO(RS ~v(a AATIO( (TRAV(T AIR CAS R(V(A1(R lOI 2
((If(IRI() all(R(iilf v(RT fk(fRP 0 Itkstvkf (t R(oo) C R(a('OJ)
CO%(R (IHO(R $ (R $ (tata(ok (t Aco'0) (c Rfq'o)
CHAR(OIL AOSOkt(R ICSS(LS IN CONSTANT TCNt(RATVR( vaVLT 7 f f'ORNAL ORAIR (TO(RW) 00 AIA CONOITIOHIH4 HH (0
~H UHI1 (( R(0'0)
CO NQT UPDATED s
y~
Page 49 BF TI 47 6/21/79 2 Li uid Effluents 2.1 Concentration 2.1.1 RETS Re uirenent Specification 3' A 1 of the Radiological Effluent Technical Specifi-cations (RETS) requires that the concentration of radioactdve material released at any time from the site to unrestricted areas (see Figure 2.1.)
shall be limited to'he Maximum Permissiole Concentration (MPC, attached as Appendix I) specified in 10CFR20, Appendix B, Table II, Column 2 for nuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to- 2xl0 " pCi/ml, total activity. To ensure compliance, the following approach will be used for
'I each release. ~
wl 2.1.2 Prerelease Analysis Prior to release a grab sample will be analyzed for the concentration of each radionuclide.'
C~ C where:
C ~ total concentration in the liquid effluent, pCi/ml.
C i ~ concentration of radionuclide i, pCi/ml.
2.1.3 MPC-Sum of the Ratios The sum of the ratios (R ) for the release will be calculated by the following relationship.
R a C
A MPC
+
C
-B MPC
+ ~ ~ ~ +
Ci i ~ +-C n
MPC n
(2 2)
Page 50 BF TI 47 6/21/79 where:
.P C
i ~ undiluted effluent concentration of radionuclide i; as determined in Section 2.1.2, llCi/ml.
MPC the MPC of radionuclide i pCi/ml-R ~ the sum of the ratios for the release.
For prerelease and post-release analysis each Ci is first assumed to be unknown and the MpC is then alp pCi/ml for each radionuclide i. If the R calculated is too large for equation 2.3 then the appropriate MPCi will be used for each C . There is one liquid release point into the discharge canal by one of 3 possible modes.
-" S Radwaste helper
..- opera pumps 8 200,080 gpm/pump 3 pumps 8 150,000 gpm/pump Discharge closed 50,000 gpm conduit The folio"ing relationship will assure concentrations are within allowable lir~ts.
f(R-1) < F (2. 3) where.
f~ the radwaste flow rate (gallons/minute) before dilution.
R ~ the sum of the ratios of the release as determined by Equation 2.2.
F ~ minimum dilution flow rate for prerelease'nalysis.
2.2 Instrument Setnoints 2.2.1 Set oint Determination
~ ~
Page 51 BF TI 47 6/21/79 The respective alarm/trip setpoints at each release point vill be set such that Equation 2.3 is satisfied. The methodology describing the setpoint determination is contained in Technical Enstruction 45.
2.2.2 Post-Release Pmalvsis A post-release analysis vill be done using actual release data to ensure that the lie>its specified in Section 2-1-1 vere not exceeded.
k composite list of concentrations i (C.), by isotope, vill be used with the actual liquid radvaste (f) and dilution (F) fZov rates (or volumes) during the release. The data vill be substituted into Equation 2.3 to demonstrate compliance with,the limits in Section .2.1.1.~0 This data and
~l setpoints vill be recorded in auditable records by plant personnel.
2.3 Dose 2 3.1 RETS Recuire=ent Specification 3-8.~.2 of the Radiological Effluent Technical Specifi-cation (R~iS) requires that the dose or dose co~t-ent to an individual from radioactive naterials in liquid effluents released to unrestricted areas from each .reactor (see Figure 2-1) shall be limited:
a. During any calendar quarter to < 1.5 mre= to the total body and to < 5 mrem to any organ, and
b. 'During any calendar year to < 3 mrs to the total body and to < 10 mrem to any organ.
To ensure co"pli,ance, cu=ulative dose calculations vill be perfor ed at least once per month according to the following methodology.
Page 52 BF TI 47 6/21/79 2.3.2 Monthl Anal sis Principal radionpclides will be used to conservatively estimate the monthly contribution to the cumulative dose. If the projected dose exceeds the above limits, the methodology in Section 2.3.2 will be implemented.
The following radionuclides contribute at least 98 percent of the total estimated dose based on four years of operational source terms.
Percent of Fish Dose Percent of In estion Dose
~Th roid
'8-3 8.5 1-0 Na-24 2.5 ~ 3 Co-60 ~ 5 1.8 ~ 2 Zn-65 *5.0 3.9 3 7 .4 Sr-90 32 2 3.8 Nb-95 67.4 I<<131 ~ 1 1 2 81.1 I-133 5.9 Cs 134 40. 4, 8.3 .20. 7 2.4 Cs-136 2.4 313 1.7 ~ 2 Cs-137 51.0 14. 5 26.1 3.1 99,7 98,0 98.4 98.4 A conservative calculation of the monthly dose will be done according to the following procedure. First, the monthly operating report containing the release data will be obtained and .the activities released of each of the above ll radionuclides will be noted. This information will then be used in
~
the following calculations.
2.3.2.1 Mater In estion The dose to an individual from ingestion of water is described by the following equation.
Page 53 BF.TZ 47 6/21/79 (DCF)ij x Ei rem (2.11) where:
Dj
~ dose for the j th organ from ll radionuclides, rem.
5 ~ the organ of interest (thyroid or total body).
95 ~ conservative correction factor, considering only Il radio-nucHdes.
DCF ~ adult ingestion dose commitment factor for the j th organ from the ith radionuclide rem/pCi, see .attached Table 2.1.
I ~ .monthly activity ingested of the ith radionuclide,,pCi.
Ii is described by II i 12Ud i
365 A V.
where:
365 days per year k A ~ i activity. released of th radionuclide during the month,
~
yCi.
V ~ average rate of water consumption (730 ml/d ICRP 23, p. 358) 12 ~ months per year C
V ~ total cooling tower blowdown during releases, ml.
d ~ minimum diffuser pipe dilution (5)
The dose equation then becomes D 4 'x10 (DCF) i Ai (2. 13) j v 2.3.2.2 Fish In estion The dose to an individual from the consumption of, fish may be described, by Equation 2.11 where i is described by
Page 54 BP.TX 47 Zi~ h i B d
i' N
6/21/79 (2 14) where:
hi ~ activity released of i radionuclide th during the math, yCi B<
~ fish conceatiation factor of ith radioauclide DCi/aa pCi/al, see attached Table 2.1.
8 amunt of fish eaten nonthly (1 9xlO gn) 0 ~ total cooling tower blowdown during releases, d ~ rLinizua di fuser pipe. dilution (5)
The dose equation then becomes 4xlO Dg V Ai x Bi x DCF wren (2.15)
If these calculated mntnly doses. exceed lirtits specified in Section 2.3.1, then a mre accurate and complete calculatioa ~<ll be doae as described in r
Section 2.3.3. An annual check will be made to ensure that the mathly dose estimates accouat for at least 95 percent of the dose. calculated by the method described in Section 2.3.3. If less than 95 percent of the dose has been esti~ted, a new list of principal isotopes will be prepared.
2 3.3 Annual Analysis A complete analysis utilizing the total source release will be 'done at least annually (=onthly if necessary). This analysis will replace previous estates calcula".ed ia Section 2.3.2 and consists of. the'
~,
followiag approach. The dose to the ) th organ fron u radioauclides,',
is described by L
o ~ ~
Page 55 BF TE 47 6/21/79 D ~ rem (DCF) ij x I, rem
~here:
D ij ~ dose to the j th organ from the ith radionuclide, rem.
5 ~ the organ of interest (bone, GZ tract, thyroid, and total body).
(DCF) ij ~ adult ingestion dose commitment factor for the jth organ
'from the ith radionuclide, rem/pCi, see attached Table 2.l.
'I I for water ingestion is described by A V n pCi (2. 18)
U d and for fish ingestion Ii is described by Ai Bi M (2. 19) where:
released of th radionuclide during the release j
A ~
i activity period, pCi.
V ~ average rate of water consumption (730 ml/d).
n ~ number of days during the release period {d).
~ cooling tower blowdown during the release period, ml.
Bi fish concentration factor of the ith radionuclide, ~1IEi/ m
~ amount of fish eaten monthly (1.9xl0 3 gm).
d ~ minimum diffuser pipe dilution (5).
Page 56 BF TI 47 6/21/79 2.4 erabilit of Li uid Radwaste E ui ment
'g)
Specification 3.8.A.5 of the Radiological Effluent Technical Specifi-cations requires that the liquid radwaste system sha3;1 be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected dose per unit due to liquid efflient releases to unrestricted areas (see Figure 2.1. ) when averaged over 31 days ~ould exceed 0.06 mrem to the total body or 0.21 mrem to any organ. The following methodology will be implemented to assure compliance.
2.4.1 Release Limit The liquid radwaste operability limit is an activity release limit based upon four years of operational. releases excluding tritium. The curie limit is dependent upon the future operational mix being similar to past operational mix. The most restrictive pathway is to the GI tract by ingestion of fish. The individual dose from the operational source terms was calculated to be .04 mrem/mo. This dose is a factor of 5 below the operability limit of 0.21 mrem to any organ. The total activity released excluding tritium is 0.10 curies. The allowable release without exceeding 0.21 mrem/mo is5 times O.l curies, or 0.50 curies/mo excluding tritium.
Al~it ~ 0 .50 Ci/mo. exc luding tritium The value of 0.50 Ci/mo will correspond to the limits specified in Section 2.4 if the mixture of isotopes is similar to the historical mixture.
TA]) '.1 DOSE CALC TION DATA RhO f fit.e 6 fl)Lfl"f CA~EFFEC T 1 VE tf()tthtt OUSE Cft+ t I ) ')EtlT I hCTt)f(S f RE)'/UC 1 ) F]SH 6]OLOC
)II.L) L 1 l 8 )tPLF l.]F C . ttbLF/L )F E ~nucztt(nattoii Fa(.'7< IIIILF LTFC (OhY5) (Ohv5) (OAYS) f]()VE Gl 'fRACT Tl(YRO]O fCTAL GL'OV SThf)LE RAOfOLO (04YS]
H-3 f>> 64 "E C3 (.00> ttl 9.'Iee 00 9 7TF 05 'I 77E 0) 9,'(7E-05 7 7)E>05 1.00E 00 1,00E 00 0,0 C-14
~]P")ZhQ K"40 CR-51 2
4 2
O'J L 6.1)F <<C]
]94)f. Cl
~ 6CF ICL CL r.b 1 (IOE inf bl 2,>iC 02
'.I ni IIOC ul 6.1 ac 02 1 0'lC 01 5.9(E-ol
(..I>E 5 UIIE 2,66> ol UL Ol Zid>C 01 l, 73 C-03 i "I)>-oi 3 'i>F 02 3;21E-06 Si70( Oii 5 32(-07 i,i>E-OL 0 (I 1,'(ll-i<3 5 7UC 1.7>E-03
(,41(E 0) 3 i>C-02 3,39E-Ua 04
-i 5 1
3,4)E 70( 04 7)E.o) 4',(1 3,2(E:oa 03 t<2 4
1 5>E OOF.
l,ona U) 2,>UE 03 Z,ouz 02 0) 02 4 >SE
'1 noE o2 i i'OC 05 2,'IOE 03 2,00E "02 03 0 0 0I0 0,0 0 0 0,0 rtt-54 3 .03F 07. 1<7(tt( Ol 1.415 Ol E,(l)E-O>.03E."04 4,0<IE 02 4,00E OZ 0.0 rtt-56 1,071-01 L,IUF. Oi l,(l>E Ol 2 O'C-0> 4,(III:-03 2,0'1-05 2,C41 05 ii,nnl 02 4,00E 02 0,0 FE-55 9. 5."..F 02 U.nnf: o) 4,142 02 3 0)L(-04 1.1)F.-OI 2, t c'-0'.74(-c\ L.OUE 02 I,UUE 02 0,0 F E-5>>) 4 9 'Jbt, Ol CO-58 7613C Cl 96pE 00 A>>3tlE 00 '196'IC 03 3>> Z9C 02 1 eb')2:"03 '1 96'IC 03 560OE 01 2998E 01 1eooE 02 CU-bo 1 612F. C3 9,ioE 00 '9, ' oo 4 ?3E-03 8 5()t "n2 4, /3c.-03 4,73c,..03 5,00E 01 4,75E 0] l,ooE oZ tt I F)5 1 ~ 0 tl <<C] 6,67E 0z 1;o7E-01 5,3t)E-04 3.]t.c-n3',27;-05 3,z7F-o5 ],ovE oz ],OOE oz o,o Ltt-65 264 Jl CZ 9,33F UZ ],9f E 02 3,O]E-O3 l,(9C-vZ. 7,]36-O3 1,]3C:03 2,OOE 03 ];4ZE O3 ],OOE OZ 2t I-61tl 5>> 75f-Cl 9,33f (tz 5,75E Ol 1 t 5PE-04 2O9]C "03 9 3tb4C 05 '064E-05 2 OOC 03 1 0 14E 01 i 1 9 CQE OZ Z tl-61 3 e>>/bE>>r.?. 9,33E 02 3,96C 0? 1 03E 05 9 97E "0'3 ],3'IE-06 ].37E=06 2,0VE 03 7,'IZE OL',COE 02 Btz-i)3 ]UOQL'-C] 5,'UOF. 00 9.>>IIE U2 3.S>E-OS, 1,30E-03 . 3,)5E-05 3.555=05 4.20E 02 4,20E 02 0,0 SR-84 2921L"C2 RR 05 2 6 Gc'E>>ZC 3 U,UOE 00 2.naE-03 >, 17E-07 . 7.24E-05 i 56, 17EE-07 5,1)E 07 -4.2UE 02 4,20E 02 0,0 Vn-83tf 797>C-Cz T,i(E 02 ,0,0 L,<aE-U4 o,o 0,0 i,ooE 00 l,noE 00 . 0,0 x R-8 sf'l ]>>>>f38-CL 00~00~ 55E-ol 0 0 3(30E-03 4,6ZE-v2 0 0 C fc 1,005 00 1 OOE 00 0(0 KR-85 3613L C3 L,OQE OO ].OnE 00 OUO 0,0 0,0 (,OUE 00 t,nnE 00 0,0 RB ]>>248-C?, 4,>oc 01 1,245 02 3,3'E-05 3,09E ('3 3,)4E-05 3,345-05 2,0UE 03 2,'OOE 03 0.0 R 8-St9 (.U7i= z SR 89 5. Z IE C] , 30E Q4 5,?5E Ol 1 6 PIE 01 1 904E ol,. 9 ~ 22C 03 9 UZZE<<03 3 ~ OOE Ol 1 00>>E Ol ]OOOE 02 5R-90 ].0]E C4 ], jnE 04 sebi)E 03 1 9] IE OL 3958E-02 2.nf)E-O2 1, I6i 00 1576C 00 3,00E Ol 2397E 0] ]OOOE 02 Sfz 91 4>>038"Cl ],30E O4 4.03C-O] 197?E-03 1, I?E-04 1.92E=C4 . 3.00E 01 1,20E-01 1,00E 02 5R-92 1 0 ) Jl.-c 1 1,)(<E oi 1,13<:ni '7<iTE-0', li)>E=u) a,u(5-05 a,it')E<ii> 3 litt> ol 3,3>>E'=ol 1,COE OZ 5R-93 5>>sf)L-C3 1,3(lf 04 5,561 t<3 6')IE 05 1 i(I'IE 03 9 96E06 E 905-II6 300E Ol ! 6)E 03 1 OOE 02 Y-'IO 2,!)IS. r,ft l.'UL'4 2 ( IL 00 9i6'L-06 i Z5E Oi 2 )IC-07 2 STE:07 2,5UE Ol 2 )OE 01 0,0 Y 9]tl 3'47f-".2 1,40F oi 3,'7(-nz 2,17F. Oll 5,06(-04 1,'(21-09 1,(21:09 2,5UE Ol 2,>OE nl 0,0 Y-91 5.5"".E Ul i, i<F 04 5;E'Ol 1'17L'-'U'i(OF-'I<l )Iat C.-'06 3'66C"oa Z,SJE Ol 2,5UE Ol 0,0 Y-12 ] ~ 4'If -Cl 1 4or o4 1 47E-O] 8 49E-07 1 27E n2 2 47F 08 2 47f =Oft . 2 5nF Ol 2 sOE OL 0 Y-93 4 92'3] iC] 04 4>>29Evol I IE 06 335]E OZ 595]E oft 565]LUTOBW95(EE 0] 2950E 090 0.'9'>>0E 1 ~ OL ZR-95 6.55C cl 4,50E Pz 5,7zE ol 2 54E-05 4 28E oz 6,3()E-06 6 38E"Qft 3,33E 00 3,33E 00 0,0 ZR 91 7,(JJE CL ttB-95t( 7>L fio 7 ~ 6!t . f)2 3,73L 00 5, f)f>>E 07 5SF-02 2, ztttE-07 "07 '3 ~ QVE 00 3,00E 04 .0,0 tt8-95 3 ~
3.5.E L.l .I,bg;. ()2 '3,35E Oil 5;]'ZE-Ob 3
3,0]t-vk 1,'~3c-06 2 ~ 88E l,83C-Cb 3;OOE"f)C 3,0i)E 04 0,0~~ 3' 1)
+ J'<
g tt~-97 5.ncf- 2 7d b)E 02 5.00C=OZ. 4 9OE-08 ? 10f. L)3 4.bOE<<O't 4.60.-09 3.00E QF 3,0QE 04 0,0 t'Q 1't 2 14'L Cv 5 Jf)E Qn ] /df'. 00 ct 'E?c-of>> 5 93l "L)2 tt 9'F Ib-E)f>> 8 4 /l: 04 l,ovc 3] 1 ~ ovE Ol 0 0 6.0'IL-0',37E-na
~
~ 9 ~
TC-91tl 2.52L-C] l,ona oo 2,nt>>-ol 2,4'E-07 9,3IE-06 1.5OE ol 1,5)E ol o,o TC <<1V 7, Ivt C'I TC-}0] 9,93f<<C3 1,0')4 00 9,<I)E ~ 0) 2,57E-07 7,49L "04 3,60~2-06 3,LOF=06 1,5(<F. Ol 1,5(IE Ol 0,0 RU-]ft3 RE) 106 3 ~ 9FJ 3,bOE C2 E C] I,)n,.< 00 7,30( Ou 6, l>E 00 7,1>>E 00 2 1 >LE-i(4
< Ul-n) 2 2
>>1 "u2 67("Ol T,i<UE-05 3,>0>-.04 7.9>>1-05
),5OE=04 i,ouE ol
(,OOE Ol l,soE'ol
(,OSE Ol ',0 0,0
TABLE 2. ONTINUED i
'" "'Ji'I
.IEAI.I -I.]I t IIALJ LlFC IIALFII.IF] ~CA((?EII(knf(LIW FBKT, (Iki) -L]FE lubv5) IObv5) 'Ohvb) Bl) IE Gl TR'AC T T)IY)ID]0 TOTAL UDOV 5TAGL.E GAOLDLO (OAVS) 8!I(Bi!< ');I(f-c? . 7.)oi uri 3,9cf;.!)2~672-07 ] '2]E=O'4 4,>PE 0(( 4;99E CB'.ouE Ol "1 OOE ul " 0,0 rclioii TEi)>k Tf(2rk 2.>)E 5.uot ci l,u')f CZ CZ
>.Ouie Do 1.>ui 01 l,>OE ol 4,90E 1',)>F.
1,32E Ol Do ul 2 1,3)E-04 52E"03 Bi9LE-03 9,7(f-o2 2,'25E 1,56E 7( 2 '82,3!f 8.7i!E-0>
1'.>8 Ori 03 8.78E.05 4 i5 Sf" 04 1,12(-03 2,00E 00 4;ouE 02 2,00E 00 E,DDE"02 0,0 0,0 OR 4 ODE 02 4;OOE 02 0 0 TE-l)7 3;9ZE='Cl 1,5oe "ol 3,82(.'ol ]i]32=04 6;76F=((3, Il;36E.=05 }','44E;05 4;OOE 0} 4;OOE 02 0,0 TE)? rN 3,4]E Ol )5I)l 0) 1)04C Ol ]'g14E OZ 4)96F<<O2 3 96E 03 U4F"03 4.00E 02 4,nnE 0.0
'. I7L-ui $
],5j': l.77F-03 1 OZ TE-LZ9 Tf(3ik 1.2>f L'0 ',5AE O]
OL
. Iie. ui 1.15t 00 3 u]3C=65 7! 1>E-04 3.61) 0? .-6!2,3/l.-05 I'IL'-04 7.3 IE u6 4,89( 04 4,uf)t B.DOE 02 OZ 4,upas 02 4,()OE 02 O,u 0,0 TE-1.'2 3 ~ )(E I:0 l,>>A( 0( 2,662 00 2,'i'.-03 2.2(f 02 (,PLk "0) 1 5III)-CC3 4.0AE DZ 4,00E 02 0,0 6 ~ ZlE C9
')5E Cp 1 ~ 3UE 02 1 3I)E OZ 7 6]E 00 3e]OE 03 0 ~ 0,98I>LE u]E 00 1 ~ 2 EC OZ "03 5 ~ ouE 5,0uE OL Ol 5 ~ 0 E "5E Ol 01 1 OOE 00
] ]31 G 1 3GC 02 8 EOI>E 03 4 I84F 8)02, 2 00 3 852F 4 8 1 OOE 00
] 32 9 2? I -.f? 3>>I; 02 9 I 1C-"OZ 97E-0'5 4 75C-03 7, ) ]E-02 1) 9 IE-04 5,00E Ol 4, 30E 00 L,OOE 00
]335 lE ~ BI?] Iieet,]930 1
~ 'OZG ~ BLE+nt "02 1
te36E03357UEOZ 03"'
IBI)9E01 755]E0 47E-05 5 5 ~ OOE012529EOL lepOEpp f 1')4 3 f? ".2 ) 3 IF. 0? 3 61C 7 I G E 05.. f.
3 40C 2 9? C 02 7 5,00E Ol 74E 00 L,OOE 00
'?. 1 Q~
'1 Q]0~!2i>ut-!2A)~
1
]35 2 7) 3>> 2 7 IE Ol 38 lUE 0 5 ] ]7E OZ 47E Ol . 3 9UC 0 5 OOE 01 09E OL OOE 00
~ft>3((~'I 1 ~ C 1 ~ ~ ~ ~ ~ 5 ~ 1 ~ 1 ~
I I Ofl QQ 6 9!I I!f 5E fl Cgo ] O(IE Oil iiAAE 60 0!0
)EE-])3 58Z IL 00 LBOOC pu U84]Evo] pep 0,0 0 0 1 Doi 00 ]i(IDE 00 0 0 x)]3SE) 1 ~ nUl. f;? ) .OOE oo 1,07E:nz 0)0 3.29C-04 2 Oeo G.o t,ooE on l)nuE op 0,0 3.I)3L-.OL L,Onr. 00 2.7'IE-Ot 0,0 L,OOE-O? O,O O,O ],OOE OO ],OOE OO P,O C5-.]34 t '.7E.CZ 7 ppE pt <. 40E pl 5e'I'~E 02 .7 67T..-.,QZ 1 ZoE.OL \ ZDE pl Z.OI)4.03 2 OOE.03 . 1'OOE pp C5 ] 35 1 ]L'L. O'I 1 ]SF. 0?. 1 1>C 02 1 5'I"E"02' 0 4),0< E "03 G 06C "03 Z,OI)E 03 Z,OOE 03 L,OOE 00
~5-1)'I ]~ ) If* c] 7,ne)E yt j, ."E
$ l)g 5I>>IEE 03 GI7'ff AI'. ~
7II)3c 0?. 2 03c l'I>> 2,00E 03 1 I)t E 03 1 IOOE 00 C5-]37 ]8]'-'C 04 'IBDI)E Ol 6896E IIL 784) IE 02 68'EOC~OZ 'le?",E-02 78?UL "02 2,00E, 03 2QOOE 03 L,OOC 00 Pit>OLO]
PA ]3'7 5 'II C OZ 6 50I] QL 5 I5EE OZ 1 05E 08 3;) EC 03 3 u7C 06 3 C7E 06 <,OOE pn 4 '30E 00 0 0
)i)l'6 LB (40
]4~ii'3(".I 1 I >L Ccu
]
5
(>)i)E Qllf 0]
02 1 (i7!L Ot)
]it?E I)]
1 SI'!I 1- {)?
II J>(
9!{iu( .0) t)22 1 (2)91 2,!!'Il ur 00 3 CI( 07
-? IC?I:;08 0~
2 Sot Ol 2 >OE ZI>OE 01 0]
II!0 o10 CE 1' (f -1,,4 3 2>f Cl 2,,)'1-C) 5
<io)f 0?
t,'3E-OZ
(,ii'It-u~f 30 .(f ul '! 3)f 4,,)iil'..Oiiill 06 3 1
75(f 02 71- 02 lL0!i 7,
2 (212 07 I'ii 7
Z 72( 722,5DI 6,",f.,c> 2 Ol
>>of-ul 2 >Of 2,>OE-OL 0] 0 0 0 0
.oz "liof '.S.o(f-'oo i.> '(oI Pk ]54(
M(0=]'~1]E Pk.-l(7 1.?cl'.cE}
9,"It-C2 f]
7 >o74 6.>BL.092.
6',>(E-02 3,'89t-oz
,o}]
Ql 6 T!E;.99 ],
9 Iiriu(.05 1,33(-.oz
)0>I-'03 06(;='I? oi i, >i r.-'o>
'!,5.':-.0'?
2, ~ 9F o6 4,55E:07 2,69>E.ca 2,>of ol 2.>>E Ol 2,5oE-ol 2.>of Z >OE
},SAE ol O]
o,o 0,0 0,0 (ktuk)
PI) ) ' ? ) 1 f. co 6 )6g 0? ? 70c 00 1 )5I c-06 / I Gnc 0?. I), I)7E-OG G I G 7c-OG 2' 50E 0'1 2 I 50E ol . 0,0 w 0(}
P)I 151 1.]eE CO 6 ~ 5I)E PZ '],16E -00 6,'l4>E-07 381 IL-02 5,'llC-05 5,91E:CG 2.'50E Ol 2,50E OL 0,0 ~~
],9ii. 't.f/4t" 00
')6 ~392
~6 6)l Ou 0]
6,~SE 02
{,>I f 6,)>F. 02 02 3 3,2(t 92F,-O]
1 eu3E i!638-A7 5 (>t-05 06 3 ~ 5GF 5!B f 03 1,3>E 02 UZ 6 ~ I)I)C 5 '!3f-08
'3,3>L-D>
OU 6 ~ 66K 0})
5,3!P:OB 3,3)E-O>
2 50E Ol 2,>OE Ol 2,50E Ol 2 50E 01 2!>DE Ol 2,>OE 0]
'!0
.0 p 0,'0 Eu-(5S ~ CZ OZ k l>7 9 ~ 961"Cl l,oorl 00 4,9')E-o] Bi'(OE 05 2 >(F."02 .2,(0(-05 2,702'.05 1, DE 03 ],ZOE 03 0,0
~tt) 23~+35E nn ),')0~< 7, 35E 00 ')45E".06 3}.t?)E"0?~ 'I4C-OG 7)74E-OG~ OOE 0~1IOOE 0~pep 8
Page 59 BF TX 47 6/21/79 Restricted Area SN'ITCH VARD J
PARRIHC I I I
TRAHSPORIIER YARD SERV dCOC TVRdIHE dCOO 0 n OO STORAGE AREAS AO OFPICE JVAS TE dI.OC REACTOR dI.OC IHTAAE PJIIIPIIIC S TA TIOH STACA'EWACE TREAOIEHT PEAHT I
...Ni~v .
Figure 2.1 Assumed Liquid Effluent Restricted brea I
Page 60 BP 'Xl 47 6/21/79 Rad io'o- icaL Environ=.ental Yanitorin Fanitorin~ Pro ran hn environ=ental radiological.~nitoring pzagran shaIl be conducted
,as described in Tables 3.1-1, 3.1-2 and 3.I=3, and Xn Figures 3.3.-1, 3.1-2, 3.1-3, and 3.1-4 '. Results of this program shall be reported in accordance with Technical Specifications 6.7.l.d and 6.7.2.c.
The atnospheric environ=ental radiological monitoring program shall consis of ll =a+coring stations fzon <<hich sa=ples of air partic-alates, a-wspheric radioiodine, zain=ztez, and heavy particle fallout shall, be collected.
The terrestrial nonito=ng progr~ shall consist o the collection of milk, soil, ground vater, drin~ <<atez, and food crops. Xn addition, direct g~ radiation levels <<~1 be =easured in the vicinity of the plant.
The xeservoir sa=pling program s".a~J, consist of the collection of samples of surface <<ater, sedi=ent, and fish.
Deviations are permitted from the required sa pling schedule if specLens are unobtainab'e due to hazardous conditions, sample unavail-ability, or to wlfunction of sa=pling equip=ent. lf the latter, every effort shall be ~de to co=piete corrective action prior to the end of the next sa"pling period.
Page 61 BF Tz 47.
6/21/79 Detection Caoabil itSes haalytical techniques. shall be such that the detection capabilities listed in Table 3.2-1 are achieved.
ENVIRONMENTAL RADIOLOGICAL MONITORING Exposure Pathway
Sampling and Type of Frequency and/or Sam le Sam le Locations Collection Fre uenc of Anal sis AIRBORNE Particulates 4 samples from locations (in different sectors) at or near the site boundary (LM 1, 2, 3, a 5) 1 sample from the residence Continuous sampler operation Gross beta following filter change having the highest X/Q (LM-4) with sample collection weekly composite (by location) monthly for ~amma scan. Composite quarterly 4 samples from communities for Sr, Sr. If any fi~-er approximately 10 miles indicates a gross beta concentration distant from the plant (PM 1<<4) 1.0 pCi/m greater than the average of the control stations, a gamma 2 samples from control. scan will be performed on the filter locations greater than'0 miles from the plant (RM 1&2)
Radioiodine Samples from'same locations Continuous sampler operation I weekly as air particulates with filter collection weekly Fallout Samples from same locations Heavy particle fallout Gross beta monthly as air particulates collected continuously on gummed acetate paper with paper collection monthly Rainwater Samples from same locations Rainwater collected con- Gamma scan, monthly as air particulates tinuously with composite sample analyzed monthly W Cd&
~%0)
Iv 00 Soil Samples from same locations Once per 3 years Gamma scan, 6 Sr, Sr ~ AH (hm as air particulates once each 3 years V h)
I
Sample locations are shown in Figures 3.1-1, 3.1-2, 3,1-3, and 3.1-4.
t
TABLE 3.1-1 Continued Exposure Pathway Sampling and Type and Frequency and/or Sam lc Sam 1'e Locations* Collection Frc uenc of Anal sis DIRECT . 2 or more dosimeters placed Quarterly Gamma dose quarterly at the air particulate sampling stations located greater than 5 miles from the plant (PM 1-4 and RM 1 a 2) 2 or more dosimeters placed at 8 locations (in different sectors) at or near the site boundary (Figure 3.1-2)
WATERBORNE
)
Surface TRM 305.0 Collcctcd by autpmatic Gemma scan monthly (Figurc 3.1-4) . TRM 293.5 sequential-type sampler Compoistc for tritium, TRM 285.2 with composite sample Sr and Sr quartorly taken monthly Ground (Figurc 3.1-3) 1 sample ad]accnt to plant Coll ected'y automatic Gamma scan monthly.
Hcqu<<ntial-typo sampler Composite quarterly for with composite sample tritium.
tak<<n monthly 1 Hamplc from ground water Monthly grab sample ~ Gamma scan monthly, source upgradicnt Composite quarterly for tritium 1 sample at the first Collected by automatic Gross beta and gamma scan 'rinking (Tnb1 u .3. 1-3) potable surfaco water supply sequential-type sampler monthly. Composite quarteily Ch tXI W (Figurc 3.1-'4) down..trcnm from the plant with composite sample for Sr, Sr, and tritium. M 00 (TRM 282.6) tak<<n monthly wR m WH
'4 Ch
Sample locations are shown ip Figures 3.1-1, 3.1-2, 3.1-3, and 3.1-4.
TABLE 3.1-1 Continued)
Exposure pathway
Sampling and Typo and Frequency and/or Sam le Sam lc Locations Collection Fre ucnc of hnnl sis 1 sample at thc ncxL 2 Monthly grab sample Gross beta and gamma scan monthly.
downstream potable surface Composite quarterly for tritium, water supplies (greater than ssSr, and oS 10 miles downstream) (TRM's 274.9 and 254.3) 1 sample at a control Monthly grab sample location (TRM 306.0)
Sed 1m't TRM 307 ' Semiannually Gamma scan, Sr, and Sr analyses (Figurc 3.1-4) TRM 393.7 semiannually TRM 288.8 TRM 278.0 INGEST IGN Milk 1 sample from milk Semimonthly when animals I analysis semimonthly or monthly (Figure 3.1-3) producing animals in each arc on pasture.'onthly on collection. Gamma scan, ~~Sr, of 1-3 areas. indIcated by when animals are off and Sr monthly.
thc cow census where doses pasture.
arc calculated to be highest. If samples are not available from an area, doses to that arcs will be estimated by pro)ecting the doses from concentrations
'detected in milk from other sectors or by sampling vegeta-tion where milk is not avail-able 00 H m 1 sample from a control location V H
c
Sample locations are shown in Figures 3.1-1, 3.1-2, 3.1-3, and 3.1-4,
TABLE 3.1-1 Continued Exposure Pathway ~
and/or Sam le Fish 1 sample each of a commercial and a game species in Guntcrsvillc Rcscrvoir above thc plant 1 sample each of a commercial Semiannually Gamma scan semiannually.
and a gama species in Wheeler Reservoir near thc plant 1 sample each of a commercial and a game species in Wilson 1 I
Rcscrvoir below the plant Food Products 1 sample each of principal hnnually, at time of harvest. Gamma scan on edible portion food products grown at Thc types of foods availablc private gardens and/or farms for sampling wl.).1 vary.
in thc immediate vicinity of Following is a list of typical thc plant. Selection of, foods which may be availablu:
locations to bc baaed an tha cabbage and/or lettuce, corn, land use census. green beans, potatoes, and tomatoes; 1 sample each of the sama good products grown at control locations.
W td W t4 00 Hm WH
~Sample locations arc shown in Figures 3.1-1, 3.1-2, 3.1-3, and 3.1-4. e>eV
TABLE 3.1-2 Page 66
-BF TI 47 6/21/79 A~i..OSPEERIC A.'iD TERRESTRIAL HONITORI'.iG STATION LOCATIONS BROOKS FERRY hVCLEAR PLA'iT Location and Approxinate Distance and Direction from Plant Lf-1 BF 1.0 mile N LW2 BF 0.9 niles hhE LW3 BF 1.0 niles hE LW4 BF 1.7 miles hhR IN-5 BF 2.5 miles VSV Ht-1 BF (Rogersville, AL) 13.8 xailes hV PH-2 BF (Athens, AL) 10.9 ni1es hE PY~3 BF (Decatur/Trinity, AL) 8.2 niles SSE w
PH-4 BF (Courtland, AL) 10.5 miles VSM W-I BF (..uscle Shoals, AL) 32.0 ni1es 4'0.5 RH-2 BF (Lamenceburg, TN) miles hiVR Farm B 7.0 miles hhM Farm S 4.8 miles H Farm Bi ,4.5 miles EhE Farm L 5.8 miles RE Farm T 7.0 ni1es E.'~E Farm N (control) 27 niles Rf Farm J (control) 40 niles hhQ Farm C (control) 32 miles N Farm Ca (control) 32 miles V
Page 67 BF TI 47 TABLE 3.1-3 6/21/79 LISTING OF TENNESSEE RIVER SURFACE WATER SUPPLIES TO BE SAMPLED IN ENVIRONMENTAL MONITORING PROGRAM',
Distance from Plant
~Su ~l Source miles Courtland {Champion Paper Co.) a Tennessee River 11.6 (mile 282.6)
Decatur b Tennessee River (mile 306.0)
Wheeler Hydro Plant , Tennessee River 19.1 (mile 274.9)
Sheffield Tennessee River 39.7
{mile 254.3)
a. First potable water supply downstream of the plant. Sample collected automatically and analyzed monthly. /
\
b. Decatur is upstream "of the Browns Ferry Nuclear Plant.
cable S.2-1
~ .
OETECTtnH CAPAhtLTTIFS FOR rlQthnHHFVF BAHP E AHALYSt9 A 5 pcff fc A/CA I ooo flnHtHAL tfSWrR t.tHtT nr nrtrcytnH Lt.O a Ffsh, hfr Voh ~ tstfon Soll aod elan Clash, Poodeg osat ~
Charcoal Fallout Motor and brain Sodfaont ptonktdlnd Claw aholle poultry, Nf 1'h partftufatea
~~~Cf a~ ~CI KCI/K a CCCIII ~CL I ~dr ~Cf ~dr gCCfr ~dr ~CI ~dr ~Cl K a K ~l O.OL 115 Total 5 0.1 0.7 0.35 Cross g Cross ff 0.005
0. 01 0105 2.0 2.)
0.05 0.20 0.70 0.1 OK7 'S 330
~ ~ ~
~ ~ 0.01 0.5 1
~~ 10 0.25 la 5 0.5 5.0 40 10 Sr OKOOS la0 ~
"Sr 0.001 2 0.0$ 0.3 0.1 8 .2 B. Caorsa Anal sea I
HOHtHAL LOWER LtHLT OF DETECTIOH LLD Air Mater V48etatfon Soil and Claw tlesh foods, toaatooo Lfsat and part tculatee and rdfltt and grain 'ediment Fish and plankton Claw shells potatoes, etc,) poultry l4to t.t oo
~cl/ I Li ~CI/ dr Hat ~Co Lf
~CI / ~R~r ~Ctl ~dr Hal Li
~CI/
Kal dr LI
~CI/
llal d'r LI Kal Ct X a sdot ~CI/I val
~Cv Hat ~Cr H.st ~CC.(Lf ~Co ~Ca ~Cc C~eLI Hat ~CotLf
$ +$ ~ fooCe 0.35 0.03 38 O.SS 0.3$ O.) S 38 90 fobCO 0.02 33 OK22 0.06 0.06 0135 0.06 33 d'or ssCr 0.07 0.0) 60 44 1a10 0.41 0.60 0.10 0.60 0.10 O.S6 Oa 60 0.10 60 44 200
$ )st O.OL 0.01 15 8 0.3S 0,09. OK20 0.02 0.20 0.02 OK07 0.20 0.02 15 8 50
$ ~ S ~ I o ~ Ru 0.04 0.45 0.45 0.45 40 40 OKGS 1$ 0 tssh 0. 0) 40 0. SL O.LL 0. LL 0,74 0.11 40 90 ss+C 0.01 0.02 10 26 OK20 '0.33 0.12 0,08 0.12 0.08 0.48 0.12 0.08 10 26 40 $0
'"Cs O.OL OKOL 10 5 0.20 0.06 OK12 0.02 OK12 0.02 ~ OKOB 0.12 OK02 10 5 40 ~ 1$
s Xr-Hb 0.20 0.12 O.OL 10 0. 12 Oal2 10 40 1 sZr 0.01 10 0.11 0.0) 0,0) 0.1$ 0.03 10 20
$ Slab 0.01 0.07 O.OL 5 0.05 O.OL O,OL 5 1$
'Co 0.02 O.OL 1$ 5 OK23 0.05 0.20 0.01 0.20 0.01 0.07 0.20 0. 01 15 5 5Sr r 15 s
H/s 0.02 O. OL 10 .5 OK20 0.0$ OKLS 0.01 OILS O.OL- 0.08 OKLS 0.01 10 5 "40 15
~ sin 0.02 O.OL 1$ 9 0.25 O,LL 0.23 0.02 0. 2) 0 ~ 02 0.17 0.23 '.02 15 9 10 20 Co 0. OL 0. OL 10 5 OK17 OKOG 0. 11 Oa OL 0.11 0.01 0,08 0.11 OKOL 10 5 30 1$
0.10 150 2.50 0.90 0. 90 0.90
"'bi-La 0,02 '5 O.GB 0.34 0.15 0.07 0 15 0.07
~
0.30
/ 0.1$
0.07 1$ 0 1$
400 50 bo 0,02 2$ 2$ 50 lb ~ L 0. Ol 7 0.08 0.02 0.02 0.10 0.02 7
~
1$
Page 69.
BF TI 47 6/21/79 TABLE 3. 2-1 '(Continued)
TABLE NOTATIONS
The NaI(T1) LLD values are calculated by the method develope'd by Pasternak and Harley as described in HASL-300 and Nucl. Instr. Methods,:533-40 (1971)-
These LLD values are expected to vary depending on the activities of the com-ponents in the samples. These figures do not represent the LLD values achievable on a given sample. Vater is counted in a 3.5-L:farinelli beaker.
Vegetation, fish, soil, and sediment are counted in a 1-pint container as dry weight. The average dry weight is 120 grams for vegetation and 400-500 grams for soil sediment and fish. Meat and poultry are counted in a 1-pint container as dry weight, then corrected to wet weight using an average',
moisture content. of 70%. Average dry weight is 250 grams. Air particulates are counted in a well crystal. The counting systen consists of a multi-channe1 analyzer and either a 4" x 5" well NaI(Tl) crystal. The counting time is 4000 seconds. All calculations are performed by the l.east-squares computer program ALPHA-M. The assumption is made that the samples are analyzed within one week of the collection date.
The Ge(Li) LLD values are calculated by the methods developed by Pasternak and Harley as described in HASL-300. These LLD values are expected to vary depending on the activities of tPe,co ponents in:the samples. These figures do not represent the LLD va1ues achievable on given samples. Vater is counted in either a 0.5-L or 3.5-L ."farinelli beaker. " Solid samples such as soil, sediment, and clam shells are counted in a 0.5-L Marinelli beaker as dry weight. The averag'e dry weight is 400-500 grams. Air filters and very small volume sanples are counted in petrie dishes centered in the detector endcap. The counting system consists of a N)-4420 multichannel analyzer and either a 8/, 14/, or 18. Ge(Li) detector. The counting time is normally 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . All spectral analysis is performed using the soft-water provided with the ND-4420. The assumption is made that all samples are analyzed within one week of the collection date.
a. All LLD values for isotopic separations are calculated by the method developed
~
by Pasternak and Harley as described in HML-300. Factors s'uch as sample size, decay th~es, chemical yield, and counting efficiency may vary for a given sanple; these variations nay change the LLD value for the given sample. The assumption is made that all samples are analyzed within one week of the collection date.
The LLD is the smallest concentration of radioactive material in a sample that vill be detected with 95% probability with 5% probability of fasely concluding that a blank observation represents a "real" signal.
Page 70 BF TI 47 6/21/79
~,
~ ~
TABLE 3.2-1 (Continued)
TABLE NOTATION Por a particular measurement system (which may include radiochemical
'eparation):
4.66 sb E~V 2.22 y exp(-Akt) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume) s is the standard deviation of the background counting rate or of tie counting rate of a blank sa~le as appropriate (as counts per minute)
E is the counting efficiency (as counts per transformation)
V is the sample sic'e (in units 'of mass or vol.me) 2.22 is the number of transformation per minute per picocurie Y is the fractional radiochemical yield (when applicable)
X is the radioactive decay constant for the particular radionuclide ht is the elapsed ti=e between sa=ple collection (or end of the sample collection period) and tMe of counting, 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'he counting rate of the blank samples ('as appropriate) rather than on an unverified theoretically predicted variance.
1
Ia figuto 9'. I-I Page 71 BP TI 47 6/21/79 Sto~nS FCtty lluClCOt Pl.IOC ATMOSPHERIC AND TERRcSTRIAL, MONITOR)i~lG NETNVORI(
RM ZBF LAOAEIICEBVRG
~PVL ASIAI PAYETTEVILl E ~
PM-IBS WILSON WVEELEII POSE'IS~".LL+
CAU OCM ATIIE'IS FLOREnCE PM-28F C
FFgL "~~~i uuSCLE IIVIITSvl LE
.~5%*LS BROW~S FERRY nuCLEAR PL HT
~~2 n4~18F LEIQRTO:I TVSC4~BIA couRTLA>;0~
Pu-+BF OECATVR PIA->OF <
IO MILES
~RussELLvILLE CIPI TERSV'L'A;4 HARTSELLE gQ Ml C.S HALEYVILLE
@cuLLuAII 4$ MILES E~qqcqvE~tiL MOufo~i'IG STATIO<
NOTE T~E FOLLO'.vi.'IG SAM>LES ARE COLLECTEO I QO+ c C~ 5TATIO<:
AIR nARTlcuLATEs RAINWATER RAOIOICOlnE SOIL
~ VY PARTICLE FALLOVT VEGETATION
Fipv~ 3 /- z BF TZ 47 LOCAL MONITORING STATIONS BROWNS .FERRY NUCLEAR PLANT t
~o--
Q
~
BFNP S
Rl VK R oo Legend Air Monitoring Station 0 TLD Station Scale 0 I Miles
Figure j.r- 3 Page,73 QF TI 47 6/21/79 LOCAL MONITORING STATIONS BROWNS FERRY NUCLEAR PLANT ATHENS US HWY 72 ALA HWY 20 Legend 0 Air Monitor DECATUR 6 Air Monitor & TLD Station N
TLD Stotion A Automatic Well Sampler Scate
, 0 Dairy Farm 0 I 2 3 4. 5 Miles
Picture '9-~-'F Page 74.
BF'I 47 Breams Ferry !ruclear Plant 6/21/79 R ESERVOl R VfONITORING NFTVrJORI(.
Efk. River WHEELER DPM mile 270.90 mile 277.98 Rog rsviffe 0
mife 29I.76 A)hens mile 2S2.6 0
~mii 285.Z-- ~ I B.F.'rCL,EAR Pl Pr~)T Q.
B Champion Pap r Co.
mile 288.78 rn~le 293.50 rnih ZGi.o Courtfahd mile 293.7Q Deca ur milo 07'-
Scale o", i".lifes Aufor;.atiC Samofor 0
Page 75 BF TI 47 ~
6/21/79 I
0 ~
Appendix Xhis appendix contains 10CFR20, Appendix B. The values in this appendix are the maxiaum penaissible concentragions (NPC) in air and eater above natural background.
4O
E
\
APPRNDIX tt APPSHDI)f ()
Ceacoesmctoas fa Afc 444 Wecsc Above Hecvoef ttecbncovad Coaceatceetoao la Afc omf 'atotu /Ebovo ftotvcef Dechocovcd~~ob (Sso eet ~ I ~ I oli et eppeabth) (544 aotse ~ I oad et eppeadte)
TeL14 I foLlo tt Table I fe'Llo ff Slecloee (ecom4 avaebeot Is ~ Iepo I Cotvma I Crlvelll 2 Cefvma I Celvma 1 Rle)a4ht (4l4alle avmbeo) tselopo I Crlvma I Colvma 1 Cetvma 1 Crlvma 1 I
hi<< Wctu Alr We'er AII Wecu *Ic Vcetsc (Ie I/e<<t) lac/mlt (I I/mll t).c/ml) tvc/mt) (ac/mll (xc/mt) ~ /eeet I I
I rto'I <<fo' (ll) bvlo I 4rf0 Pol ACItltvra (491.... ~~ .. ~ . Ae 2 Rr I Ac 224 5 2 x lolo 4 ~ lo '
II b ~
9glo I 10 1 ifo,s 4
0 rlo 1 h1 0
'.> 'lo 2
9.'.IO
~
I SC ~ Iata4 CeimIvm
~~~
(ci)..
~~~~o~
~
.~
~ bc 5'1 CJ 109 5
I 5
1 r10 Rhto I 5 10 I
~
I 5
~ lo I
~ lo I 4 ~
le to lo 1
4 2
~
~
IJ tl 10 0
l vlolo 'I ~ ~ ~ ~ ~
I ilo ~ b ~ lo 'I
'I 0hto'I I r ~ lo ~I 5 ~ 10 I 1 ~ 1) 2 tl '1 Ameilclvm t05). ... ~ AlI lit 5 b ~ lo>> I ~ 2<<r 10 4 X C4 115hs 5 4 ~ 10 r ~ lo ~ I rto I to
~
tt I I ~ lo 'I ~ Inc 4 e'10'I to'r 10 I 4olo I rrlo I o I oto 2 lo l
~
hei 142ee 5 brlO II I fn' 2 ~ 10>> I CII 115 5 2 ~ 10 ~ .
I 10 lo to l ~ 4 e
'.rlO
~
I ~ lo>> ~ lo I 9 i lo 'I 0<ID I I I 1 r lo'I trio I 4 elo ~ ~
4 ~ IC hm 242 5 4 ~ ln ~ 4 e.ln I I r 10 ~ fytO I Cetttoai (20)eoooooooeee. Ce 45 5 2<<lo I 1 ~ lo ~
I r lo 0 ~ to I SrlOI 4 ~ 10 I 2ilo II I I xlo I I
.I lolo I 5<<ID I 4 rf0 2 ~ 10 hm Ril 5 4 ~ lo>> 'I ylo ~ '2 ~ lo 4rlo I Ce 41 5 lelo I 1rlo I 4 ~ 10 5 ~ 10 I I*I> 'I 4 ec lo'I ihtn'It 1 r lo ) I 2 ~ lo I i<<to I b clo 1 ~ to Ale 244 5 4>IO ~ I xlo I fxlo I 5 ecto'I Celltecafvas (95), ~ Ct 249 5 2 <<IO It Irlo I 5 r 10 I ~
4 ~ IO I 2 e.'lo I I yfO I irtO I Sxlo I I I fxlo>>II r ln
)e ~
1 rto II 1 ~ 10 I Aattmoa9 (Sf).... SL 122 5 rtO r 4 r lo'I 4XIO I Sxlo I Ct RSO 5 5XIO 4 y.tO ~
2 r 10 es I I II I fyto I SXIO ' Sxto ~ lxlo 'I I
~
I xto II Pxlo I 1 414 'I 1
~
~ lo 5L 124 $ 2rln > y 10'I 5yto ~ 2vto Ct 2$ ) 5 RXIO 'I I) lo ~ 4 h 14 I ~ ~ ~ IO t '1 y lo ~ r xto' r x 10'>> xlo'I ) I elo>> ~ rlo I 1 a 14 11 1 ~ 10 5b 125 5 5 x to 'I 2 ylo'I 2xlo I xlo I Ct 2$ 1 4I 5 b <lo 'I fr 10 ~
1 wlo II 1 ~ to I 2 r to I 1410 I 'rlo>>
I xlO ~ 1 ecto II 2 10 ~
I )e lo II rtn A<<boa (14) ~ oooo<<oooo ~ ~ A lr SVLI bcto I 1>to ~
Ct lsl ~ x lo'1 4vtO I 1 r lo II R
I r lo (
A4t 5vb 2rlo I 4XID I SXIO>> 4 ~ 10 I 1 r lo II 'I rlo C AII444 (ll)~ ~ ~ eeoooe herl 5 1 ~ ID ~
I IO I r xlO ~ $ cl4I Ct 154 5 srlo w 4rl4 I 2 r lo II lo I
~ ~
I irlo I 1xlo I Ihto I Sxlo I I 5xlO It 4 ~ to ~ 2 ~ 10 II 1 ~
I ~ 10 I-As r4 RLIO I I .clo I Srlo I Cecboa (b)ee 4@14 I 1<10 I .I r lo I C 5
ir C 14 4 <<14
'sfo
~e ~o~ ~~o 5 I lrto I 1 xlo I lo ~ 5<<10 I .I (COI) 5vb Sxlo I I ~ lo hs rb 5 I /to 'II 4 e,lo r;10'
~
ir lyln I 10 I 1 xto'I lvlo I CSItvm (SS)oooo<<oooo<<<< ~ Co 141 5 4 ceto I 2<10 I 2 rlo 0 ~ 10 I I I .'10 b I RxtO 1 xlo I 5 r 10 0vlo I Ae rr 5 Srlo I 1 Wlo'I 2xlo I 5 x lo'I Cs 145 5 >'yfo I xlo I 9xto I 4rlo I C I 4 ~ lo I ~
2 <<to I IXIOI Seto I 1 lo:I ec txlo I r ~ Io 4<<lo I Ascottao( ~ 5) , ... ~~ .. At 211 5 r ecto I 5 v 10"I Seto) 2ylo>> 2xlo I Co tig 5 I xlo I 1a lo ~
1 ~ lo I~ felOI I 1 xto ~ 2xfo I I )clo I tytO I I 4 xlo ~ lxlo I I 10 I ~ toto I (
be<<tern f54) eeeeer oooo be 121 5 I vlo i.lo I I 5> lo I
. 4XIO I I Ylo'I Rxlo I 2rlo '
Cestvas (55) ~, ~ ~ .. ~ . ~ .. Cl Ilf 5 I xlo rxfo 2
4
~
r lo I 2 ~ lo I I I 4 I lxtO I I rlo 0 olD ~
'vfo
'xto 4~ 140 5 I ylO "I 4 r lo ~ ixlo I x lo'I Ce film 5 I
'xlo 2xfo I 1 rlo 4 ~ ID I
~
I 4<<,lo I r xlo ~ IXI4 o RXIO I bXIO I sr to I 2 << lo I I ~ los I boebsttvm (91)....,. SE 240 5 9<<to>> 2xlo I 1 vtO'II I '110 C@ 124 5 4xlo I 2) ID I I rlo 0 10 ~
I 'ilo I 2vlo I irlo I 4 glo' I I xlo I I xlo I 4 r lo I ~ 4
~
r lo ~
SE 2$ 0 5 tvto I brio I srfo 2 r lo ~
Ce llS Svfo 1 r lo I 2 elo I I ~ IC I I I <<10 ~ brio I I'rlo Seto I I I 'vlo rxlo I 2 v lo 2 ~ loo I bet>lttrm tl) ~~~~ 4~ 7 5 4'lO I Solo) 2 ~ lo I 2:elo I Cs lib $ 4hlo I 2 r 10' I <<lo I 0 ~ 10 I
~ ~ ~ ~
is
~
t I ~ toe lo I 2<<IOI f 2410 I 2'ilo I 4 r lo b ~ 10 I oe ~ eeo ~ el Ilbe ~'
ee ovv~ 1 ~ III totn I 4eth I 4 'e'U CI 'Ile hvtn I 4 ~ ln ~ 2 ~ ln lh I
~ ~
I I eto ~ ln ' S tc) ' I III I I eto I 1*10 ' 1 o III e 2
I
~
IS 1 Se for s 2 e'IO > ~ ln I IIII 4 ~ IO I Chtoclae ltr) ~ ~ ~ ~ ~ ~ ~~ ~ ~ CI lb 5 i e.lo I olo I I ~ lo 4 ~ I&
I I eln ' 2 ~ lo I S IO 'I bolo I I ~
1 ~ 10 I Rrlo I 5, ln I ~
4 I Dc lo 'I
~
aI RIO 5 ~ ln I I ~ to I 2 ~ IO I CI RS 5 1 r IO ~ I rlo I 0 Io I octo IO I 2<< 'I I 2.<<lo I
~
I ~ 10 4 ~ 10 I I yfo I 1 ~ Io 4 ~ tbcsa c In ~
to I sr ttl I 4 eloc Chtom)vta (24),...c. Cc Sf 5 I ~ IO I SilO> 4 ~ ln I R.to I
~ e I ~ ~ o '
eh I
APPSHOIX S APPSHOIX.II ~
Coacoaaett oao la Alc oa4 Water Ab Jve Itotvvol becbgoeva4>> Coact 4 U o 4 Ceacoatvottoao Ia Atc aml fyatar A'bove Netbool Siccbacova4>>Coattavaa
{5oo aetoa et eai ef oppcaita) {$44 Acta ~ ~ I oa4 of eppaadfo) yabto I Tobfo II yobla I yabta ¹ 5famoat (etoacto avecbae) lcetapo 'atvaen I Catvma 2 Cotvma I Calvma 2 Stoical (etemtc Avmboi) Icotapo I Cofvmi I Calvma 2 Cafvma I Cotvma '2 Alt We tot Atc Wat ~ I Alt Wotct Atc Water (ac/ml) (AC/ml) (Ac/ml) (Uc/ml) (r I/mt) (AC/a If ~ {rc/>> Il Io I/mtf I)yl.... "" J X la'I )clot I Ala' i la ~ PetmtUAI 1100) ~ ~ ~ ooooeo Pm 254 5 45 10'I la' 10'o i IO x la' 2 ~
Cobett ~ Co SF 5 I 2'10 I I x 10'
'I 4xla I
~ 4 Icto I I r xf0 ~ irl4xta'I I ~ loc I I .Ia c C' $$m 5 )xto I ~ 10 Pac 2SS 5 $ x 10
~ I 4 ala 'c ) ~ 10 I I 9 xla 4 > fo'I ) x'la t 2> la I Ixlo Ic ~
I XIQ I 4 ~ la ' 2 ~ 10' f 4ita I ) vto' I X la ~ . Sm 2$ 4 5 f(>10 )ala I I ola ' 9 ~ 10 I~
'ilo r lo'I Co $ 5 5 I Sxlo I )ito II 2xla c 9 I 2 xla'c )+to I 4 ~ 10 9 ~ la I Co 60 )vto ct I ela I ila I SXIO I PIV ~ Ifaa {9).~,oooooooo P lb 5 Sxta I ) ilo I 1rla ~ IQ ~
5 octa I'rlQ I 1 b Ia'>> 2 X la'I ~o I SilO I I ilo I la I
'9 10 I I
yxlo '
~ 5 ~
Copper(29) ." "~ CU4 ~ 5 )rla c I .i 10 I ) xla ~
Oa)alfafvm {44). ~ . ~ .. ~ . Od 1$ $ 5 )AIO I I 4ilotI 4 ~ 10 o 2 ~ ta ~
~
I Ala ~ bilo I xto ~ 2 I 9 .c I 0 ~ I brta 2 to c 1 Io I I
)ilatI
~ ~
)42 5 I rla 'c y e la'I 4vfa It xtoi 10 I O41$ 9 5 SilO I 1 ~ 10 ~ 4 ~ I) I
) i 10 Cvotvm (94) Cm ,
~ oo o ~ o ~ o ~ ~ ~
I 'c ~ la ,bolO>> 2 X la' I 4 o.lo t )eto I 10 ~ 4 lo I Cm ')4$
tp 5 4 ~ to>> I 'o 10 ' 2 i la 'I Sg 10 ~
Oo P) 5 )rlo fI I Irta I {
~
b,i 10 c
~
.10 I I I via 'I i la ~ )via>>It 2 I )ufo I lxta I 4" la c 4ila I f YIQ>><< r la'I
>fo'7 Cac 144 5 2 r la'I ) via Octmeafvm {12)eooooo ~ o ~ Oo 71 5 I x to'I e 5XIO I 4 eta 2 ~ IQ I It fo
)vta>>
4 rla ~ 1 ~ IO 10'tt It )bio Ic 4;IO I 4xla c )ala I 1 ~ la )ila i I.l I Cm 24$ 5 I via ~ 2 > Oaf'19), ~~~~o ~o~o~o~~~ Av 'Ifb 5 I ala ~ ,Silo I 4 ~ Ia ~ ~ ~
I I a la'I ~ Xla or 4>>O>> )AIO I I bbtq c ~
14Xla I S F 10 ~
1 ~ 10 c Cm 2cb 5 5:i la It I b la 'I 1 x IO'I 4xta I Av Iftl 1 X to't )Ala I I ila cI 5 ~ IO I I I p la'I ~ x 4 ala 'I )XIO I I 2 ata't Ix bala Srfa I e'la>> la'wlo
' 2 xf0 It 4XIO c Av 199 I xla I la'xlo I 4r'ta I Solo I Cac 24P 5 I
5 I rto lc b la' 4vto It 1 x lo' I 5
4 xla'I 4alo I 2 ~ la ~
2 ~ 14 c 4xto>> I 'i la'I 2 '.14>> Xta'P HOIAIUIII{y))~ ~ ~ ~ o ~ ooo ~ ~ ixlo c )ala I I rla Cm 2lb 5 I I vlo 4 via I 4:o 19 'I I x lo'.
la'I Hf 191 5 I iXIO I )ala I 2 ~ IO '~
P o 10 yxta I Cat 249 5 I xlo I 4 e 10'I ixla I 2 p Hofmlvm {4y)~ ~ eoeeooo ~ ~ Ito 144 )*la It 9<<ta ~ ~ lo SilO I I I > la I 4elo I 4rta t 2 4 10'I I )xta 9 xla I I
'rio Seto I Dy 14$ ) 'o 10 I I ilo'I . 9>lac 4 I 10'c HyJIaooa {I) ~ ~ ~ ~ ~ ~ ~ o ~ HS 5 5 <10 c I xlo ' lifo c ~ 14 I
Oycprocfvco {44) ~ ~ ~ ~ ~ ~~ 5
)xlb ct I ila I 'y ala I 4 x la'I ~ o I 5xla c xlo )eto c SAIO I Dy I ~ 4 I
)rto I a IO'I ~ r lo I ixto'I Svb )ala ' 4rlo I 5
4Xla t.
~ ~~
via'I
~
I ta't I y via ~
Iaitvm (49) Ia 11)ao 5 xla c I
'XIO Svto c 410 I tfactotalvac {f9) o. ~"
2 to
>10 I~ 7 x la'I lrto>> 1xlo I
~~ ~~o~~o~ oooo I y>fa I ixla I 2110 I I via I
~ Sc 2$ $ 5 I bola 'I 7 v lo'I )XIO>>
1 x 1 0'IC 2 x lo'I 2 >10'I la 114M 5 I x la'c SXIO I iilo >IO 'I c 2<10 I I~ 2$ iac Svto I 5 wlo . ~
I 1XIO I 5 xla ~
7 Silo I 5
I bvtO I S w lo ~ )x to' 2XIO I III 115al 5 2xla I I xla I 4 x la ~ ivfa' la '1$ 4 2 x 10'tt 4XIO ~ data>> I xlo I
I 2 X 10' 'I XIO 1 4 i 10 ~ 4 i la ~
t~
I xla Ia 4 x 14' 4xla It 'IO Ia II) 5 1 ala't Sxfa I 9 .Io ~ 9>ta I
Srlo>> xto' )xla " )xlo I ' I )xlo Ia )KIO I I ato 9 ~ 14 cf I rto' 5
I 4 )la'>> I xtO II )XIO'I Ioifao {5$) ~ ~ ~ o ~ o ~ o ~ ~ ~ o I 12$ 5 SXIO 4xla I 'ia>>
Silo tt x ta'I
~
(I 149 4 +la'I 2gta I I 2 xla'I 4 x la'I 4xlo c )via c~
tcblvac (45) ~ ~ ~ obooooo ~o 5 I ivlo I xlo0'xla I x la ~ 9 xlo'I I 124 5 4 xlo ~ SxlO I filO" 2 ~ la t<
I. Iy I 5 yxlo I
)ilo I I 2xlo I I xlo xla
~
I )xla It )xla I I xto
)xlo>>c I filo brta t
I bvto I 2 x lo ~ I ~
I 129 5 2hta I xla I c fVCOPIUUI {4$) oooooooo tu l)2 5 ixlO I 2)IOI I xlo I bxlo I brta I I 7 x la' 4AIO I )<f0 ) ilo c 2 xlo'I I xlo I x la't
~
Iy/) ~9,2 bta) I )xta I 5 ~ x I x 10'Ic III+ I (v I IO,I 21 10'I 4 xla 'c Silo I 1 xto'I la'via I vta I o )~o 4 vto'I 1$ 2 5 1 ft/2 1$ 2 rto I 2 via'I 4 ~ ta 'I I 1)1 ~ 5 1 1e lo't I
'via 1 ~ to I 2 r lo'I ycc) I .
Iv 1$ 4 S 4>to ~ 4XIQ I I . tO 1c 2XIO I I 9xto I Srla I SilO I )rftt o I y xla ~ bila ' )xln IIc I I)$ 5 )clatI 2 4 10 ~
4 cia 'I rgJ (U 1$ $ 5 9 xto I i lo'I )xlo 1xla c I )XIO 1xla I PAIO I 4 r fa+
I 7XIO I 4xlo I )Xlo' 2 XIO-I 5 Sxfo p 4xlo I bxlO ' 2 x la'
Amended 3? FR 23319
~
4 AttlNDI)4B APPSNDift B Ceacoaccecfocro ts Alt aad 9tecot h'bore Nefvtat Bocbvtovad~Coaftsvsd Caaoosftaffoso ts Alt vsd Ttecot *boro Hecvccit Da b~ d
~ f ee4 et e jtoscfo) ($ 4 ~ aoloo ef oad ~ I eppoedfo)
(too aeioo Tebfe I Tobfo II Tebfo I Table ft lcolot4 c <<ofueea I CotuI01s 2 Cefums I Cefums 1 ltomosf (efemto hvisbot) tooiopo 1 Cofvms I Cotuoa 5 Colvcss I Colveia 5 54meet (eleeifo ausibot) hft bYelet hft Wetot hf0 lVetot, hit Vte tot tuc/nil) (hc/mf) fpc/mf) Isc/ml) 4 c/tef) Itrc/at) tec/mff feet'eifl toiiso ($ )I:...". . ~ ~ I 154 I 5 i io i*ID t
~ )vfO t t <fo ~
Idio t Iv lo' 4441D
~ IU 4
i9))... Hp 2)P 5 I
4 A to 'f I ~ 14' Oito 0 ~ 10' f I loe>>
4 ~ lo rt ) lo
.10
~
~
0 I 1)5 5 lot I'elo t I ) ~ 14 oil I iofo 0 2 r lo'ofo
~ to clo'
~
~ ~ 0' Np 1)9 5 t ~ lo 4 Ato irlo l ).io 4
~
I I
~
'I ~ 10 ~ 0 4 I ~
I ~
4 ~
trldfrts Itt) It 100 ~o 5 in' lot )
~~ ~ ~ ~ eoo ~ ~ ~
lt l92 I
5 4r lo olo 'I 5'elo I 0'IO'0
'Irlo f C
,,l
~
9xlo'4
'io'4
)
2 4
4
'i lo
~
~
10 to
~
f 4
~ Nice
'optvsfvts I(25).. . ~ ~ ~ ~ ~ . ~ ~ .. Nl)9 NI bl I
5 S ~
Silo t 4xlo 4 4
4 4
~
~
o 10 to I
I 1 ~
leloo 1 ~
'to 100
~
)
2 1
5 15 10 I
~
~
1 0010'
)tlof
~
I U
2) fo > I r to'4 ~ r io 0 5xl4 I I ) v toot I ofo 4 10 ~
ft I04 5 I )AIO t 9vlo 0 5AIO 0 5 xlo' Nl 45 5 0XIO t iolo C 1 r.lo 4
~
~
I ~ 14 ~
Cc to)5 xlo't 2rio f )clo c I SAID t ) ~ lo 0 I olo ~
Itoa t14) oooooeoe ~ 0 ~ eo ~ 5 I
9 I BIO' totot ) xlo ~
xto'5:
10 I Niobium. Hb 0)ts 5 I <<to t I i, lo'1 4 ~ 10 0 4 ~ IO '
Ixlo t 2rto 1 5 KIO ~ brio (Colvsiblvts) (4)), I 2 x to't . I ~ IO f 5 ~ IO.." ~ lo 0 to $ 9 5 r.to'4 2xlo 4 c Hb 95 Sxlo t )Alo l lo ~ 'I ~
5 XIO' I0 ~
5 2 o
'AID 2
t)4) Kt ~ 5 so I
5vb brio 4 t x lo ~ ~ ~ ~ ~ ~~ I I Alo't 5 <<to'I ) vlo' I il4 0 0 tttTPCOS oooo ~~~~o KI I5 Ivb I e'10 0 ) tlo t N'b 0t 5 4 cto' 5 xto'f tot O.ln ~
It I XlO ~ t 2o'IO 4 I I Sxfo 4 lrfn tI )elo 0
e. IJ ~
Kt Kt II Svb 5ub I xlo ~ 2410 l
)xlo ff Ottsfvso (74). ~ ~ , ~ . Oo IIS 5 5 XIOet xlo'
)glo 2 xlo'l 2 r.l4
) ito 4
~ PolOc laaibvaVta [SP) ooo ~ eoo ~ 14 140 5 lrfo xlo't t P xlo xlo
~
~
5xlo 4 r.lo 0
0 2xlo Oo 101th I
5 5
2 ~ 10 I txlo c 4ito tc Peto t
) ~ 10 c I I P xlo 4 I frto c 0 x to ~ 4XIO c I 0rclo 0 PAID f )Ato ) ~ lo f I'b 105 bxlo '
toed II2) oooeo roe 5 5
~o~~ ~
ufo ~ IxlD f 4XIO 0 Oo 191 5 I xlo ~
5 AIO'4 4 ~ lo ~
1 ~ lo ~
Pb 110 I 2 I xlo'4 4 vlo ~ @ f0 lf I xlo' I II v)0 t, 5 x (0'f I xlo ~, 1 ~ 10 ~
5 I 2 AID '4 Sxlo f I vloe>> xlo', 04 19) 5 ri xlo tf 2elo f I <ID ~ belD 4 tb 2'I2 )xtO" 4 xloet 4vtO '4 2xlo c I ) x)4 t) )xto 4 0AIO 4 5 ~ 10 c 5
I 2 A 10'! S xlo
~ PAiO>> 2xlo f Psfiodlvao tib). ~, ~ .~.... td Io) 5 fl xl4' 0 Iilo I 5 AIO ~ ',
5 ~ lo ~
lWOffVta ttt)e ~ ~ eeeoooo tv ltt 5 b<<10 t )xlo f 4 1 xlo ~ I xlOec I ~
t x)o't, I riiO 4 )Alo 4 5 ~ to ~
I Silo tt 5 cfO )xfo 4 I x 10' I
Pd 109 5 bvto ti Solo 4 2 <lo ~
0 oto 4 lo I 10 0 t xin ~ 5 vfo f I iv)4 )ufo l I <<10 4 t olo ~
M440os444 f)$ )oo ~ e~e~ ~ Ms $ 2 5 I
2.e xlo r. 0
~
5Afo 0 lrlo C Phvctbotvo <15) ~ eo ~ oeeo ~ P )2 5 1 y)0 40 SAID 0 ) cto ~
2 ~ lo c 4 10 ufo'xlo f I telo 0 lxlD 0 I ~ x lo'ot 1 xlo ~ )rcfo 0
)AIO c Ms $4 fb 5 I
~
4 v lo'4 lrlo f c I vfo ~ I r. 10' Ploffsvts pl)..,.. tl I ~I 5 ~ vlo 0, 4<10 o ) elo" 4 I ~ I0 ~ II)
Ms S4 5 I Ato t 4vlo )vl4 4 I%to 0 I 4xto t lxlo f 4 ) ct04 I tloc I Sxlo t )xlo cl 2xlo c I xlo 0 Pt I9)so 5 .1 xto', 1 xlo 1 ifo t 'I c io 4 t r Io't brio )xlO 2 F 10 ~ I 5 xlo o. )xto l )xto t ', I ilo f 19tts Motcvtt {IO) ~ ~~ rot ~ o ~ ~ HQ 5 I Ivlo t $ 410 f 4
'xlo 2 x 10' ** tc 10) 5 I rlO 4 ~ )clotl 4 cto ~ 0 ifo ~
I 'io'4 0vlo f 4vlo ~ 5 I c ) telo << Srlo I rlo ~ 1 ufo 0 5
lito'
~
HQ IQP I lxlo f 9xlo 4 to'XIO tt 19tts 5 bxlo' )vlo f 1 %10
'0 I eto 4 txlo t '0'lo c 2xlo 4 2 xf0'! I
' xlo'4 )xlo 1 1 via c 9 vf0
'Io) 5 4 5 ~
HQ I lxfo 5 ~ 10-f 4>to c I XiOr) i'lo'c tl '191 5 brio t ixlo 4 )wto 4 I ~ lo 0<<f0~
txfo tt 5'ilo 4 SilO 4 2 I 4xlo t ) <to'4 2+10 4 I A lo o~~g Motgbdosvoo (42 ) ~ . ~,. Me 09
~ 5 lifn I 'o fo'0 trio 0Ic 4ilO ' Ptvfoafuts {04).,0 ...... pu 2)I 2xlo '1 I <<loe ~ t <<to ~ lo 'o~
Noedtmfvsc t40) .. ~ ~ .. I Ifd 1>' 1010 i 5iiO
'o'0 Ivto I i.fo c tu 250 5
I 5.to>> I << to ~ lhto>>
00 5
5 ~ to '~
I 10 2elo 1
'Oi 5 ~
2 xfo.',1 I VIII ~
4 v lo'0 ~ 5 ~ IO'o~
HII lit 5 4 i lo 1 4.10 f 1 . I 4 ilo'0 I I ul>> ~
I ef1 I 1 "10 4 I I 1 ~ 10't ) ~ 14 I lOI 4 ~
io 0 tu 140 ~
fo>> IAI) 4:IJ ' 5 0.14 <<Xf ii I Hd 149 5 2 ~ 10 I ~ 'I 0) 4 ~ 10 c 1 ~ ln 0 I 0
'ilo I ~ ~ 0>> I 5 ilo +~
I I
lo ~ I AID f S >10 ~ 1 i.lo PII 241 5 0clo>> t ~ '0 4 )AIO>> 2 +to't8 g I I 4 Xlo'4 4xlD f I xf0' I xlo I
, **AddeC 37 FRe23319. w c fitful)26))dcf1 37 FR 23319 'eC
s I
I I I
\ I AF9fftafX 0 A99lftDI)( tt ' I CeesoJ<<uoKoeo Ie Atr eed Werer Alo<<o Heh)rel Sesbgrovad~CeaKavoJ) CoassafreKeas la Afr eau) Wessr Abovo ftesvrot SesbgiovaJS goaKavec)
(5so aoiss el oed ef ~ )JIJsecfa) (Sso slol so el eed el epfJoadfo)
Tells I 'fable tt Tello I fable ft Sfoeseec (oremfc avmbor) tsesepe I Col<<me I Col<<me 2 Celvma t Cetvma 2 5tsMcaf (efelafc Iivmbor) tsolopo I Cot<<ma I Cefvma 2 Cofvssa I Colvme 2 Alr We lot Alr We)sr A4 Welot Alr Weier IJJ g/mf) (xi/mf) 6 r/mf) txr/mt) (rc/Iel) IXI/mf) (rc/MV (<<I/eilt Teche<<H<<es (4))... Tc 94ei 5 Sxlo ) 4r'10 I 1 x) a ~ I xla txlo) s fho>>vm (90).. ~~
~
~~ ~, .Th 2)4 4)JIO o
)xla 5 xlo ~ 2xla~ 2 Tc 94 5 1
4rlo xlo s
)r:to 1 )rla's I I xta 2<10
~
s I xto ~ Thvllvm (49).... TM Ifa 4 XIO c
~
5 w lo txtO
~
I t v ta~
I xlo e 5 cia'<<la
~ lo I s
~ ~
I 2 x lo. > t xto!I 4 A lo ~ 5rfo I 5 X la ~ I x la'I I x la ~
5 . Io'I Tc 97ra 5 1 Ala ~ i>f0 ~ xlo ~ 4 r IO ~ TM tlt I xlo r I xlO I 4 4 IO' 5 ~ lo ~
t 1 xlo r 5110 I 5 X IO ~
2XIO s 2xlo > I xla'I 4 <<to ~
, 5 <<to'I Tc 91 5 I XIO I 5Xla I 4xlo f 2xla I la7$ 0fo ~ ~ A ~ A ~ A ~ i A ~ A ~ ~ tn 11) 4 x la'r 1 xto I I A14 I 9 rta I
)xlo r 1) lo I I x lo ~ ~ Xlo I' 5 xto ~ iota s 2<10 s Afo I 5 4)JIO ) 2 5 lo I Alo I ilo'I te 125 5 trta I 5 v)a' i 4 la ~ lifo II P>>
Ixla I .4AIQ I 5xl4 f 2 xlo I I 4 clo ~ S A lo' ~ 1 AIO ~ SAIO Tc 99 2 x lo ~
I xlo I 7XIO I lxl4 s Tve9sfsa {Wolfram) {74).. W 14) 5 2 XIO's I xta ' 4AIO s 4 Ato 4 xla's 5) lo) .)xlo s 1 Jr f0' I Ixfa f > la'I 4'Ala I ~
'.10 T<<vrtves (52)JA ~ . ~, ~, ~,. Te Ilies 4 w)0') 5 mfa'I I x la ~
)xla I W )45 5 4 bio'r 4xtO I 2 ~ 10 s I Ala s Q
I rla r )xlo I 4 vto! I xfo I I filo I )Alo I 4ilo s IAIO I I) fe 127m Ixfa f 2 h IO'I 5)JIO I 4xln I ~ W ISY 5 4 x tat> )xlo I 1 cia IJ )AIO s 4Alo I )4 IQ I I,>> la ~ 5 xla'I I )Ala r )xlo s I efo I '4-10 I Te l)J 5 2ilo s) Srlo I 4)J Ia s ) xla' Urealves (92)A ~ ~ A ~ A ~ A ~ A ~ U 2)0 5 )xto>> I r lo ~ IrlD>> 5 ~ 10 ~ . C)
~
I 9rla Srla I )xla I 1 ) la'I I xlo.>> lxlo I 4 ~ IO'I 5 sta ~
fe 119es 5 ~ xla
')xtO I I trta I ) )Jto s ) xto'I U 1)1 5 I xto.i ~ 4 iffJ ~ 5 xlO 'I )rlo II I 4r lo ~
1)L 10 s 2 xlo'I I 1)'10 'I 4 xla ~ 9r IO>> )xlo To 129 5 5 A 10 ~ 2xla I 1 xlQ > SAI4 I V 25) 5 S r lat I~ 9 r la's 1 to'! I lrla II 4 i IO'I
~
fe ISles I
5 I
4 x 10 4xlo r 2xlo r
~
2AIO I
)rlo I' I ilo I xto-r I xla I 4 Aloe 4XID s 4AIO I 4rlo I V 2)4 I x lor>>
4 x lof>>
I xlof Is 9ila s 9 xla' Ala ~
1 xlo>>
4vlO>>
Silo l<<10
)AIO I
'st Te 1)1 ~ 5 I
2<IO r I xlo r X la 4rlo I
~, 1)fla x la
~
)xlo 1 xlD'I I U 2)5 5 x 14 Is I xlo. Is 9
~
4 <<
i laIo.' ~ lifo>>'I 4 cto Silo
)AIO I M I
TciMeel (45), ,. Th 144 5 I
)>>4 r la ~
I AIO I )xlo ss 4 r. 1 0' V 274 4 X IO'. ' I o lo. I )AIO 'I '5 vlo I I I : I rto s ' Xto )r lo'I I glO..II I XIO s 4rlO>> lrlo II Tlolf!res (41), s . Tl 100 )>IO I I xtO I 9 x 10'.I 4 yta- ~ V 2)l ~
7 x la'>> I r lo: I 1 xla'>> 4 <to I <<14 ~
7xta I 4xlo I 2 Ala ~ I xfa 's ~ t<<o,s 5 clo 'I 4 Ata ~
fl )0l 5 1 x la ~ 9710 s 7 )rto I 1 Ala' U 240 ~
2 xlo. f ) r lo,' Silo ss SilO I I 9xla > Silo I 4 ilo I
)<<fo I 2 eta ~ 2 x la I ~ via:I I)'
4xlo )ila II Tl 202 5 sr)4 r
I
) )la I
)rlo sI I xlo ~ UAeeiure) Yxla>>
xta'>>
). A I 1 i 10'>>
lo'I
)AIO f 10 4xlO vto I x IP,'I 1 vfa I Tt )Oc 5 I
2 ~
4xtO r
)XIO I
)itO I
).Alo I 2 x la'I 9gto <<
7 I x la'I 4XIO I Veaodtvat {2)).~ ... ~ .. III 44 4
2 r la:r 4xfo ~
'ilo,'x la ~
2 4
2 x
<to'1 5 v'lo I lifO I Thorteei (90)A ~ A' A~ A~ A~ ~ Th 227 5 )X la sxto'X I x lo )XIQ s Xsaoa (54) ~ ~ ~ Air<<i<<i<<i~ Xo flies 2xfO I I ala.'cta S
4XIQ Is l)l ~~~ ~~ ~ ~ ~~
I )X IO I ~ )X I x la'I )AIO r Th 11 ~ 9X 14
~
IO
IO'X Io )X lo IO' IQ'X Xo Xo I))M 5 vis 5vb I x lo 'I
~ ~ A ~ ~ ~ ~ A~ ~ ~ ~
))JIO r
~ ~~ ~ ~ ~ ~~
I, 1! Io.
~ ~ ~ ~ ~ ~ ~~ ~ ~~ ~
~ ~ ~ ~ ~ ~
4)J 4X 10 IX lo c 4xlo IAIO I CXIQ 'I Xo 1)$ 5<<b s T )XIQ )X IO' ...
~ ~~ ~ ~~
)Xla
Th 1)0 5 ., SX IP YIf~ Iblum pa) ~, ~ ~ Tb 175 .5 7814 r Sxla I 2AIO s I slo ~
1 I IX IQ I I ~ 'X SX IQ' ~ << la I 5h fa'1 TIIO I I
,. IO
~
~
fh)SI IO':
~ 5 I Iu IO SEII) 4 Yttrfum I) tf, Aln r 4<< fa' 4<<los JC IX IQ lo'X
~ ~ Y 94 I 2 Ala ox f0 )ilo II
'r I ~
II) 10 I cia I 4) 1 xIO Th 1)1 5 tt ID .5) )O I) IO ' lxto s Y 9fra )AIO I ta'hto I 5 ILIO s~rI))
SCh
'>lo lX 10 tXIO>>I 4X lo t
'X I
lx lO'II 10 to IXIQ' )xto I txto I 4<<to I )glo Sh)
Th iisfvrct 5 I )X IO
)X IO'414 s
IX IX to "{ Ix lo Y 91 4xfa I 4 vlO ~
I xlo I >>)O II I-) n 1 xlo.s 4 x.lo ~
I XIO's 1 << la sm Y 92 4xla r illa I Isla I 4 fat f)~C
~
'i I
Cl PJ A)IFKIIOIX O n
ht ct Coaeoattetloao ta Alr oad Water A'Love tfotvrot Socbotevad<<Coattavod yo (Seo a ~ I ~ 0 O'I ~ hd ~ I oyy ~ adlo)
TOMO I Tettto Il I I I
I ~
Sletaeaf {otomtc avtabot) tcotofi ~ I Colvthh I Colvala 2 Cotvma 1 Colvma 2 I I
M Alr Water Alr Water ~ ~
Q c/thl) 4 I/ml) Q c/ml) tt c/ml) I Zlae tSOI ~~ 0~ ~ 000 ~ Zabs 5 I XIO-y lxlo II 4 Xtov I XIO-c 1 4 xlo-0 5XIO 2 @to ~ 2 tf to ~
Za 49m 5 4 X!0-r 2XIO I z to ~ Z XIO-I '0 I 2xlo y I
'xlo IXIO c 4 XIO-I yhto I Srlo I 2 rflo I 10-1 I 1 Zab9 5 2 0 I
I 9)loe 5!Io I 2 BIO-r 2 ~ 10 I Zltcealvta tbo). Zr 95 5 'I 0 10 I 2 >.10 I dxlo 0 5 hlo ~
~ ~~~ ~ .
1 2510 I 2 > 10'I 1 xlo I ~ xlo c Zr 95 5 lxlo r 2XIO 4 xlo ~ 4XIO I 1 2 XIO ~ I
'>tlo I XIO'I bX)0 I Zr 91 5 I xlo! 5 X)0 ~ 4 X lo ~
2xlO I 0 1 9hto 0 S Xlo ~ 2 Xlo ~ 2+10 I Aay ~ labia rod toavcttdo ..". 00000 Svb I hlo ~ 2 vlo ~
~0 ~ ~ ~0 ~
~ yj aot II~ ted above <<lth decoy alodo other Ihea O
~ tahe ~ tat ~ Itoa ot eooatoaeove httfoa aotf <<eta Iodt ~ ottto ~ ~
tltiif I I I ~ ~ ~ Ihoa 2
~
~
O hovt ~ .
Aay etoet ~ Iodtoavtttde ~~0~0~ 000 ~ 0 ~ 0 ~ ~ 0 ~ 0 ~ 2 X to~ tt X to"I' X)00>> SX)O 4 aot litttd ol ~ 0 ~ <<hh det ~ y taodo ~ It ~ I Ihea OIoho ~ Iii I ~ I ~ a ~ I
~ Ooofoaeove
~
hI ~ I ~ a O
~ ad <<ith todieottioe heft lif~ greet ~ t thea 2 hovte.
Aay etaot ~ todioavcttdo ~ ~ 00000000 ~ 0 ~ 0 ~ 000 F 0 Oxto~ . 4xto ~ Rxto <<
aot li~ Itd oooo ~ . <<htch docoye tty ~ Ifiho ~ alt ~
@) p-8
~tt ot ~ fioat ~ tl ~ ove httloa.
~ 1
0'
~ ~
~ ~ ~ ~ r N ~ bolubfe (S)) Snaolub)e (S)o 0 "sub" means thaL values gleet> aro foc eubmerefoct)n a seal(spbeftca) )ftf)nits cloud of att borne D>aCtclat,
~ i ~ ar XnIC In anr ra<<< <<ht>r Ihr> ~ u ~ in>a<uic sn aa4>es waco> 4 iu <<r <han ane > ~ Ie no>ih.lt. I>ar hini<inc
~
e>r>< ><sea<>eel aa Iti I s>>or/ ~ ool shia .>le>eon>il s>see<<>ot Ior 4>>et ~
r>rwh <a tr<<>e<.
I it ><at ~ I n>>>i <<n 1 ~ <eorm>~~ian~~
~~~ I~ 4'si In i si>oiio'sr Lie'aria, lho'<ii<ii<et~~
~
~~s ~ Ines I-s rial< ia.~~
~~~ aar.>>> r I <sat I ao S,u,ri lsrlo><easier, I >>nee >e'> ~ es ~ i<<i<os ~ > ~ eie <ia ~ ~ >vs I ~ t ~ i isr'isse<~~
~~~ ~ Ii~~
~~.'.":;.". luce'eir>>>sr .is>>>~~
~
~~<<.>>iu ei. <. se.ease<or sea I >>>> ~~~
~~I.",'"~~
~~.alt I .ss l>> r Ie> I> I << I< r o> ~ ~ site>s>r<<ee>a>t>r <<4 n~~
~~~ .i i>> ~ ie"a"aer I'r eon< e.l ei 4 ~ ais ~ . I os <<>I l>ee~~
~~'I ~ r ~~~
~~ta:~~
~~ult<<e I iis ihr sue<ease ~ >osis iie I ~ ~ ~ ~ I t~~
~
~~~ oe 1 ~~~
~~ei ~~~
~~se:>~~
~
~~ti sit<a i~~
~
~~awrir )I >a>ies.sio>.>ra .I. II, <<eeltoe i<<>eplie~~
~~~ ~ ~ I maes I > ~ as< I~~
~~<< ~ tee rnl~~
~~~ >o>r~~
~
~~i>a ~~~
~~os LII' <<sr 'ill'< ~, <<i>V~~
~~~ ear>> eros <<or re.<<o ~ ~ oi ~ ii <<eo o>ii>1 lr la<i<i>s l>aal~~
~~~ ~~~
~~slr Iul owoeg Isis < >>>oo ~s I~ ~ v III'> ~~~
~~'ll 1'< s Lt)'>'o~~
2 ff rtthrr tt>o tetr>>I>ty ur the )nose% cu>o.chtralloa ot any'tadloaucllde iif A)i)<Cndt! u chal) bel ltt tho mle(ufo (o ho'S 1 bnuwn, the ti>will>a>o sat>>re tur )su>
Fuc I ur pu cs uf Table I, Cul. 1 0 x 10 '>
Tste4 'table lf
~~b. I if psi>peo.rs ief Stable I. t'ut 2 ) C ln <~~
S C. )'<p..ia s of Tshle )l. t:ul 1-2 et )0'> a, Elle>cn) (ctomfc nun>b<<)'and betsps
d. Yor Pu>P- i ~ uf Tub)c fl, Cu).2-SX)0 ~ Caluma 1 Column S C@I<lnai> I CalumaS -(:
~~A>r gc>u<I) >e<<lee Atc >wclsn)) u><<>rr (tr/>>>1)~~
2. 11 u>>y ot tlic cond)1(ons s)wc)bed hr)ovr (re<<>al) 1
~ >P met. Ihc ceil>rite in<>l>id <e>sls>es ~ fire>>>cd bete<<< >w sy hi u.r<1 In 1>ru uf ttsu c ~ )srslllcd ff Il Is t now a I hat f)c 00, 1 12$ . t IX, ( I."2, 1 121. (t 122, ln )ear.sr<.sph 2 ~ >nsrC. I ~ >e>c tl unit), I'4 210, Pu2>u, Al CII, Its ..A II~ t:I,
~~a. )t Itic 14rwttty of carh cadlonuclhfe ln 11 ~ .".'a. Ar 2:I. Ilc:e. 'I li CJ<. )'a '1>. T4 P:, YI>>~~
h<<I, 1'<a 2>C. I'I 'I. e>>il Iu>,"A e>r swl tuawul.. ~ oo ~ ooooooto SXIO4 )XI(to I thr Wil~ lailr I ~ LnnWn tiut the Ce>>i<mt>aLI>>>l ~
cs )111 I ~ L>euwn llisl 4> <<>. I Irl, I I"a, 1 I V, It III I IYI, t<
Cef <Or ur Oo rr of tho cne)4<>>ur)4)es ln the Ei labia tl uu>y> ~ I Ii 4> ) oi Clast II ~ I~ )I i Ita <ie n>lscu<c ts >o>L 4>suwn. clio c>>nrr>>cent) >>I
~n I'a DI 11< i<1'I 1 iii 2>c I I 'ri ra<4 )ii> ~ o I> ~ easel SXIO4 ~ oootttootoo SX)04 C
I' l)mlt )ocr lhr >>i)et>>>c I ~ the )toi>L a)arri>)rd oc In e \e'i Ie Il
~r tn AP)erin)>c 'llr 1 or the rni))i >>>>cl)ile In the 4 f1 >I i< Ln<<wi>
c<
tl>>l ueslyl, I Ii ~ lie, II~
dl >>>. I I.'V. >I Its. I IW, I IJ>, ls>>>e 8 )l<sg tho luwrsL cunccntcntlu>l
~ ciilil4>t ~~l<<r<<asl, SXIO4 ~ to o o o e o to o ~ OX)(te~~
)>sa,<<. >r Il>I i. e nunc> Ile sl > I I V, t<<<e>e II au> y), Ila hoe aii4 II~
r<>Illy <d rsCh rndhen<>c'Ilds In thr mlstii>r 1 ~ n>>t k>>esw>l. l><<L It te hwuwn 2.'I <<>e is at p> west,,
~~If >I I I<>>area lla';C.~~
~~21'>.~~
~
~~Let:I,~~
~
~~lie al r>> Ii P>>~~
~~> essa>>lei CO>, I'e>~~
~~I awol Y>>>>, I I V. I Ii f<e\ au4 1>L 'IU<<> ~ i>>el~~
~ ottttottett SX I(ye ~ ttoo ~ tattoos )XIII ttaaL cr>tiil>> cai>leewurtldra s)aer)1)rd )>> Apt too.wast..... SX) tyo ) X)O'" ~ to o to o toot<<a a>ouse>ss><>a<a aevi 1eb ~ >0, hc ~ I, Pe>ee)IC -)Sr are Wut )a>C:r>>L I>> t)ir Inlet>>>C. )I Ils<<l 2 X I 0'>I IXIO'u i I ~ 'll nie ias'I >uo'ariel,, oooooototooo ~ oooootoooota thr Cn>>ccntr.>t>esn 1>>>nt lur the iidati>>e te a, asset i> ~ ~
~~I> ~ ~~~
1) sl n L>>>>w>s lie<<l a>> lsseaeae>>r>s a<us hc O'I aie seal the loons- 1 res>>re>>trull sn ltw>) t ~ te< lnri) In SXIO n )X)o.u t A)e)w<><l>c 'l>> h>C a>iy C.><flash>>rlhtr vo>ilrh I ~
~
)1 >I >a L>><<wn Iha> hr '."I,
'I'>s M, I'a 4>, I'u:'.u. Pi>
l "4'4 I'>> .o<ii. 1'> CI ', I'u "I>, Cm >c, I:I ~ IQ au I CI 2>1
~ o o o to o o o to <<
Dut S>au<<a tO be abitnt flu>n Lhe mtatucc; 2 x) o'u ~ toototttooo IXIO O ~ eoo ~ ootoootoe h or e )f fhe m)>>Lute of fidlonucl)dce con. S Pot putposre of this ftnte ~ ta<1)o all>a nf ursi>l<>nl aud )ls daughter pl<est>lots hue))de may be en>>a)drcrd aa >o>t prrac>>L tn in ole duaL p>tuc Ln chc>ntcsl pc>>ccrc)>sg of a mlcture If (a) the Iat)a Lhe Ura>>li>>n >ice, the values a)irclhril brtow tton n! that raillonurlldo In the n>lstuce oiay be used ln ltcu of those dc)el>nlhcd In os (Ca) Lo Lhe conrrlitrntlun 11>n)t for tl>at ll 30 FR 15&01
~~~ ws>'st ie>4.<wrc atlh par<<graph 1 a>se I ~ or thoar.e e>>afoCCIDCe) I>< 1< s>h/>ate>st 2 aii'I 2 ~ I>eire~~
~ Fnr Pii>ti".ra Ot 1'ehl ~ 1, Ciil I o tr >< oe ~ nl)ilia art)'ally, <>C 2 6 r 10
~
~~IX)0<<~~
~~ca<1)wnuc)lifo e)irrthei) I>> Tnble~~
~~)am<)lc )) (.If)'Ct] di>ce I>UL cscccd Ci ~~~
~~. )~~
~~) and (I>) the all>>i of ~ ><eh~~
~~)'>Revisf.d nf AP~~
~~<<<<ERRATUM)~~
~~"210, hc 227, This 1tne should ref)ds~~
~ () c. h>f,,' Rn 2280 Ps 230, Pu 241o fsy)d n alii>>>l ii>eai>li>>ii, 7$ I>>lrl <aero>i>> <2< Css <cf
~~<<a~~
~
~~~ S pr' u' '~~
~~OS)~~
~~~ or>,) <<>I i<C ii Siss<.il i<>.a>i isis>~~
~
oe
~~~ ~~~
~~ruth>a fe C atl >hi Ca<I)i>n>la')Idea CO>> ~ 1<lett>) ne~~
~~>< il ~~~
~
~~Ir',r<.L I>> Itib p<lalO <Ii'ra <oit ~ i< re>I Bk 2I>9 nte not>) . W<c) tas f<>~~
OO
~~>i ) > fess>)oae'eo, I't Isa>ele II. (eil I~~
~
~~a" I>ill;-. WC. It )0 "~~
~~.I I>> ~~~
'i 1 I e. >-s
~~'>>>> H H h>~~
~~<>>I g<oi .. <<>ps<.>~~
~
~~v co~~
~~.C In'I lint>>lee) u>u>i)i>ln: >i> 2 Il'Cae'Iu>hn Aff Cs )~~
~~Sf) Cs" ' ' -i~~
~~) tc cut >c >ne>rc uf a)c >situ>4)>>c.<tno>>>~~
~~Append(a b f>em 2$ pf( 10)) 4 casey) oe ethel<<leo note<)<~~
~~I I ' '~~

ML18024A874

Text

.'

0.9 where

Navigation menu

Search