Text

Proposed Tech Specs Re Implementation of Generic Ltr 89-01, Removing Radiological ETS Procedural Details to ODCM & Placing Radiological ETS Programmatic Controls in Administrative Tech Specs
	ML20247D823
Person / Time
Site:	Callaway
Issue date:	09/06/1989
From:	; UNION ELECTRIC CO.
To:	;
Shared Package
ML20247D815	List: ML20247D811; ML20247D823; ML20247D829; ML20247D836;
References
	GL-89-01, GL-89-1, ULNRC-2070, NUDOCS 8909150097
	Download: ML20247D823 (79)
	v • d • e

. _ _ _ _ _ _

ULNRC-20 70 PROPOSED TECHNICAL SPECIFICATION CHANGES Pages:

1-4 3/4 12-5.

Insert A 3/4 12-6 1-6 3/4 12-7 3/4 3-63 3/4 12-8 3/4 3-64 3/4 12-9 3/4 3-65 3/4 12-10 3/4 3-66 3/4 12-11 3/4 3-67 3/4 12-12 3/4 3-68 3/4 12-13 3/4 3-69 3/4 12-14 3/4 3-70 B 3/4 3-5 3/4 3-71 B 3/4 3-6 3/4 3-72 B 3/4 11-1 3/4' 3-73 B 3/4 11-2 3/4 3-74 B 3/4 11-3 3/4 3-75 B 3/4 11-4 Insert AA B 3/4 11-5 3/4 11-l' B 3/4 11-6 3/4 11-2 B 3/4 11-7 3/4 11-3 B 3/4 12-1 3/4 11-4 B 3/4 12-2 3/4 11-5 6-17 3/4 11-6 Insert B 3/4 11-8 6-18 3/4 11-9 Insert C 3/4 11-10 6-18a 3/4 11-11 6-19 3/4 11-12 Insert CC 3/4 11-13 6-20 3/4 11-14 6-22 3/4 11-17 Insert D 3/4 11-18 6-24 3/4 12-1 6-25 3/4 12-2 Insert E and F 3/4 12-3 6-26 3/4 12-4 8909150097 890906

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- 0FFSITE DOSE CALCULATION MANUAL 1.17 The OFFSITE DOSE CALCULATION h.ANUAL (ODCM) shall contain the methodology l

and parameters used in the calculation of offsite doses due to. radioactive gaseous and liquid effluents, in'the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, an in the_c t of the Environmental Radiological Monitoring Program.

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OPERABLE - OPERABILITY 1.18 A system, subsystem, train, component' or device shall be OPERABLE'or l

- have OPERABILITY when it is capable of performing its specified function (s),

and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, i,ubsystem, train, component, or device to perform'its :

function (s) are also capable of performing their related support function (s).

OPERATIONAL MODE - MODE 139 e An OPERATIONAL MODE (i.e., MODE) shall correspond to my one inclusive l

combination of core reactivity condition, power level, anc' average reactor coolant temperature specified in Table 1.2.

PHYSICS TESTS 1.2.0 PHYSICS TESTS shall be those tests performed to measure the fundamental.

I nuclear characteristics of the core and related instrumentation:

(1) described in Chapter 14.0 of the FSAR, or (2) authori:ed under the provisions of

..10 CFR 50.59,' or (3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE 1.21 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tuce l

1eakage) througn a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.

4 PROCE55' CONTROL PROGRAM Sck S 3 1.22 The PROCESS CCNTROL PROGRAM shall contain the current SmA, sampling, l

analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of l

actual or simulatad wet solid wastes will be accomplished in such a way as to j

assure compliance with8534884 i ::,....

A and State 1

regulations, burial ground requirements, and other requirements governing I

the disposal of 4Ae.rac';oactive waste.

h to C.FR. Paxh 20flM 7/7 i

PURGE - PURGING J

1.23. PURGE or PURGING shall be any controlled process of discharging air or l

gas from a confinement, to maintain temperature, oressure, numidity, concentra-tion or other coerating :endition, in sucn a manner that replacement air or gas is reouired to purify the :enfinement.

CALLAWAY - UNIT 1 1-4 Amencment No.,2.5, 25

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Insert A The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semi-annual Radioactive Effluent Release Reports required by Specifications 6.9.1.6 and 6.9.1.7.

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SOURCE CHECX 1.33 A SOURCE CHECK shall be the qualitative assessment of channel-' response j.

when.the channel sensor is exposed to a source of increased radioactivity.

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STAGGERED TEST BASIS 1.341 A STAGGERED. TEST SAb1S-shall'-consist -of:" ~~~ -"~~ " '

l a.

A test schedule for n systems, subsystems, trains, or other

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

b.

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

THERMAL POWER 1.35 THERMAL POWER shall be the total core heat transfer rate to the reactor coolant.

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TRIP ACTUATING DEVICE OPERATIONAL TEST

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1.36 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall. consist of operating the l

Trip. Actur.cing Device and verifying OPERABILITY of alarm, interlock and/or trip functions. The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that.it actuates at the required Setpoint within the required accuracy.

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. UNIDENTIFIED LEAKAGE 1.3 7 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CDNTRDLLED LEAKAGE.

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UNRESTRICTED AREA l.38 An UNRESTRICTED AREA shall be any crea at er beyond the SITE BOUNDARY j

access to wnich is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any i

area within the SITE BOUNCARY used for residential quarters or for incustrial, L

commercial, institutional, and/or recreational purcoses.

CALLAWAY - UNIT 1 1-6 Amencment No. 75, 23, 2E

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_ _ - _ = _ - _ _ _ _ _ _ - _ - _ - _ - _ _ - -

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(UMENTATION

-RAD 10A VE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING C ITION FOR OPERATION 7

l-3.3.3.9 'The radio tive liquid effluent monitoring instrumental' n channels shown in Table 3.3 2 shall be OPERABLE with their Alarm / Trip tpoints set to ensure that the limit of Specification 3.11.1.1-are not exc ded. The Alarm /

Trip Setpoints of thes channels shall be determined and justed in accordance with the methodology an parameters in the OFFSITE 00SE ALCULATION MANUAL (00CM).

APPLICABILITY: At all time-l ACTION:,

With a radioactive lic 'd efflup t montioring instrumentation channel a.

Alarm / Trip Setpoint less consgtvative than required by the above g;

-specification..immediatel spspend the release of radioactive liquid i

effluents monitored by they fected= channel, or declare the channel inoperable.

b.

With less than the mirlimum number f radioactive liquid effluent monitoring instrume fation channels PERABLE, take the ACTION shown in Table 3.3-12.

estore the inoperab e instrumentation to OPERABLE-status within t time specified in the KTION, or explain in the next Semiannisal Radioactive Effluent Releas Report, pursuant to

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Specification [6.9.1.7,whythisinoperability as not corrected within the 1me specified.

c.

The pro sions of Specifications 3.0.3 and 3.0.4 ar not applicable.

l SURVEILLANCE EOUIREMENTS I

4.3.3.9 ach radioactive liquid effluent monitoring instrumentation chan I sna11 e demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHE, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequen c' s shown in Table 4.3-8.

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Table 3.3-12 (Continued)

ACTION STATEMENTS ACTION 31 - With the number of channels OPERABLE less than required by the is

{nimumChannelsOPERABLErequirement,effluentreleasesvia.

pathway may continue for up to 14 days provided that prior ini' iating a release:

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At least two independent samples are analyzed in. cordance a.

wit Specification 4.11.1.1.1, and b.

At leas.t two technically qualified members of ha facility.

staff ihgiependently verify the release rate calculations and discharge line valving.

Otherwise, su nd release of radioactive ef luents via this pathway.

ACTION 32-With the number of\\ channels OPERABLE Les than required by the ffluent releases via this MinimumChannelsOPEqABLErequirement, pathway may continue (or up to' 4 :.

analyzed for principai\\ gamma emitter and 1-131 at a lower limit L-OC of' detection as specifikd in Table.11-1:

a.

At least 'once per 12 urs w n the specific activity of the h

secondary coolant is greate tnan 0.01 microcurie / gram DOSE EQUIVALENT I-131, or

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.At least once per 24 h rs\\henthespecificac'tivityofthe secondary coolant is ss than or equal to 0.01 microcurie / gram COSE EQUIVALENT I-13.

ACTION 33-WiththenumberofchMnelsOPERABLElessthanrequiredby.the Minimum.-Channels OP ABLErequirement,\\effluentreleasesviathis pathway may contin for up to 30 days p ovided that prior to initiatir.g a rele se:

At least t o independent samples are an dyzed in accordance a.

with Spe fication 4.11.1.1.1, and N\\

b.

At le t two technically qualified members of the facility g

staf independently verify the release rate caipulations and d

harge line valving; nis Othe7 wise, suspend release of radioactive effluents via pa way.

ACTION 34 - ith the number of channels OPERABLE less than required by qe Minimum' Channels OPERABLE requirement, effluent releases via his pathway may continue for up to 30 aays provided the flow rate 1 estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

Puma performance curves generated in place may be used to estimate i

flow.

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RPtilSic TABLE 4.3-B-(Continued)-

N TABLE NOTATIONS The ANAltG CHANNEL OPERATIONAL. TEST.shall also demonstrate t) automatic (1) ~

isolation %f this pathway and control room alarm annuncia fn occur as-appropriate f any of the following conditions exists:

a.-

Instrument indicates measured levels above th larm/ Trip 5etpoint l.

(isolation and arm), or b.

Circuit failure (' alarm only), or c.

. Instrument indicate ownscale i ure (alarm only), or d.

Instrument' controls not in perate mode (alarm only),

s (2) The initial CHANNEL CALIBRATION haNbeperformedusingoneormoreof d solidhstandards certified by the the reference (gas or liquid p(N85) or usihg' standards that have been National Bureau of Standards /

obtainedfromsupplierstpetparticipateinmgasurementassuranceactivi-3 itsintendedrangeof(tandardsshallpermitchybratingthesystemover ties with NB5. These s f nergy, measurement range, And establish monitor response to a solid calibration source. For-subsequent CHANNEL CALIBRATION,

.NBS traceable stan6ard (gas, liquid, or solid) may ben sed; or a gas, liquid, or soljd source that has been calibrated by relit {ng it to equip-mentthatwaypreviously(within30 days)calibratedbythe-ame geometry and type o.f source standard traceable to NBS.

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(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of ye' lease. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months o' days on which continuous, periodic, or batch releases are made.

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09D CALLAWAy - UNIT 1 3/4 3-57

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REVISloy 3

INSTRUMENTATION ADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION L ITING CONDITION FOR OPERATION 3.3.3.1-The radioactive gaseous ef fluent monitoring instrumentation annels shown in abic 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoi s set to ensure tha the limits of Specifications 3.11.2.1 and 3.11.2.5 are t exceeded.

The Alarm /Tgd and adjusted in accordance with the methodology Setpoints of these channels meeting Specification 11.2.1 shall be determine parameters in the ODCM.

APPLICABILITY: A shown in Table 3.3-13.

ACTION:

a.

With a radioa tive geseous effluent. monitoring instrumentation channel Alarm / Trip Setpoint less conse/vative than required by the g

abovetspecificatiqn, immediately susp'end the release of radioactive gaseous effluents Inonitored by th affected channel, or declare the channel inoperable.

b.

With less than the minimum pumber of radioactive gaseous effluent monitoring instrumentati channels OPERABLE, take the ACTION shown

.in Table 3.3-13.

Rest e inoperable instrumentation to OPERABLE I

status wit.ein the tim spect ed in the ACTION, or explain in the 3'

next Semiannual Rad etive E luent Release Report, pursuant to

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Specification 6.9,

.7, why thi(s operability was not corrected d thin th?

.ne specified.

c.

The provisi s of Specifications 3.0.

and 3.0.4 are not applicable.

SURVEILLANCE RE IREMENTS 4.3.3.10 ) h radioactive gaseous effluent monitoring trumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK HANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TE T at the frequen-cies hown in Table 4.3-9.

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TABLE NOTATIONS.

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- Duri WASTE GAS HOLD UP SYSTEM operation.

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ACTION STATEMENTS b

ACTION 38 igh the number of channels OPERABLE less than required by e

Miniaum Channels OPERABLE requirement, the contents of the tank (s) may 6e released to the environment for up to 14 days pro ded that

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prior lo initiating the release:

a. 'At least two independent samples of the tank's c tents are

. analyze'd and b.

At least two technically qualified members o the facility

. staff indephdently verify the release rat calculations and dischargeva1\\elineup.

Otherwise,. suspend lease of radioactive e 'luents via this f

pathway.

ACTION 39 - With the number of channels OPERABLE le s than required by the Minimum Channels OPERABLE \\ requirement effluent releases via this pathway may continue provi' ed the f1 rate is estimated based on-d fan status and operating curves or ctual measurements at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

\\

ACTION 40 - With the. number of channels OPE BLE less than required by the.

}

Minimum Channels OPERABLE regt) rhment, effluent releases' via this pathwaymaycontinueforupp630'daysprovidedgrabsamplesare taken at least once per 12 Jiours arid these samples are analyzed forradioactivitywithin)4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 41 - With the number of chant)61s OPERABLE one less than required by the Minimum Channels 0 ERABLE requirement, PURGING of radioactive effluents via this p way may continue for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . With bath channels inoperable immediately suspend P' URGING of radioactive effluents via this athway.

j ACTION 42 - With the Outlet *ygen Monitor channel inoperable, operation of the system may ontinue provided grab samples are taken and analyzed s

at least once er 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . With both oxygen channels or both the inlet oxygen nd inlet hydrogen monitors inoperable, suspend oxygen supply to e recombiner.

Addition of waste gas th the system may g

continue ovided grab samples are taken and analyzed at least once per 4 ho rs during degassing operations and at least bnce per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during other operations.

\\

ACTION 43 - With he number of channels OPERABLE less than required by the Min' mum Channels OPERABLE requirement, effluent releases Qa the ected pathway may continue for up to 30 days provided samples a

re continuously collected with auxiliary sampling equipmentMs required in Table 4.11-2.

{

ACTION

- With tne number of channels OPERABLE one less than required by t'e f

Minimum Channels OPERABLE requirement, suspend oxygen supply to j

the recombiner.

AC ON 45 - Flow rate for this system shall be based on fan status and operating curves or actual measurements.

CALLAWAY - UNIT 1 3/4 3-71 Amendment No. 20

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TABLE 4.3-9 (Continued)

TABLE NOTATIONS

" At all mes.

- During WAS GAS HOLDUP SYSTEM operation.

(1) The ANALOG C NNEL OPERATIONAL TEST shall also demonstratefhat automatic isolation of t *s pathway and control room alarm annunciation occur as appropriate if a of the following conditions existst p

a.

Instrument in cates measured levels above the arm / Trip Setpoint (isolation and alarm); or

\\

b.

Circuit failure (ala ly), or

)

Oh c.

Instrument indicates a downscale failure (alarm only), or N

operate /

c,\\n mode (alarm only).

d.

Instrument controls not set i

-(2)

The ANALOG CHANNEL OPERATIONAL TEST'sQa also demonstrate that control f-room alarm annunciation occurs if any nf the following conditions exists:

/

Instrument indicates measured ieve\\

N)

Q ls\\above the Alarm Setpoint, or a.

b.

Circ'uit failure, or' l

J

')

c.

Instrument indicates ownscalefailure,o(

d.

Instrument controls et set in operate mode.

i (3) The initial CHANNEL CA BRATION shall be performed using one or more of liquid and solid) standards certl ied by the National NBS)orusingstandardsthathave(beenobtainedfrom the reference (gas o Bureau of Standards g

suppliers that par icipate in measurement assurance activi4ies with NBS.

Thesestandardspsallpermitcalibratingthesystemoveritsintendedrange of energy, meaperement range, and establish canitor response \\to a solid calibration source. For subsequent CHANNEL CALIBRATION, NBS t aceable str.ndard (gpl, liquid, or solid) may be used; or a gas, liquid, r solid source that' has been calibrated by relating it to equipment that as previousJf(within30 days)bythesamegeometryandtypeofsourc traceab e to NBS.

(4) The ANNEL CALIBRATION shall include th.e use of standard gas samples to aining a nominal:

One volume percent hydrogen, balance nitrogen, and b.

Four volume percent hydrogen, balance nitrogen.

CALLAWAY - UNIT 1 3/4 3-74

g -.

d RE

'j Stoy y

TABLE 4.3-9 (Continued)

TABLE NOTATIONS (Continued)

-(5) The C NEL CALIBRATION shall include the use of stan ard gas samples contain1 a nominal:

a.

One volwe percent oxygen, balance nitrogen and b.

Four volum p reent oxygen, balance nityogen.

(6) -The CHANNEL CALIBRATION shall include the/use of standard gas samples containing a nominal:

/

a.

10 ppm by volume oxy

, balance nitrogen, and

.l f

b.

80 ppm by volume oxygen,.alance nitrogen..

Ifflowrateisdeterminedby/exh pst fan status and fan performance (7)

Li

' curves, the following surveillance 's rations shall be performed at least once per 18 months:

/

6

/

~

a.

The specific vent flows by direct m urement, or l'

b.

-The differential pressure across tile e ust fan and vent flow established by the fan's " flow-AP" curve, or

/

}

The fan motor horsepower measured and vent f w established by the c.

fan's'" flow-horsepower" curve.

,/'

Go N

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CALLAWAY - UNIT 1 3/4 3-75

2NSERT AA' g

i.-

INSTRUMENTATION' F

WASTE _ GAS HOLDUP SYSTEM b.

, EXPLOSIVE GAS' MONITORING INSTR _UMENTATION LIMITING CONDITION FOR OPERATION 3.3'.3.10 _At least one hydrogen and both the inlet'and outlet oxygen explosive gas monitoring instrumentation channels for each WASTE' GAS HOLDUP SYSTEM recombiner shall be OPERABLE.with their ALARM / TRIP SETPOINTS set to ensure that the limits of Specification 3.11:.2.5 are not exceeded.

APPLICABILITY:

During WASTE GAS HOLDUP SYSTEM operation.

ACTION:

.a.

.With an outlet oxygen monitor channel inoperable, operation of the, system may continue provided: grab samples are taken'and analyzed at least once per-24 hours.

1 b.

' With both. oxygen or both_ hydrogen channels or both the inlet oxygen and inlet hydrogen monitor channelsLfor one recombiner inoperable, suspend oxygen supply to the recombiner.

Addition of waste gas to.the system may continue provided grab samples are taken and analyzed at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during' degassing operations and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during other operations, c.

The provisions of Specifications 3.0.3 and 3.0.4 i

are not applicable.

SURVEIL _ LANCE REQUIREMENTS 4.3.3.10 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERADLE by performance of:

a.

A CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

An ANALOG CHANNEL OPERATIONAL TEST at least once per 31 days, and c.

A CHANNEL CALIBRATION at lease once per 92 days I

with the use of standard gas samples containing a nominal:

1 1

l

1 INSERT AA continued INSTRUMENTATION'

. WASTE GAS HOLDUP SYSTEM

' EXPLOSIVE GAS MONITORING _ INSTRUMENTATION-SURVEILLANCE REQUIREMENTS CONTINUED L

1)'

One volume percent hydrogen, balance nitrogen l

and four volume percent hydrogen,. balance nitrogen for the hydrogen monitor, and l.~

2)

One volume percent oxygen, balance. nitrogen,

.and four volume percent oxygen, balance

nitrogen for the inlet oxygen monitor, and 3) 10 ppm by volume oxygen, balance nitrogen and 80 ppm by volume oxygen, balance nitrogen for the outlet oxygen monitor.

1

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I REVISIob; 3

.11 RADIOACTIVE EFFLUE U S y

1 LIQUID EFFLUENTS CONCEH1 10N LIMIf1NG COND 3.10N FOR OPERATION

3. l t.1.1 The concent 4 tion of radioactive material released in liquid effluents to UNRESTRICTED AREAS ('

Figure 5.1-4) sh611 be limited to the concentrations specified in 10 CFR Part

. Appendix B, T,able II, Column 2, for radionuclides ases. For dissolved or entrained ainednobleplimitedto2x104 other than dissolved or en shall b -

microcurie /ml noble gases, the concentrate total activity.

APPLICABILITY: At all times.

AC110N:

With the concentration of radioactive material released in liquid effluents to g

UNRESTRICTED AREAS exceeding the above li ts, immediately restore the concen-tration to within the abo /e limits.

~

Si!RVEILLANCE REQUIREMENTS f

m/

1 4.11.1.1.1 R ioactive liquid wastes shall be sampled a analyzed according to the sampi ng and analysis program of Table 4.11-1.

4.11.1.l e The results of t.he radioactivity analysis shall be sed in accordance j

f with the methodology and parameters in the ODCM to assure that t concentrations

{

at the/ point of release are maintained within the. limits of Speci ation 3.11 l.l.

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pp, Amendment No. 2 TABLE 4.11-1 RADIbACTIVELIOUIDWASTESAMPLINGAND-ANALYSISPROGRAM

,.j:

"~

LOWER LIMIT MINIMUM OF DETECT j LIQUID RE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLDP l

~'

TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/ml)

1. Batch Waste P

P Release Ea Batch Each.Baten-Principal Gamma Sx 0 Tanks (2)

Emitters (3) j I

[

-6 I-131 1x10

\\

a. Waste r

Monitor Dissolved a /.-

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One Batch /M Entrained asas (Gamma itters)

b. Secondary Liquid

-5 Wasta P

M H-1x10 Monitor Each Batch Composite {

,, 7 Tank ss Alpha 1x10

w. '_'T c Discharge P

Q Sr-k, Sr-90 5x10'8 g,[.

4)

Monitor Each Batch Composi'

-6 Fe-55\\

C' Tank 1x10

\\

7

2. Continuous W

Principal G ia 5x10 Releases (5)

Daily (6)

,,p,,$g,(4) hitters (3)

Gran Sample

/

-6 I-131

\\ 1x10

\\

Steam Generator N

.c Blowdown M

M Dissolved and 1210 "

Gr Sample Entrained Gases (Gamma Emitters) 0h M

H-3 1x10 Daily (.6)

Compos'ite(4) 7 Grab' Sample Gross. Alpha 1x10

~8 Q

Sr-89, Sr-90 5x10

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Daily (6)

Composite (4)

N y

Grab Sample Fe-55 1x10 3/4 11-2 CALLAWAY - UNIT 1

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REVISlon 1

t-l AHLI' 4.11-1 (Continued)

TABLE NOTATIONS (1)The LD is defined..for purposes of these specifications, as the s llest L

conc tration of radioactive material in a sample that will yield net l

count, above system background, that will be detected with 95% p obability.

with on' 5% probability of falsely concluding that a blank ob rvation

. represent a "real" signal.

'For a parti lar measurement system, wh4ch may include rad chemical separation:

4.66 s 0

h LLD =

E V *\\.22'x 108 Y

exp (-Mt)

Where:

LLD = the "a prior 1' lower limit of detect on (microcuries per unit mass or volume),

the standard devia ion of the bac round counting rate or of s :

bthe counting rate of a bl k sample appropriate (counts per minute),

4.

s per disintegration),

E = the counting efficiency ( u g j...

~s V = the sample size (units of a or volume),

2.22 x 106.= the number of disinteg tions per minute per microcurie, Y = the fractional rad' chemical yiel, when applicable, A = the radioactive ecay constant for th particular radionuclides (s 3), and i

at = the elaps time between the midpoint of ample collection and the time f counting (s).

Typical v ues of E, V, Y, and at should be used the calculation, it shuuld recognized that the LLD is defined as an a_ p ori (before Lhe fact limit representing the capability of a measuremen system and not as n a posteriori (after the fact) limit for a particula measurement.

(2)A b ch release is the discharge of liquid wastes of a discrete olume.

k Pr ur to sampling for analyses, each batch shall be isolated, and wn thoroughly mixed by a method described in the ODCM to assure representative sampling.

6 CALLOWAY - UNIT 1 3/4'11-3

....a.

............ ; u.a..w:... w

.. ~., -..

a.- x.=...-.... L r. a...a._v.u.c.w.;.

REVISION TABLE 4.11-1 (Continued)

Q

'b' TABLE NOTATIONS (Continued)

(3)The prin algammaemittersforwhichtheLLDspecificatjenapplies.

Include the ollowing radionuclides: Mn-54,Fe-59,Co-J5,Co-60,In-65, Mo-99, Cs-134 s-137, Ce-141, and Ce-144. -This list <loes not mean that j

only these nuc1 are to be considered. Other gansna peaks that are identifiable, toge with those of the above nuc11 des, shall also be analyzed and reporte the Semiannual Radioactive Effluent Release Report pursuant to Specificati g6.9.1.7, in the format outlined in Regulatory Guide 1.21, Appendix B, Rev sion 1, June 1974.

(4)A corrposite sample is one in w h th antity of liquid sampled is proportional to the quantity of NJid waste discharged and in which the J

method of sampling employed resu tt h a specimen that is representative of the. liquids released. Pri o anaTy is, all samples taken for the composite shall be thoroughl ixed,in or for the composite samples to be representative of th-ffluent release.

(5)A continuous release i / he discharge of liquid w tes of a nondiscrete t

volume, e.g., from olume of a system that has an ' ut flow during the continuous releas (6) Samples shall e taken at the initiation of effluent flow and t least once per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter while the release is occurring. To be resenta-

@h'

.tive of

-e liquid effluent, the sample volume shall be proportion to the efflue stream discharge volume. The ratio of sample volume to effl t

disc rge volume shall be maintained constant for all samples,taken for th composite sample.

w CALLAWAY - UNIT 1 3/4 11-4

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1 i

REVISION 3

D10 ACTIVE ~ EFFLUENTS

~

',}' -

.,j LIMITING ONDITION FOR OPERATION I

3.11.1.2 The se or dose commitment to a MEMBER OF THE PUBLIC fr radioactive materials in liq 'd ef fluents released, from each unit, to UNREST CTED AREAS (see' Figure 5.1-4) hall be limited:

i a.

During any alendar quarter to less than or equal 1.5 mrems to the whole bo.and to less than or equal to 5 mre s to any organ, b.

During any calen r year to less than or equ to 3 mrems to the whole body and to ess than or equal to 10 ems to any organ.

APPLICABILITY: At all times.

O4 AC110N:

a.

With the cair.~ated dose om the r ease of radioactive materials in liquid ef

.ents exceedi g ar.y f the above limits, prepare and submit t. the Commission wit n 30 days, pursuant to Specifica-tion 6.9.2, a Special Report t identifies the caus,e(s) for exceeding

,l-the limit (s) and defines the rective actions that have been taken d

Qf to reduce the releases and t e oposed corrective actions to be taken D

to assure that subsequent r less will be in compliance with the above limits. This Speci Report shall also include:

(1) the results of radiological nalyses o the drinking water source, and h

(2) the radiological i act on finis d drinking water supplies with regard to the require nts of 40 CFR rt 141, Clean Drinking g

Water Act.*

K b.

The provisions of specifications 3.0.3 an 3.0.4 are not applicable.

Qs SURVEILLANCE REQUIREME S 4.11.1.? Cumul ive dose contributions from liquid effluents for the current calentlar quart r and the current calendar year shall be determ.ed in accordance with the met dology and parameters in the ODCM at least once pe 31 days.

9 he equirchshtfoi ACTION a.(1) and (2) are applicaDie only if drinki water ply is taken from the receiving water body within 3 miles of the plan

.t scharge.

In the case of river-sited plants this is 3 miles downstream ly.

CALLAWAY - UNIT 1 3/4 11-5

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' ' * 'i LIQU19 RADWASTE TREATMENT SYSTEM di-LIMITING NDITION FOR OPERATION l

l 3.11.1.3 lhe L uld Radwaste Treatment System shall be OPERABLE and a repriate portions of.the sygtem shall be used to reduce releases of radioacti' ty when l

the projected duses due to the liquid effluent, from each unit, to RESTRICTED AREAS (see Figure 5. -4) would exceed 0.06 mrem to the whole body r 0.2 mrem to

}_

any organ in a 31 day eriod.

h APPLICABilliY: At all t es, AC110N:

a.

With radioactive li id waste being discharg without treatment and in excess of the abov glimits and'any porti of the Liquid Radwaste Treatment System not irt peration, prepare and submit to the Commission within 30 days, pursuan o Specification 6.9.2, a Special Report that includes the following in rmation:

1.

Explanation of why liquid radwp te was being discharged without b.

G treatment, identification f ny inoperable equipment or subsystems, and the reason r the inoperability, C h.

\\

2.

Action (s)- taken to resto the'inopera'ble equipment to OPERABLE Y.f.~

status, and 3.

Summary description f action (s) then to prevent a recurrence.

h.

-the provisions of Spe fications 3.0.3 and

.0.4 are not applicable.

%URVLlLLANCE REQUIREMENTS I

4.11.l.3.1 Du es du to liquid releases from each unit to UNRES ICTED AREAS j

.h.ill be prujected t least once per 31 days in accordance with t. methodology

{

l and parameters i the 00CM when Liquid Radwaste Treatment Systems a not being tully utilized.

4.11.1.3.2 he installed Liquid Radwaste Treatment System shall be cons ered l

OPERABLE meeting Speci fications 3.11.1.1 and 3.11.1.2.

i 1

,/

CAtLAWAY - UNIT 1 3/4 11-6 i

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ADI0 ACTIVE! EFFLUENTS 3

.11.2 GASEOUS EFFLUENTS Q

005 ATE LIMITING ONDITION FOR OPERATION 3.11.2.1 The se rate due to radioactive materials re ased in gaseous effluents from e site to areas at and beyond the SIT BOUNDARY (see Figure 5.1-3) shall be 'mited to the following:

a.

For noble ases:

Less than or. equal toj600 mrems/yr to the whole body and 1 s than or equal to 3000 mr ms/yr to the skin, and b.

For Iodine and 133, for tritiu. and for all radionuclides h

in particulate orm with half-liv greater than 8 days:

Less than or equal to 150 mrems/yr to any organ.

0 APPLICABILITY: At all times.

ACTION:

Y With the dose rate (s) exceeding t. above limits, immediately rest. ore the release rate to within the above 1 it(s).

,p...

gW 0 Q

SURVEILLANCE REQUIREMENTS i

4 4.11.2.1.1 Thedoserpeduetonoblegasesingaseouseffluentsshallbe h

determined to be with n the above limits in a ordance with the methodology and parameters in t ODCM.

4.11.2.1.2 The' e rate due to Iodine-131 and 13-tritium,abdall radionuclides i articulate form with half-lives g ter than 8 days in gaseous effluents shal e determined to be within the above 'mits in accordance with the methodolo and parameters in the ODCM by obtaining representative samples and performi g analyses in accordance with the sampling a analysis program specified i Table 4.11-2.

\\

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1 1

.TABtF 4.11-2 (Continued)

' f '

.\\

,' ;~yI TABLE NOTATIONS u.

(1)th. LLD is defined, for purposes of these specifications, as the snallest conc tration of radioactive material in' a sample that will yield a net -

count, bove system background, that will be detected with 95% probabili with oni 5% probability of falsely concluding that a blank observatio l

represent a "real" signal.

For a partic ar measurement' system, which may include radiochemi el separation:

4.66 s b

LLD =

E V

2}R2 x 108 - Y exp (-Mt)

Where:

~ icroCuries per unit LLD = the "a priori" 1 wer limit of detection m

mass or volume),

of the backgr /und counting rate or.of s = the standard deviatio' thecountingrateofabla%nk b

ample as ppropriate (counts per minute),

m E = the counting efficiency (coun per disintegration),

9M V = ~ the' sample size (units of ss ume),

2.22 x 106 = the number of disintegrations per minute per microcurie, j

Y = the fractional radi emical yield, when plicable.

A = the radioactive decay constant for the particular radionuclides g

(s 8), and-J at = the elapsep time between the midpoint of sample llection and the time of comnting (s).

Typical va es of E, V, Y, and at should be used in the ca lation.

i a

It shoJId'b recognized that the LLD is defined as an a_ priori (bef t.he fact) imit representing the capability of a measurement system a not as a posteriori (after the fact) limit for a particular measurem t,

Y

~

G CALiAWAY - UN!T I 3/4 11-10

_11 5 r-Y.

.?- '&

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.g p

REVISloy 3 TAFLE 4.11-2 (Continued)

},4 TABLE NOTATIONS (Continued)

('

he principal gamma emitters for which the LLD specification appli i lude the following radionuclides: Kr-87 Kr-88, Xe-133, Xe-3m, Xe-135, and Xe-138 in noble gas releases and Mn-54, F 9,

1

~ ~ ~

Co-58, Co-60, In-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141, a Ce-144 in

~

lodine d particulate releases. This list does.not mean tbit only these nuclides e to be considered. Other gamma peaks that ar identifiable, together wi those of the above nuclides, shall also b nalyzed and-reported in t Semiannual Radioactive Ef fluent Releasp Report pursuant to $pecificatio 6.9.1.7, in the-format outlined in Rdgulatory Guide 1.21 Appendix B. Revis n 1, June 1974 (3) Sampling and analysis hall also be performed fp lowing shutdown, startup, or a IHERMAL POWER chan e exceeding 15% of RA D THERMAL POWER within 1 huur p+riod.

(4) Tritium grab samples shall b taken and ahalyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

[

when the refueling canal is fl ded.

(5) Tritium. grab samples shall be take.<and analyzed at least once per 7 days from the ventilation exhaust from th spent fuel pool area, whenever spent s

fuelisinthespentfuelpool./ Grab mples need to be taken only when spent fuel'is in the spent fuel pool.

pg

/

-(6)The ratio.oflthe sample flow rate'to the sam d stream flow rate shall

>+

V be known f or the time perj6d covered by each d e-or dose rate calculation made in accordance withw$ specifications 3.11.2.1,

.11.2.2, and 3.11.2.3.

/

(/) Sample < shall be changed at least once per 7 days an4 analyses.shall be completed within 4,B' hours af ter changing, or af ter rem val from sampler.

For unit vent, sampling shall also be performed at leas -once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months lor at least STARTUP or T RMAL POWER change exceedingly [/daysfollowingeachshutdown, of RATED THERMAL POWER withir) a 1-hour period nd analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples ollected for 24 ho.urs are analyzed, the corresponding LLDs may be increa d by a factor of 10.

This requirement does not apply if:

(1) analysis

.ows that tlie DOSE EQUIVALENT I-131 concentration in the reactor coolant ~ as not fncreased more than a factor of 3, and (2) the noble gas monitor shods that effluent activity has not increased more-than a factor of 3..

A (8)bontinuous sampling of the spent fuel building exhaust needs to be perform

/ only when spent fuel is in the spent fuel pool.

.c d

kD h

CAILAWAY - UNIT 1 3/4 11-11

-_-_:__WL*'_________

. ::.::. W+.2h,9 4.,

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+

./,d!3!'!E REVISION 1

~

L q

R 10AC11VE LIFLUFNih l,

,A 1:

DOSE NOBLE CASES

/

.;;Tgf LIMITING CO ITION FOR OPERATION il 3.11.2.2 The air se due to noble gases released in gaseous effluents, from each unit, to areas'et and beyond the SITE BOUNDARY (see Figure 5.1-3) shall,

~

L be limited to the follh ing:

/

k

/

a.

During any calenu.ar quarter: Less than' or equal to 5 mrads for gamma radiation ann less than or. equal to 10arads for beta radiation, and

/

b.

During any calendar year Less than or' equal to 10 mracs for gamma radiation and less than o qual to 20 mrads for beta radiation.

/

APPLICABILITY: At all times.

/

~

9 ACTION:

/

/r a-With the calculated air dose from rad tactive noble gases in gaseous ef fluents-exceeding any,4f the above linh(o 4' specification 6.9.2, a s, prepare and ' submit to the Commission within 30 days, pursuant t Special Report that)$entifies the cause(s) for exceeding the limit (s) and defines the-coprirctive actions that have bh n taken to reduce

-l;j.g the releases and the proposed corrective actionsh o be. taken to assure

't -

f that subsequenyreleases will be in compliance with the above limits.

h.

The provisipo of Specifications 3.0.3 and 3.0.4 are applicable.

\\

SURVEILLANCE REQUIREMENTS

4. l!.2.2jtumulative dose contributions for the current calendar quarter and currentjtalendar year for noble gases shall be determined in accordance with the thodology and parameters in the ODCM at least once per 31 days.

l c

co q

8h

_3 CAIIAWAY - ltNI1 1 3/4 11-12

, = =. -

g.:.:. :. ~&~.e.x' ".g., s - ~ ~7" J&*- **,5. y~;

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REVISION 1

=-

i RAD 10ACilVE EFFLUENIS 1

'.;.I ~

E'-

10 DINE-131 AND 133, IRITlUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM

,p LIMIT!

CONDITION FOR OPERATION I

1 J 3.11.2.3 lh dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133,pritium,

.and all radioritplides in particulate form with half-lives greater than 8 days in gaseous effl nts released, from each unit, to areas at and be phd the SITE BOUNDARY (see Fig e 5.1-3) shall be limited to the following:-

During any alendar quarter: Less than or equal to 7.5 mrems to any a.

organ, and b.

During any cale at year: Less than or equal 'o 15 mrems to.any organ.

~

APPLICABILITY: At all times.

ACTION:

With the calculeted dose from thy release of Iodine-131 and 133, a,

tritium,andradionuclidesh rticulate form with half-lives greater than 8 days,.in gaseous eff ts exceeding any of the above limits, prepare and submit to the M ion within 30 days,' pursuant to Speci-Q~

lication 6.9.2, a Specia Report'that ide'ntifies the cause(s) for

'... ; ; 7

exceedi'ng the limits a defines the, corrective actions that have been

taken-to reduce ^the easesandthehoposedcorrectiveactionstobe taken to assure th subsequent releases,will be in compliance with the above limits.

.4 are not applicable.

of Specifications 3.0.3 and 3}q\\

b.-

The provision SURVEILLANCE REOU MENTS

\\

s 4.11.2.3-mulative dose contributions for the current calenda qbarterand current lendar year for lodine-131 and 133, tritium, and radionuclides in partic ateformwithhalf-livesgreaterthan8daysshallbedetermind(in acco ante with the methodology and parameters in the ODCM at least once'per 31 ays.

()

N V

9 0

e w\\9 &

j U

i CALLAWAY - UNil 1 3/4 11-13

/

- m m,

.c.

-n m --

' L.:::.., w r ;.

.:: - ~:.

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...'Lh;;ik C%&_y. ;m~ ; m' T*.::ib. cJ : i.X.i.:.'xG3 :' :. A':.hx.+.LR i%; n cda..

L.a 1

l 1

!,o t ate 'sp REVISIoy.1 R

0 ACTIVE EFFLUENTS

$)-

GAS S RA0 WASTE TREATMENT.iYSTEM L:Jy

~

l-LIMITIN CONDITION FOR OPERATION l

l 3.11.2.4 The ENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HD DUP SYSTEM shall be PERABLE and appropriate perions of these systems shall be fi 31 days easesofradioactivitywhentheprojecteddoses)6eyondthe used to reduce r uent releases, from each unit, to areas at an@

due to gaseous ef SITE BOUNDARY (see gure 5.1-3) would exceed:

a.

0.2 mrad to ir from gamn.a radiation, or b.

0.4 mrad to air-from beta radiation, or c.

0.3 mrem to any or n of a MEMSER OF THE P98LIC.

APPLICABILITY: At all times.

(

ACTION:

i a.

With radioactive gaseous wa te b,rg discharged without treatment and in excess of the above 1 i s, prepare and submit to the Commission within 30 days, pu ant to Specification 6.9.2, a 5pecial Report that include. the following information:

,5 i

~

L',

1.

Identification of inoperab equipment or' subsystems, and l

the reason for th noperabilit I

r 2.

Action (s) take o restore the inop able equipment to OPERABLE status, and 3.

Summary des iption of action (s) taken t prevent a recurrence.

b.

The provisions of ' Specifications 3.0.3 gnd 3.0.4 re not applicable.

/

SURVEILLANCE REOUIRE'MENTS s

4.11.2.4.1 oses due to gaseous releases from each unit to areas a nd beyond th ITE BOUNDARY shall be projected at least once per 31 days 'n accnrdan with the methodology and parameters in the ODCM when Gaseous adwaste Trea t.m t systems are not being fully utilized.

4.1.7.4.7 The installed VENTILATION EXHAUST TREATMENT SYSTEM and the VAST G.Il0lDtiP %YSTEMS shall be considered OPERABEE by meeting Specifications 3.1

.1 nil 3.11.?.7 or 3.11.2.3.

h h.m.

CAIIAWAY - UNIT 1 3/4 11-14

w h*.

wp#/9

==

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Y SiON I

DI0 ACTIVE EFFLUENTS

^

3/

1.3 SOLID RADIOACTIVE WASTES

~

LIMIThGCONDITIONFOROPERATION

-3.11.3 R ioactive wastes shall be solidified or dewatered in accordance th the PROCESS ONTROL PROGRAM to meet shipping and transportation requirements during transi-and disposal site requirements when received at the disposal

[,/

site.

APPLICABILITY: A.all times.

ACTION:

[

With SOLIDI ICATION or dewatering not meeting dispos,a1 site and a.

shipping an transportation requirements, suspend shipment of the inadequately rocessed wastes and correct the PROCESS CONTROL PROGRAM, the procedure and/or the Solid Waste System asphecessary to prevent

,/

f recurrence.

b.

With SOLIDIFIC ION or dewatering not performid in accordance with thePROCESSCON(0LPROGRAM,testtheimpyoperlyprocessedwastein each container togensure that it meets bprial ground and shipping requirements and ke appropriate administrative action to prevent f

recurrence.

The provisions of Spe ifications 3.'0.3 and 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.11.3 501 EDIFICATION of at least o representative test specimen from at

(..f least every tenth batch of each type'o wet radioactive wastes (e.g., filter sludges, spent resins, evaporator pettom boric acid solutions and sodium sulfatesalutions)shallbeverifjedina ordance with the PROCESS CONTROL PROGRAM:

/

ofthebatchunderte/ailstoveri(SOLIDIFICATION,theSOLIDIFICATION If any test specimen a.

st shall be susp ded until such time as additional test specimens canjbe obtained, altern ve SOLIDIFICATION parameters can be determined /in accordance with th ROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFIC l0N.

SOLIDIFICATION of the batch may,then be resumed using the al{ rnative SOLIDIFICATION parameters dytermined by the PROCESS CONTROL PROGRAM; J

b.

If the initial test specimen from a batch of w te fails to verify f

I SOLIDIFICATION, the PROCESS CONTROL PROGRAM sha provide for the collecticIn and testing of representative test spe imens from each consecutive batch of the same type of wet waste u il at least three consep6tive initial test specimens demonstrate 50L IFICATION. The PROCTSS CONTROL PROGRAM shall be modified as require', as provided in specification 6.13, to assure SOLIDIFICATION of su sequent batches o/ waste;and c.

' ith the installed equipment incapable of meeting Speci ' cation 3.11.3 or declared out-of-service, restore the equipment o operable status or provide for contract capability to process waste as I

necessary to satisfy all applicable transportation and disp al f

requirements.

jfCALLAWAY - UNIT 1 3/4 11-17

/

[

._ a.e.w;5eMPp.{ 7.y ^.'

q.5

a;.az.cc.m.7 3. y;.$, p: :.,:=x.p" m m,.3

y: v..u w

m.:. ;.:... a.c:u-:..:... :. ;-

I REVISION 1

j

.. o..,.

010 ACTIVE' EFFLUENTS

'3

.4 TOTAL DOSE

.M

~

h 'l' l

[ LIMITING CONDITION FOR OPERATION

/

x

..; C 3.11.4. The annu

(. calendar year) dose or dose commitment to any MEMBER OF 3

E THE.PUBLIC due to Nieases of radioactivity and to radiation from urphium fuel I

q T " cycle sources shall h limited to less than or equal to 25 mrsans to/the whole J

l

~ m body or any organ, exhept the thyroid, which shall be limited to ss than or l

. equal to 75 mrems.

APPLI(' ABILITY: At all imes.

M M

' ACTION:

Cj k

a.

With the calcul ted doses from the release of dioactive materials gh,1 in liquid.or gas ous effluents exceeding twi the limits of Specification 3.1. 1.2a., 3.11.1.2b., 3.11, 2a., 3.11.2.2b.,

W 3.11.2.3a., or 3.

2.3b., calculations sh Id be made including h

direct radiation co ributions from the

.its and from outside storage tanks to determine wrie her the above 1 ts of Specification 3.11.4 have been exceeded. I such is the c

', prepare and submit to the

~

Commission within 30 da s, pursuant Specification 6.9.2, a Special Report that defines the correctiv adtion to be taken to reduce sub-sequent releases to pre nt recu /nce of exceeding the above limits and includes the schedule - r leving conformance with the above D

[j limits. This Special Report s defined in 10 CFR 20.405c, shall include an analysis that es sa' anium.. the radiation exposure (dose) to a T

MEMBER OF THE PUBLIC from el cycle sources, including all effluent pathways and di et radiati for the calendar year that includes the release (s covered by thi report. It shall also describe levels of ra at. ion and concent 'tions of radioactive material involved, a the cause of the e sure levels or concentra-j tions.

If the esti ted dose (s) exceeds th gabove limits, and if the release condition sulting in violation of 4B CFR Part 190 has not already been corr ted, the Special Report shah include a request for a variance accordance with the provisions' f 40 CFR Part 190.

Submittal of t report is considered a timely rei$ west, and a variance is granted u. il staff action on the request is co lete.

b.

The provi ons of Specifications 3.0.3 and 3.0.4 are t applicable.

,$_U_RVEILLANCE REO EMENTS 4.11.4.1 C ulative dose contributions from liquid and gaseous eff1 ts

5. hall be d. ermined in accordance with Specifications 4.11.1.2, 4.11.2.2 and 4.ll.2.3 and in accurdance with the methodology and parameters in the O M.

4.11.4 Cumulative dose contributions from direct radiation from the units

.ind om radwaste storage tanks shall be determined in accordance with the I

me.odology and parameters in the ODCM. This requirement is applicable only ur er conditions set forth in ACTION a. of Specification 3.11.4 CALLAWAY - UNIT 1 3/4 11-18 k

m,.

.c.~ g as

-....s.,. ; ;...wg,.....,

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y

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l. -

3 REVISIONy N'

f/--12 RAll!010GICAL I. ENVIRONMENTAL MONIl0 RING

Mc N

3/4.12.1 MONITORING PROGRAM r

)

LIMITING CONDITION FOR OPERATION k

4 3.12.1 The Radiological Environmental Monitoring Program shall be conduc. d

[

as specified in\\ able 3.12-1.

(/

APPLICABILITY:

At' ell times.

'\\

\\

~

J ACTION:

With the Rad q,Jogical Environmental Monitoring Program t being ogo O

a.

conducted as specified in Table 3.12-1, prepare and supmit to the N

Commission, in tie Annual Radiological Environmental perating Report t

[

required by Specification 6.9.1.6, a description of he reasons for not conducting the p{Aogram as required and the plap for preventing h

a recurrence.

b.

h th the level of rad oactivity as the result o plant effluents in an environmental sampling medium at a specifit location exceeding the reporting levels of Tab,le 3.12-2 when avpr; aged over any calendar quarter, prepare and submit \\to the Commissiin within 30 days, pursuant to Specification 6.9g2, a Specia)/ eport that identifies R

the cause(s) for exceeding theglimit(s) gnd defines the corrective actions to be taken to reduce r&dioact'4e effluents so that the i,,.

yj,

. potential annual dose

to a MEMB&R OF.HE PUBLIC is less than the

..Q9 calendar year limits of Specificat s 3.11.1.2, 3.11.2.2, or 3.11.2.3.

When more than one of e radionuclides in Table 3.12-2 are detected in the sampling med m,%dhis report shall be submitted if:

concentration (1) conce ration (2)

+ * * * > 1. 0 reporting level (1) reporting level (2)

When radionuclides other an those in Table 3.12-2 are detected and are the result of plant (fluents, this repo,r$ shall be submitted if the potential annual d ~e* to A MEMBER OF THE KJBLIC from all radio-nuclides is equal to r greater than the calendag year limits of Speci-fications 3.11.1.2

.11.2.2 or 3.11.2.3.

This rbport is not required if the measured i 1 of radioactivity was not the*tesult of plant Ipallbereported and described jf,ge, in such an event, the condition effluents: howevt the Annual Radiological Environmental perating Report, i

required by Specification 6.9.1.6.

c.

With milk of fresh leafy vegetable samples unavailable fr one or more of, e sample locations required by Table 3.12-1, iden fy specift locations for obtaining replacement samples and add hem withip 30 days to the Radiological Environmental Monitoring ProyramgivenintheODCM.** The specific locations from which amples

The met 'dology and parameters used to estimate the potential annual dose a MEM OF THE PUBLIC shall be indicated in this report.

- Ex.uding short term or temporary unavailability.

1 ALLAWAY - UNIT 1 3/4 12-1

)

i o.. '

)

~

7'i~..: f t:y w::. -,i,; ~ _ I,f f.]I -

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D:;^,.f:7:t..Ltbi" KG.; g(;[L;? * '*w ' ~ ~' '% ;Y"

,'. w :; i: ' p ult i L. :-

.:.1. :

1.' Y. n 'a:.:..:

f.:3.c ;::M.R:nL

..'l REVISjog t

}

OGICAL.4NVIRONMENTALMONiiORING RAD

'1tikli!

NDITION FOR OPERATION

. 3..

x ACTION (Contin

),

were unavai le may then be deleted from onitoring program.

fication 6.14, submit i e next Semiannual Radio-Pursuant to Spec {H ase Report docum ion for a change in the active Effluent R d table for the 00CM reflecting ODCM, including a r d figure (s) information identifying the the new location (s) wi upporting cause of the unavailabili of samples and justifying the selection of new location (s) for obtai g samples.

d.

The provisions of Specifications. 3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMEN

/

4.12.1 Thefditiological environmental monitoring samples sha e collected

~-

pursuant to Table 3.12-1 from the specific locations given in th ble and figure ( *in the ODCM, and shall be analyzed pursuant to the requir ts of Tabl

.12-1 and the detection capabilities required by Table 4.12-1.

1 uQ ch S

v t

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I REVI8

/ON TABLE 3.12-1 (Continued)

I 2

n i

.Y TABLE NOTATIONS (1) ecific parameters of distar.:e and direction sector from the centep ine oneunit,andadditionaldescriptionwherepertinent,shallbefrovided ofor achandeverysamplelocationinTable3.12-1inatableanpfigure(s) in tha ODCM. Deviations are permitted from the required sampli,ng schedule ifspehmensareunobtainableduetohazardousconditions, seasonal unavailab(lity,malfunctionofautomaticsamplingaquipment,/andother legitimate" easons.

If specimens are unobtainable due to r,dmpling equip-ment malfun on, every effort shall be made to complete p'orrective action prior to the ad of the next sampling period. All deviations from the sampling scheduh shall be documented in the Annual Ra#iological Environ-mental Operating teport pursuant to Specification 6.9/1.6.

It is recog-

- p nized that, at tim'ef, it may not be possible or pra ficable to continue to obtain samples of the media of choice at the most esired location or y

time.

In these instahces suitable specific alter ative media and loca-tionsmaybechosenfohtheparticularpathwayj question and approprit.te substitutions made withi'n 30 days in the Radiologien1 Environmental

\\0 MonitoringProgramgivenktheODCM. Pursupnt to Specification 6.14, W

submit in the next Semiannua) Radioactive fluent Release Report documen-tation for a change in the 00CM including revised figure (s) and table for the ODCM reflecting the ne'w locationf ) with supporting information identifying the cause of the unAyailabjiity of samples for that pathway and justifying the selection of the pew location (s) for obtaining samples.

5, (2) One or more instruments, such as pressurized ion chamber, for measuring s

(D..O and recording dose rate continuously may be used in place of, or in addition to, integrating dosimet'ers. Fqr the purposes of this table, a thermoluminescent dosimeter (Jf.D) is considered to be one phosphor; two s

or more phosphors in a packet are considefed as two or more dosimeters.

Film badges shall not be ysbd as dosimeters \\for measuring direct radia-tion. The 40 stations 1 The number of direct radiationmonitoringsa/notanabsolutenumber.tions may be reduced a'ccording to geo limitations; e.g., a n ocean site, some sectohg will be over water so that the number of imeters may be reduced accordingly. The frequency of analysis or read 6,ut for TLD systems will depend \\upon the characteristics of the specific f stem used and should be selected to obtain optimum dose f

information with minimal fading.

\\

(3)ThepurpuseAfthissampleistoobtainbackgroundinfo\\

/

rmation.

If it is not pract'ial to establish control locations in accordanceswith the distanc and wind direction criteria, other sites that prov3de valid backg 'and data may be substituted.

(4) Ai orne particulate sample filters shall be analyzed for gross beta inactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon Agd r

hurun dauqhter decay. If gross beta activity in air particulate SRmples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis, shall be performed on the individual samples, t

\\N s

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TABLE 3.12-1 (Continued) s TABLE NOTATIONS (Continued)

A

'b:)

,w/

(5) Gamma isotopic analysis means the identification an.

uantification of gamma'h mitting radionuclides that may be attribut e to the effluents from th N acility.

Nam stance beyond significant influence of the'ple" shall be taken at a (6) The."upstr dQcharge. The " downs eam" sample shall-be taken in an area beyond but nearNthe mixing zone.

(7) In this program composite plej liquots shall be collected at time intervals that are very shorMe.g., hourly) relative to the compositing period (e.g., monthly) in o. der'to assure obtaining a representative sample.

(8) Groundwater samples y all be taken when ttis source is tapped for drinking or irrigation purp tes in areas where the hydraulic gradient or recharge properties are 1 table for contamination.

(9) The dose sh 11 be calculated for the maximum organ a age group, using the metho logy and parameters in the ODCli.

(10) If.h vest occurs more than once a year, sampling shall be per, formed du ng each discrete harvest. If harvest occurs continuously,'sempling all be monthly. Attention shall be paid to including samples o uberous and root food products.

$y.,h.

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lABLE 4.12-1 (Continued)

TABLE NOTATIONS

. list does not mean that only these nuclides are to be considerep.

(1)iTh4 peaks that are identifiable, together with those of the abovp/

ogical Oth nucli. s, shall also be analyzed and reported in the Annual Radi Environmental Operating Report pursuant to Specification 6.9.1.

(2). Required detection capabilities for thermoluminescent dosime ers used he recommenda-for environmental measurements shall be in accordance with tions of RegdTatory Guide 4.13, Revision 1, July 1977.

, 'for purposes of these specificatiphs, as the smallest (3) The LLD is' defi concentration of r'adioactive material in a sample t%t will yield a net

' count, above system' background, that will be deteeped with 95% probability t a blank observation with only 5% probability of falsely concluding t represents a "real" sig~nal.\\

include radiochemical For a particular measurement system, which m separation:

4.66 s LLD =

IA$t) s E

V - 2.22 Y - exp

\\

l h

Where:

Yb@M imit ofydetection (picoCuries per unit

\\

LLD = the "a priori'" lower mass or volume),

b = the standard devi tion of the background counting rate or of s

g a blank sample as appropriate (counts per t.he-counting rate o

' minute),

E = the countin efficiency (counts per disintegration),

N size (units of mass or volume),

V = the samp number of disintegrations per minuto pergpicoCurie, 2.22 = th

\\

fractional radiochemical yield, when applicable, Y=t s

A - the radioactive decay constant for the particular radionuclides

\\

8 ), and

\\

at = the elapsed time between se.mple. collection, or end of the sample collection period, and time of counting (s).

Typical values of E, v. Y, and at should be used in the calculation.

s u

3/4 12-11 CALLAWAY - UNIT 1-

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TABLE 4.12-1 (Continued)

W

..~..

o/

TABLE NOTATIONS (Continued)

It should be reco. Qed that the LLD is ined as an a_ priori (before the fact) limit reprebt ty of a measurement system ar.d not as an a posterior'i'pting the cap [atd

{n ter the t) limit for a particular measurement.

Analyses shall be performe(5Qnch a manner that the stated LLDs will be achieved under' routine condi s.

Occasionally background fluctuations, unavoidable small sample zes,'theq resence of interfering nuclides, or other uncontrollable - cumstances'may render these LLDs unachievable.

In such cases, the ntributing factors qh,all be identified and described in the Annual R ological Environmental Op'e. ating Report pursuant to

~ Specification

.9.1.6.

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(4) LLD for inking water samples. For surface water sampi.gs, the LLD of gamma sotopic. analysis may be used.

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3 12.2 LAND USE CENSUS q

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1 3.12.2 A Land Use Census shall be' conducted and shall identify withi.

a

. distance of 8 (5 miles) the location in each of the 16 meteorological sectors of.the arest milk animal, the nearest residence and the, nearest garden

of greater than 50 m (500 ftz) producing broad leaf vegetation.

2

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APPLICABILITY: At a 1 times.

I ACTION:

With a Land Use Census identifying a location (s) that yields a v

a.

t calculated dose %r dose commitment greater than the values currently beingcalculated% specification 4.11.2.3,/dentifythenewloca-tion (s) in the nex Semiannual Radioactive / Effluent Release Report, me (4 T

pursuant to Specifi tion 6.9.1.7.

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b.

With a Land Use Census identifying a 1ptation(s) that yields a

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calculated dose or dose commitment (yia the same exposure pathway) p 20% greater than at a lo tion frog'which samples are currently e with/ specification 3.12.1, add the new S

being obtained in accorda location (s) within 30 days o the Radiological Environmental Moni-w toring Program given in the DCM. The sampling location (s), excluding the control station location, aving the. lowest calculated dose or

...._ dose. commitment (s),.via the/sa exposure pathway, may be deleted from this' monitoring program af r-October 31 of the year in which

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y this Land Use Census was/conducte. Pursuant to Specification 6.14, submit in the next Semjiinnual Radi etive Effluent Release Report documentation for a change in the O M including a revised figure (s)-

and table (s) for the'0DCM reflecting he new location (s) with infor-mation supporting t'he change in sampli locations.

j The provisions pf Specifications 3.0.3 a 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENT 4.12.2 The Land Census shall be conducted during th growing season at least once pe 2monthsusingthatinformationthatw{1providethebest results, such a by a door-to-door survey, aerial survey, o. by consulting local agriculture authorities. The results of the Land Use nsus shall be

' included in 3 e Annual Radiological Environmental Operating R ort pursuant to 6

Specific 4n 6.9.1.6.

Broa/ leaf vegetation sampling of at least three different kinds of vegetation may/ e performed at the SITE BOUNDARY in each of two different direc ion sectors b

w'th the highest predicted D/Qs in lieu of the garden census. Specif sations or broad leaf vegetation sampling in Table 3.12-1, Part 4.c. shall be Ypliowed, including analysis of control samples.

9 CAllAWAY - UNIT 1 3/4 12-13

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INTERLABORATORY COMPARISON PROGRAM LIMITING CONDIT

_FOR OPERATION N N 3.12.3 Analyses shall b ef erials supplied as part ofanInterlaboratoryComparbormedonradioactivem oo Program that has b approved by the Commission.

APPLICABILITY: At all times.

ACTION:

a.

With analyses not being pe ormed as r'tquired above, report the corrective actions taken o prevent a reh grence to the Commission in the Annual Radiolog al Environmental Oper ting Report pursuant to Specification 6.9

.6.

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b.

The provisions Specifications 3.0.3 and 3.0.4 a' not applicable.

SURVEILLANCE RE IREMENTS j

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4.12.3 he Interlaboratory Comparison Program shall be described in the ODCH.

A su ary of the results obtained as part of the above required Interlaboratory to arison Program shall be included in the Annual Radiological Environmental erating Report pursuant to Specification 6.9.1.6.

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INSTRUMENTATION BASES-a 3/4.3.3.8 LOOSE-PART DETECTION SYSTEM-The OPERABILITY of the loose-part detection instrumentation ensures' that sufficient capability is available *w detect loose metallic. parts in-the.

Reactor Coolant System and avoid or mitigate damage to Reactor Coolant System -

components. -The allowable out-of-service times.and Surveillance Requirements 4 ^ '

are' consistent with the recommendations of Regulatory Guide-1.133, " Loose-Part Detection Program for.the Primary System of Light-Water-Cooled Reactors,"

May 1981.

~3/4.m M OACTIVE'LIOUID EFFLUENT MONITORING INSTRUMENTATION The radioact e

nt instrumentation ovided to monitor 1

and control; as' applicable, t fr 1ve materials'in. liquid effluents during actual or potential'-

iquid effluents. The -

Alarm / Trip Setpoints for these

. uments shall-be 1tglated and adjusted in accordance with the m +

o ogy and parameters in the D %. + ensure that the alarm / trip wil ur prior to exceeding the limits of 10 CFR

+ 20.

The OPERABILT*

nd use of this instrumentation is consistent with the requir

, s of General Design Criteria 60, 63, and 64 of Appendix A to l

rd Part 50.

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. INSTRUMENTATION

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.4 4.3.3.10 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATlDN The ra tive gaseous effluent instrumentation vided to monitor and control, as a able, the releases of radio 4;ti e materials in gaseous O

effluents during actua tential releases ef' gaseous effluents. The Alarm /

b Trip Setpoints for these instr s sha e calculated and adjusted in accordance with the methodology and eters in the ODCM to ensure that the alarm / trip will occur prior to eding t mits.of 10 CFR Part 20. This instrumentation also includ rovisions for moni ng (and controlling) the concentrations of poten31e y explosive gas mixtures WASTE GAS HOLDUP SYSTEM. The OPERAB LITY and use of this instrumentation is istent with the. requirements General Design Criteria 60, 63, and 64 of App A to 10 CFR Part The sensitivity of any noble gas activity monitor use show complian with the gaseous effluent release, requirements of Specifica-I tion. 1.2.2 shall be such that concentrations as low as 1 x 10 S pCi/cc are F

(m surable.

3/4.3.4 1URBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed. Although the orientation of the turbine is such that the number of potentially damaging missiles which

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I' could impact and damage safety-related components, equipment, or structures is

/l minimal, protection from excessive turbine overspeed is required.

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3/4.11 RADIOACTIVE EFFLUENTS

,H BASES h4.11.1-LIQUIDEFFLUENTS 3/4

.1.1 CONCENTRATION Th specification is provided to ensure that the concentration of radioacti materials released in liquid waste effluents to UNRESTRICTED AREAS will be les ' than the concentration levels specified in 10 CFR Part 2,' Appen-dix B, Table

.I, Column 2.

This limitation provides additional ass ance that the' levels of dioactive materials in bodies of water in UNRESTRIf ED AREAS l will result in posures within:. (1) the Section II. A design objectives of Ap' pen-

-dix I, 10 CFR Par 50,' to a MEMBER OF THE PUBLIC, and (2) the eits of 10 CFR Part 20.IO6(e) to e population. The concentration limit fo dissolved or

. entrained noble gas is based upon the assumption'that Xe-13 is the control-ling radioisotope an its MPC in air (submersion) was convpfted to an equivalent concentration in water sing the' methods described in In ernational Commission on Radiological Protecti (ICRP) Publication 2.

The required detection capabilities for radioac. ve materials in liquid waste samples are tabulated termsofthelower}/mitsofdetection(LLDs).

E Detailed discussion of the LL and other detectiph limits can be found in HASL Procedures Manual, HASL-30 (revised annual)y), Currie, L. A... " Limits.

for Qualitative Detection.and Qua titative Detptmination - Application to Radiochemistry," Anal. Chem. 40, 5 -93 (1968), and Hartwell, J. K., " Detection I

Limits for Radicanalytical Counting chni "s," Atlantic-Richfield Hanford Company Report ARH-SA-215 (June 1975).

'3/4.11.1.2 DOSE This specification is provided o imple ent the requirements of Sections II.A, III.A and IV.A of pendix I, Q CFR Part 50.

The Limiting Condition for Operation implemen theguidessagforthinSectionII.Aof Appendix I.

The ACTION statem.ts provide the required operating flexibility and at the same time implemen the guides set forth in Section IV.A of Appen-

-dix ! to assure that the re ases of radioactive mat rial in liquid effluents to UNRESTRICTED AREAS will e kept "as low as is reas ably achievable." Also, for f resh water sites wi drinking water supplies that an be potentially af fected by plant operpt) ions, there is reasonable assuran that the operation of,the facility will ot result in radionuclides concentrat ns in the finished drinking water that re in excess of the requirements of 40

'R Part 141. The dose calculation. thodology and parameters in the ODCM implem t the require-ments in Sectio [ dix I be shown by calculational procedures based oh models and 111.A of Appendix I which specify that cenform qce with the guides of Appe,p data, such ft the actual exposure of a MEMBER OF THE PUBLIC throu 5 appropri-ate pathwa is unlikely to be substantially underestimated. The eq tions specifiep in the ODCM for calculating the doses due to the actual rele e rates of ra active materials in liquid effluents are consistent with the me odology prov' d in Regulatory Guide 1.109, " Calculation of Annual Doses to Man f m

Ro ne Releases of Reactor Effluents for the Purpose of Evaluating Complia e CALLAWAY - UNIT 1 B 3/4 11-1

REVISlay 3

RADIOACTIVE EFFLUENTS

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7 Bases

,,SE (Continued) with FR Part 50, Appendix I,"

Revision 1, October '

and Regulatory Gui'de 1. 13,, " Estimating Aquatic Dispersion of Eff nts from Accidental and Routine Reactor Releases for the Purpose of Im nenting Appendix I,"

April 1977.

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3/4.11.1.3 LIOUID RADWASTE TREATMENT,8 STEM The OPERABILITY of tv Radwaste Treatment System ensures that this system will be available f

% benever liquid effluents require treatment prior to release to the ironment.NQg requirement that the appropriate portions of this syste e used when specif4ef provides assurance that the releases of radioac ' e materials in liquid efflugnts will be kept "as low as is reasonably ac vable". This specification impIhmegs the requirements of 10 CFR Part 50 6a, General Design Criterion 60 of Appendix to 10 CFR Part 50 and the de n objective given in Section II.D of Appendix I CFR Part 50.

The spe ied limits go wning the use of appropriate portions of 4 uid Radw e Treatment System were specified as a suitable fraction of the I

d gn objectives set forth in Section II.A of Appendix I, 10 CFR.Part 50, m ' i g,;iM <1 nonte y

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

i CALLAWAY - UNIT 1 B 3/4 11-2 j

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BASES LIQUID HOLDUP TANKS (Continued)

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the

' tanks' contents, the resulting concentrations would be less than t.he limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

& 4.11.2 GASEOUS EFFLUENT 5

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.1 DOSE RATE I

Thi b cification is provided to ensure that the dose at any time at d

aeyond the BOUNDARY from gaseous effluents from all units on the sit will

>e within the anqual dose limits of 10 CFR Part 20 to UNRESTRICTED AREA The

<innual dose limitt te the doses associated with the concentrations o 10 CFR Part 20,' Appendix B, able II, Column 1.

These limits provide reas able issurance that radioac ive material discharged in gaseous effluen+ will not

'esult in the exposure o a MEMBER OF THE PUBLIC in an UNRESTRI.ED AREA, either within or outside e SITE BOUNDARY, to annual average concentrations i

exceedingthelimitsspecifydinAppendixB.TableIIof1 CFR Part 20

10 CFR 20.106(b)). For MEMB 5 0F THE PUBLIC who may at imes be within the SITE BOUNDARY, the occupan of that MEMBER OF THE JBLIC will usually be

' ~

sufficiently low to compensate f any increase in th atmospheric diffusion factor above that for the SITE B0 ARY.

Examples calculations for such MEMBERS OF THE PUBLIC, with the app priate occup cy factors, shall be given in the ODCM. The specified release r ?e limits estrict, at all times, the corresponding gamma and beta dose rates bove ackground to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to es than or equal to 500 mrems/ year to the whole body or to less than or equal o 3000 mrems/ year to the skin.

These release rate limits also restrict t 11 times, the corresponding thyroid dose rate above background to child ia the inhalation pathway to less than or equal to 1500 mrems/ye The required detection cap ilities for radio tive materials in gaseous waste samples are tabulated i terms of the lower li *ts of detection (LLDs).

Detailed discussion of the D, and other detection li ts can be found in HASL Procedures Manual, HASL-32 (revised annually), Currie, A.,

" Limits for l

Qualitative Detecti E y d Quantitative' Determination - Ap ication to Radio-chemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.

. " Detection f

l Limits for Radioapalytical Counting Techniques," Atlantic Ric.#ield Hanford J

Company Report FtH-SA-215 (June 1975).

3/4.11.2.2 E - NOBLE GASES 1

1 is specification is provided to implement the requirements of j

se ions II.B Ill.A and IV.A of Appendix 1. 10 CFR Part 50.

The Limitin-I ggML 8 g

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NOBLE GASES (Continued) l Conditio for Operation implements the guides set forth in Section II.B of Appendix I.

The ACTION statements provide the required operating flexib' ity and at the sa time implement the guides set forth in Section IV.A of ppendix I to assure'that releases of radioactive material in gaseous efflu ts to UNRESTRICTED AREA ill be kept "as low as.is reasonably achievabl. ' The Sur-veillance Requirement implement the requirements in Section III of Appendix I that conformance with t guides of Appendix I be shown by cal ational proce-i dures based on models and ta such that the actual exposure f a MEMBER OF li THE PUBLIC through appropria. pathways is unlikely to be bstantially under-4 i

estimated.

The dose calculati methodology and paramet s established in the I

l ODCM for calculating the doses d to the actual relea rates of radioactive noble gases in gaseous effluents ar consistent with e methodology provided in Regulatory Guide 1.109, "Calculati of Annual ses to Man from. Routine i

Releases of Reactor Effluents for the P ose of valuating Compliance with 30 CFR Part 50, Appendix I," Revision 1, tob 1977 and Regulatory Guide 1.111, C

T

'" Methods for~ Estimating. Atmospheric Transpo and Dispersion of. Gaseous Effluents in" Routine Releases f rom Light-Water Coole ctors," Revision 1, July.1977.

h The ODCM equations provided for determin' g the ir doses at and beyond the SITE BOUNDARY are based upon the histo cal avera atmospheric conditions.

3/4.11.2.3 DOSE - 10 DINE-131 AND 3, TRITIUM, AND 10 ACTIVE MATERIAL IN PARTICULATE FORM

)

.g This specification is p vided to implement the requi ments of

..)

Sections II.C, III.A and I.A-of Appendix I, 10'CFR Part 50. The Limiting Conditions for Operation re the guides set forth in Section

.C of Appendix 1.

The ACTION statements ovide the required operating flexibilit and at the same time implement e guides set forth in Section IV.A of Appe ix I to assure that the releases radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be ke "as low as is reasonably achievable." The ODCM c culational methods specif' d in the Surveillance Requirements implement the requi ments in Section J

.A of Appendix I that conformance with the guides of Appe ix I be shown b calculational procedures based on models and data, such that actual e osure of a MEMBER OF THE PUBLIC through appropriate pathways is unlike tn be substantially underestimated. The ODCM calculational method-

)

niog and parameters for calculating the doses due to the actual release rates J

of e subject materials are consistent with the methodology provided in Regula-y Guide 1.109. " Calculation of Annual Doses to Man from Routine Releases of eactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, W

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BAS DOSE - 1 i-131 AND 133, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE

%RM (Continued)

Appendix I,"

Rev on 1, October 1977 and Regulatory Guide

.111. " Methods'for Estimating Atmosphe c Transport'and Dispersion of Gaseou Effluents in Routine Releases from Light-W r-Cooled Reactors," Revision 1, uly 1977. These equa-tions also provide for.

ermining the cetual d.oses b ed upon the historical average-atmospheric condit s.

The release rate s cifications for Iodine-131 and 133, tritium, and radionu ides'in particulat form with half-lives greater.

than 8 days are dependent upon e existing rad nuclide pathways to man, in the areas at and beyond the SITE NDARY. T pathways that were examined in the development of these calculation were:

(1) individual, inhalation of airborne radionuclides, (2) deposition radionuclides onto green leafy vege-tation with subsequent consumption by

, (3) deposition onto grassy areas where milk animals and meat producin nima g graze with consumption of the milk

'and. meat'by' man,.and (4) deposition n the gr' d with subsequent exposure of man.

~

3/4.11.2.4 GASEOUS RADWASTE TR TMENT SYSTEM The OPERABILITY of theat the systems will be availa{he ' VENTILATION EXHAUST, ASTE GAS HOLDUP SYSTEM and%

TREATMENT SYSTEM ensures b

for use whenever gaseous effluents requi treatment prior to release to the nvironment. The i

requirement that the propriate portions of these systems be sed, when l

specified, provides essonable assurance that the releases of r ioactive materials in gase s effluents will be kept "as low as is reasona y achievable".

(

-This specificat' n implements the requirements.of 10.CFR Part 50.3 General Design Criter n 60 of Appendix A to 10 CFR Part 50, and the design ectives given in Se ion 11.0 of Appendix I to 10 CFR Part 50.

The.specified - mits governing e use of appropriate portions of the systems were specified a

suitabl fraction of the dose design objectives set forth in Sections II.B d

II.C o Appendix I, 10 CFR Part 50, for gaseous effluents.

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RADI0 ACTIVE EFFLUENTS

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.h 3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits. of hydrogen and oxygen. Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits. These automatic control features include isolation of the source of hydrogen and/or oxygen. Maintaining the concentration of hydrogen and oxygen below their flammability limits pro-vides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

3/4.31.2.6 GAS STORAGE TANKS The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly

.by another Technical Specification. Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an unco 7 trolled release of the tank's contents, the resulting whole body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will rot exceed 0.5 rem.

This is consistent with Standard Review Plan 11.3, Branch Technical Position ETSB 11-5, " Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure," in NUREG-0800, July 1981.

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This specificatica implements the requirements of 10 a and General Design Criterion 7tbofdppendix A to 1 ER-P 50.

The process parameters included in establishing"the ff.00E ONTROL PROGRAM may include, but are not limited to, waste,typeliiste bas uid/ SOLIDIFICATION agent /

catalyst ratios, was,teAMo'ntent, waste principal nstituents, and mixing andjurirrg'fimes.

RGLO CRTED

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.4' TOTAL DOSE R

Th specification is provided to meet the dose limitations of 40 The Part 190 t t have been incorporated into 10 CFR Part 20 by 46 FR 18 specification equires the preparation and submittal of a Special port whenever the ca ulated doses due to releases of radioactivity d the radia-tion from uranium el cycle sources exceed 25 mrems to the le body or any organ, except the th id, which shall be limited to less an or equal to 75.mrems. For sites co aining up to four reactors, it highly unlikely that the resultant dose to a M ER OF THE PUBLIC will ex d the dose limits of 40 CFR Part 190 if the indiv al reactors remain hin twice the dose design objectives of Appendix I, and iT irect radiatio doses from the reactor units

.and from outside storage tanks are pt small The Special Report will describe a course of action that should result ' th imitation of the annual dose to a MEMBER OF THE PUBLIC to witnin the 40

. Part 190 limits. For the purposes of.the Special Report, it may be assum t

the dose commitment to the MEMBER OF THE PUBLIC from other uranium fu cycle s rces is negligible, with the exception that dose contributions om other nu 3 ar fuel cycle facilities at the same site or within a radi of 8 km must be c sidered.

If the dose to j

any MEMBER OF THE PUBLIC is imated to exceed the uf rerrents of 40 CFR Part 190, the Special Rep with a request for a varia e (provided the-release conditions resu ing in violation of 40 CFR Part

. have not already been corrected), in ordance with the provisions of 40 CF ' 90.11 and 10 CFR

(

20.405c,:is consid ed to be a timely request and fulfills the ecuirements of 40 CFR Part 190 til NRC staff action is completed. The varian only relates f 40 CFR Part 190, and does not apply in any way to e other to the limits for dose limitation of 10 CFR Part 20, as addressed in 5'.cifica-requiremen tions 3.

.1.1 and 3.11.2.1.

An individual is not considered a MEMBER

.THE PUBLI uring any period in which he/she is engaged in carrying out any o ra-Lio hat is part of the nuclear fuel cycle.

Ret.oarreo so CYD CY t

CALLAWAY - UNIT 1 B 3/4 11-7

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REVISlay y H

3/4.12, RADIOLOGICAL ENVIRONMENTAL MONITORING l

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.12.1 MONITORING PROGRAM Radiological Environmental Monitoring Program required by this specifi tion provides representative measurements of radiation and of dio-active ma ials in those exposure pathways and for those radionucli s that lead to the ighest potential radiation exposures of MEMBERS OF T PUBLIC resulting fro the station operation. This monitoring program lementsSection IV.B.2 Appendix 1 to 10 CFR Part 50 and thereby s lements the Radiological Eff1 t Monitoring Program by verifying tha e measurable concentrations of r ioactive materials and levels of rad tion are not higher than expected on the

. is of the ef fluent measuremey'and the modeling of n

the environmental expos pathways. Guidance for Jnis monitoring program is "provided'by the Radiologic,]' Assessment Branch Tectinical Position on Environ-mental Monitoring, Revision November 1979.Aeinitiallyspecifiedmoni-toring program will be effecti

.for at leas the first 3 years of commercial operation.

Following this perio, rogra hanges may be initiated based on operational yxperience.

The required detection capabi]A ies or environmental sample analyses

}

are tabulated in terms of the low (r limits detection (LLDs). The LLDs required by Table 4.12-1 are gaffsidered optim for routine environmental measurementsinindustrial) laboratories.

It sho be recognized that the

-(

LLD is defined as an a_ priori (before the f act) lim (representing the capa-bility of a measuremenysystem and not as an a, posteribej (after the fact) limit for a particul f measurement.

Detailed df cussion of the LLD, and other detection limits, can be found in HASL Proc Dres Manual, HA5L-300 (revised annually), Currie, L.

" Limits

'for Quali ive Detection and Quantitative Determination - Applicati to Radioc istry," Anal. Chem. 40,'586-93 (1968), and Hartwell, J. K., "

ction Lim for Radioanalytical Counting Techniques," Atlantic Richfield Hanfor pany Report ARH-SA-215 (June 1975).

AsLoaVTED 40

@CO CALLAWAY - UNIT 1 B 3/4 12-1

R{yggION 3/4.12 = RADIOLOGICAL ENVIRONMENTAL MONITORING z

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- 3/4.12.2 AND USE CENSUS

-l This spe itation is provided to ensure that changes in the se of areas at and beyond t SITE BOUNDARY are identified and that modif ions to the Radiological Envir ~ ental Monitoring Program given in th M are made if required by the resu of this census.

Information th ill provide the best

- results, such as door-t oor survey, aerial survey consulting with local-agricultural authorities, - all be used. This c us satisfies the requirements-of'Section IV.B.3 of Append 1 I to 10 CFR Par Restricting the census to gardens of greater than 50 m2p vides ass nee that significant exposure path-ways via leafy vegetables will be ent ed and monitored since a garden of this size is the minimum required to-oduce the quantity (26 kg/ year) of leafy

- vegetables assumed in Regulatory de 9 for consumption by a child. To determine this minimum garden e' e, the fo ing assumptions were made:

(1) 20% of the garden was u for growing bro leaf vegetation (i.e., similar 2

to lettuce and cabbage),

d (2) a vegetation yie of 2 kg/m,

l 3/4.12. 3 'INTERL ATORY COMPARISON PROGRAM The re _ rement for participation in an approved Interlabora Comparison Program i rovided to ensure that independent checks on the precisio,n

'id accu-racy of e measurements of radioacti,ve material in environmental sample O

matr' s are performed as part of the quality assurance program for environ-

~[

- m al monitoring in order to demonstrate that the results are valid for the rposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

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lurbine Overspeed Protectinn Reliability Program e.

A program to increase the assurance that the Turbine Overspeed l

Protection System functions, if challenged, and to assure structural integrity of turbine components which could result in missile gen-eration'in the event of an actual overspeed occurrence. The pro-gram shall include the following:

1)

Periodic testing and inspection requirements, 2)

Specification of test and inspection intervals, and 3)

Administrative restrictions and procedural guidance for program implementation such as: record keeping; reporting; evaluation and disposition of discrepancies; review and approval of revisions to the program; and authorization (s) required to program guidelines.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS In addition to the applicable reporting requirements of Title 10, Code 6.9.1 of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the NRC Regional Office unless otherwise noted.

STARTUP REPORT

- 6. 9.1.1 A summary report of plant startup and power escalation testing shall be submitted following:

(1) receipt of an Operating License, (2) amenament to the ticense involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a differest fuel supplier, and (4) modifications that may have significantly altered the nuclear,.

thermal, or hydraulic performance of the plant.

6.9.1. 2 The Startup Report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions'and specifications.

Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6. 9.1. 3 Startup Reports shall be submitted within:

(1) 90 days following completion of the Startup Test Program, (2) 90 cays following resumption or commencement of commercial power operation, or (3) 9 fronths following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed.

.A.N_NUAL REPORTS 6.9.1.4 Annual Reports covering the activities of the unit as described below f or the previous calendar year 7, hall be submitted prior to March 1 of each year. The initial report shall bt submitted prior to March I of the year following initial criticality.

CALLAWAY - UNIT 1 6-17 i

m.

1

Insert B f.

Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC l

from radioactive effluents as. low as reasonably achievable.

The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.

The program shall include the following elements:

1)

Limitations on the. operability of radioactive liquid and gaseous monitoring instrumentation including surveillance-tests and setpoint determination in accordance with the methodology in the ODCM, 2)

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2, 3)

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM, l

4)

Limitations on the annual and quarterly doses or dose commitment'to a MEMBER OF THE PUBLIC from I

L radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50,

)

5)

Determination of cumulative and projected dose l

contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6)

Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radic. activity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50,

s s

(/'

- I.,:

tInsert B continued-6.8[4.f. ' Radioactive' Effluent Controls Program (Cont.)

7):

Limitations on the dose rate resulting from-radioactive material-released in. gaseous-effluents to' areas beyond the SITE BOUNDARY

' conforming to the doses associated with'10

- CFR Part-20, Appendix B, Table II, Column 11, 8)

Limitations ~on the annual and quarterlyfair doses resulting'from noble gases released in-

. gaseous'effluentsLfrom each unit to areas-beyond the SITE BOUNDARY conforming to

. Appendix I to 10 CFR Part 50, 1

9)^

Limitations'on the annual and quarterly doses

~

1to a MEMBER OF THE PUBLIC from Iodine-131,

. Iodine-133,-tritium, and all radionuclides in

. particulate. form.with half-lives greater than 8 days'in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY-conforming to Appendix I to 10 CFR Part 50, 10)

Limitations on the annual dose or dose commitment to any MEMBER OF THE FUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR'Part 190.

g.

Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the

" plant..The programLshall provide (1) representative measurements of radioactivity in the highest potential exposure pathways,. and (2)

L verification of the accuracy of the effluent monitoring program and modeling of environmental l

exposure pathways.

The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50,.and (3) include the following:

1)

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the

. environment in accordance with the methodology and parameters in the ODCM,

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Insert B' continued.

2)'

A L'and'Use~ Census.to ensure that changes in V

the use of areas at and beyond.the SITE-BOUNDARY..are identified.and'that modifications to:theanonitoring program are, c

made if required by the resulto of this census; and 3)

Participation in.a Interlaboratory_ Comparison Program to ensure;that independent' checks on the precision andLaccuracy of;the=

measurements of, radioactive materials in environmental sample matrices'are performed H

.as part of:the quality ascurance program for environmental monitoring.

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ADMINISTRATIVE CONTROLS l

-ANNUAL REPORTS _(Continued) l 6.9.1.5 Reports required'on an annual basis shall. include a tabulation on an-

-annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrems/yr and their associated man-rem exposure according to work and job functions,* e.g., reactor operations

~'

and surveillance,; inservice' inspection, routine maintenance, special mainte-nance (describe maintenance), waste processing.and refueling. The dose assignments to various duty functions may be estimated based on pocket dosi-meter, TLD, or film' badge measurements.. Small exposures totalling less than 20% of the individual total-dose need not be accounted for. In the aggregate, at least. 80% of'the total whole body dose received from external sources should be assigned to specific major work functions.

~

The report shall also include the results of specific activity analysis in which the primary, coolant exceeded the limits of Specification 3.4.8.

The p

following infonnation shall be' included:- (1) Reactor power history starting.

(2) Results

'48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit vias exceeded:

of the-last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit.

Each result should include date and time of sampling and the radiciodine-concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine Ifmit.

ANNUAL RADIOLOGICAL ENVIRONMEitTAL OPERATING REPORT **

nh 6.g.1.6

^

tv.. uni Rodk,legicsi O.i.e,-nt.PCperanng Repor i; w.}a6 ion of ing e previous calendar year s submitted for to May 1 f each year.

"tial report s 61' u mi prior

.o 1 of the r following in ial er Oper(ing Re shall inc1 de; The Annual diological nviro ries, i te retations, nd ysis of rends of tp 1 ts o the[

adio ogical envi onmental ypre adce activi ies fo th report od, t

inclu ing a compar(son tfi preoperat onal studies, w th peration 1 co 1s and wi p vious to ental survei lance ports, n an assess nt of the obs cts f e plant opera on n the env p nment. The reports shall' nel u' a-t'.c. =1ts-of4and-U nsusas-voquired by 5 F4fi

.9 1HseRT c.

1

~

This tabulation supplements the requirements of 820.407 of 10 CFR Part 20.

- A single submittal may be made for a multiple unit station.

l I

CALLAWAY - UNIT 1 6-18 Amendment No. 27 I

Insert C 6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall.be submitted before May 1 of each_ year.

The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

1 l

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II l-ADMINISTRATIVE C0itTROLS Al1NUAL RADIOLOGICAL ENVIRONMENTAL OPERATIf1G REPORT. (Continued)

Annual Radiological Envir'onmental Operating Reports Js ar include f all j

the resu saf analysis of all radiological environmental,sa:fiples and o environmental ation measurements. taken during thepfied pursuant to the

[

locations specifie in4he Table and Figures in the1DCM, as well as summarized and tabulated}esq1ts of these andyibs and measurements in the format of the table in the Radio ogical Assessment Branch Technical Position, Revision 1, November 1979. In the 6 that so=e individual results are not available for inclusion with the re' port,

'e report shall be submitted noting "1ts. The missing data shall and explaining the reasons (for'the missing r be submitted as soon as sible in a supplementha eport.

The reports shall also include the followir.g: a s

. ry description of the radiologij.a1,. environmental. monitoring program; at least twDo egible maps ***

L coveringjM sampling locations keyed to a table giving distances andN4 ections from the centerline of one reactors the results of licensee participation n

7 s

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s t CALLAWAY - UNIT 1 6-18a Amendment No. 27 e

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I-REVISlay y

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ADMINISTRATIVE CONTROLS ANNUAL' RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ** (Continued) 4

. h ieri a..t g ca m ehnn peg-.. anu tne corrective action being tak f if.the ied program is not being performed as required b ation 3.12.3; reasons of not conducting the Radiological ental Monitoring

]

Programasrequiredby)tc441cQion tscussion of all deviations

]

.from the sampling schedule discussion of environmental' sample j

measurements.tha ed the reporting leve 3.12-2 but are not the result o plant effluents, pursuant to Specification discussion of analyses in which the LLD required by Table 4.12-1 was not achievevi SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

t 6.9.1.7 o

em'TannuePRacioactTW Efflucou neiene neports covering the era ion of tne unit during the previous 6 months of operation shall be mitted within 60 days af ter January 1 and July 1 of each year. The per d s

of t first report shall begin with the date of initial criticality.

'k The miannual Radioactive Effluent Release Reports shall incly a

summary of quantities of radioactive liquid and gaseous effl hts and solid waste re ogsed from the unit as outlined in Regulatory de 1.21,

" Measuring,EvaluTtfng,andReportingRadioactivityinSol Wastes and Releases.of Radioactke Materials in Liquid and Gaseous fluents frcan Light-Water-Cooled Nucl r Power Plants," Revision 1 une 1974, with data f.

e summarized on a quarterly sis following the fo of Appendix B thereof.

i ', f For solid wastes, the format qr Table 3 in Ap ndix B shall be supplemented with 'three additional categorieh class of olid waste (as defined by 10 CFR u-Part 60), type of container (e.g.,

A, pe A, Type B, Large Ouantity), and SOLIDICATION agent or absorbent (e.g.

ement, urea formaldehyde).

The' Semiannual Radioactive y fluent R Qase Report to be submitted within 60 days af ter January 1.of ea.c(year shall inM de an annual summary of hourly meteorological data collec d over the previous This annual summary may be either in the form o, an hour-by-hour listing on og etic tape of wind speed. wind directi, atmospheric stability, and precip on (if measured),

or in the form o oint frequency distributions of wind speed, d direction, and atmospher stability.** This same report shall include an a wussment of the radiat~

doses due to the radioactive liquidjand gaseous effluen'ts released from th init or station during the previous calendar year. This same re rt shal 15o ir.clude an assessment'of the radiation doses from radioactive l

1 sid and gaseous ef fluents to MEMBERS OF THE PUBLIC due to their activities D456RT C C-

~

"A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

n li3u of mission ytt the Semiannual Radio tive E Jent ase g

epprL, t li enseeAas t e optjin of etal ing his.umm 3r r qu d

mepeorolpgical dat.4 on sit in 4 file tlat shall e rovidt# to th R

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CALLAWAY - UNIT 1 6-19

Insert'CC 6.9.1.7 The Semiannual Radioactive Effluent Release Report j

covering the operation of the unit during the I

previous 6 months of operation shall be submitted

{

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 4

effluents and solid waste released from the unit, d

The material provided shall be (1) consistent with l

the objectives outlined in the ODCM and PCP and

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(2) in conformance with 10 CFR 50.36a and Section j

IV.B.1 of Appendix I to 10 CFR Part 50.

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ADMINISTRATIVE CONTROLS

. "A.

5

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_ SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT * (Continued)

-~

b de the SITE B0UNDARY (Figures 5.1-3 and 5.1-4) during the report period using istorical average atmospheric conditions. All assumptions used in ma ng these as ssments, i.e..' specific activity, exposure time and location, sh be included i these reports. The meteorological conditions concurrent wi he time of relea of radioactive inaterials in gaseous effluents, as dete ned by sampling freque and measurement, shall be used for determining th ' gaseous pathway doses. Th assessment of radiation doses shall be perform in accord-fancewiththemethod1pgyandparametersintheOFFSITEDOSECAL LATION MANUAL (DDCM).

The Semiannual Radioact v Effluent Release Report to e submitted within 60 days af ter January 1 of each ear shall also include assessment of I

radiation doses to-the likely.mos exposed. MEMBER OF T PUBLIC from Reactor L

releases and other nearby uranium f cycle sources including doses from primary effluent pathways and direct r iation, fo the previous calendar year f

to show conformance with 40 CFR Part 190, "Envi mental Radiation Protection Standards for Nuclear Power Operation." Ac ble methods for calculating the dose contribution from liquid and gaseo ffluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

l t

The Semiannual Radioactive Efflye'nt Release Re rts shall include a list and description of unplanned releases from the site UNRESTRICTED AREAS of y

radioactive materials in gaseous nd liquid effluents de during the reporting fl,.

period.

' fa The Semiannual Radio ive Effluent Release Reports sha 1 include any

' changes made during the porting period to the FCP and the O M, pursuant to n Specifications 6.13 an

.14, respectively, as well as any majo change to

. Liquid, Gaseous, or lid Radwaste Treatment Systems, pursuant t Specifica-tion 6.15.

'It sha) also include a listing of new locations for se calcula-tions and/or.env'fonmental monitoring identified by the Land Use C.e us pursuant to Specificati 3.12.2.

The S iannual Radioactive Effluent Release Reports shall also inc e

the foll ing information: An explanation as to why the inoperability of a

liquid r gaseous effluent monitoring instrumentation was not corrected wi in l

the me specified in Specification 3.3.3.10 or 3.3.3.11, respectively; and

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de ription of the events leading to liquid holdup tanks or gas storage tanks j

e eeding the limits of Specification 3.11.1.4 or 3.11.2.6, respectively.

J HONTHLY OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the pressurizer PORVs or RCS safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washin-) ton, D.C.

20555, with a copy to the NRC Regional Office, no later than the 15th of each month following the calendar month covered by the report.

.)

CALLAWAY - UNIT 1 6-20

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ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued)

Records of changes made to the proteoures required by Specification j

e.

6.8.1; f.

Records of radioactive shipments; Records of sealed source and fission detector leak tests and results; g.

and h.

Recorcs of ar.nual physical ir.ver. tory cf all sealed source raterial of record.

5.10.2 The felicsin; rccords shall be retained fcr the d:;raticn of the unit Operating License:

Records and crtwing cranges reflectir.; uni: cesign : deifications a.

cade tc systers and ecuioment described in the Final Safety Analysis Recort:

1 b.

Records of new and irradiated fuel inventory,. fuel transfers and assembly burnup histories; Records of radiation exposure for all individuals entering radiation c.

control areas; d.

Records of gaseous and liquid radioactive material released to the -

environs; Records of transient or operational cycles for those unit components e.

identified in Table 5.7-1; f.

Records of reactor tests and experiments; Records of training and qualification for current members of the g.

unit staff; h.

Records of in-service inspections perforned pursuant to these.

Technical Specifications; i.

Records of quality assurance activities required by the QA Program; j.

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

Records of meetings of the ORC and the NSRB; 1.

Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the service life commences and associated installation and maintenance

~

I records; Records of secondary water sampling and water quality; and m.

Records of analysis required by the Radiological Environmental n.

Monitoring Program that would permit evaluation of the accuracy should include procedures of the analysis at a latesdateMhi4'h ds showing that these effective at spetjMfd times and QA re procedures wer ellowed.

Insed-

~D CALLKn'AY - UNIT 1 6-22 Amendment No.

28 i

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Insert D o.

Records of reviews performed for changes made to APA-ZZ-01003, the OFFSITE DOSE CALCULATION MANUAL and APA-ZZ-01011, the PROCESS CONTROL PROGRAM.

1.

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. ADMINISTRATIVE CONTROLS

}

.3 HIGH RADIATION AREA (Continued) in radiation protection procedures to provide ppsitive exposure control over the activities being performed within Lhe area.

lor individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h that are located within large areas,'such as PWR containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area,.

l.

that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.

6.13 PROCESS CONTROL' PROGRAM (PCP)

IN5ER T F_.

.1 The PCP shall De appivved by who L.ommission prior to implementation.

6.13.2 ensee-initiated changes to the PCP:

a.

Shall submitted to the Commission in the Semiannua adioactive Effluent lease Report for the period in which change (s) was made. This bmittal shall contain:

Sufficiently ailed informat to totally support the J

1) rationalefort(hdqangew' out benefit of additional or

-supplemental informa I'

2)

'A determinate hat t e did not reduce the overall

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I 1

-conforman of the solidified ste product to existing cr.iteria for so 'd wastes; and 3) documentation of the fact that the change s been reviewed and found acceptable by the ORC.

Shall become effective upon review and approval by the ORC in accordance with Soarifir=tinn 6 U.1.

f 6.14- 0FFSITE DOSE CALCULATION MANUAL (ODCM) F IN SERT -

1 lhe N e!' M cpp ewed L.y the CEmmission17tm te i.p1mcHcaT.ivo.

6.14.2 Lic

%nitiated changes to the ODC!i:

a.

Shall be s mitttd to the Commission in the Sem pi al Radioactive Effluent Release R#por(for the period in,which the change (s) was made effective. This suDmi.

c6ntain:

1)

Sufficiently deta An7ormatic to totally support the rationale for hange without b it of additional or suppleme i nformation.

Information s

'tted should consist of ekage of those pages of the ODCM to be ed with each

~ge numbered, dated and containing the revision nu together with appropriate analyses or evaluations justifying th (e chso e(s);

)

/

CALLAWAY - UNIT 1 6-24 J

.. -. ~ - -..

9

L Insert E 6.13 PROCESS CONTROL PROGRAM (PCP)

Changes to the PCP:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2o.

This documentation shall contain:

1)

Sufficient information to support the change together with the appropriate analyses or evaluations-justifying the change (s) and 2)

A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or'other applicable regulations.

b.

Shall become effective after review and acceptance by the ORC and the approval of the Plant Manager.

Insert F 6.14 OFFSITE DOCE CALCULATION MANUAL (ODCM)

Changes to the ODCM:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2o.

This documentation shall contain:

1)

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2)

A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b.

Shall become effective after review and acceptance by the ORC and the approval of the Plant Manager.

)

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l I

Insert F-' continued c.

Shall be' submitted to the Commission in the: form H

of a. complete,. legible' copy of.the entire:ODCM as a part of'or concurrent.with the Semiannual 1

-Radioactive Effluent Release Report-for-the period-of the report in which any' change::to the.0DCM was made.

Each change shall be identified by' markings

'in the margin lof the'.affected pages, clearly i

indicating the area'of_the page-that was changed, 7

and shall indicate the date.-(e.g., month / year) the

_ change was implemented.

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J ADMINISTRATIVE' CONTROLS urr h DG5E--CALCutal10N MANUAL (OUGM) (Continued) ination that the change will.not reduc accuracy or reliabil dose calculations or Set determinations; and 3).

Documentation of act tha change has been reviewed.and found acc e by the ORC.

b.

S ecome effective upon review and approval by the

\\andin accordance with Specification 6.5.3.1.

q MAJORCHANGEST0-LIQUID, GASEOUS,ANDSOLIDRADWASTETREATMENTSYSTEM[

6.15.1 icensee. initiated major changes to the.Radwaste Treatment Syst

.s (liquid, eous,'and solid):

a.-

tShal reported.to the Commission in the Semiannual R ioactive

'Effluen elease' Report for the period in which the ev uation was reviewed b he ORC. Th'e discussion of each change iall'contain:

'1)

A summary the evaluation that led to the determination that the change co d be made in accordance wi 10 CFR 50.59;

}-

f 2)

Suf ficient detail ' information to tot ly support the reason for the change with t benefit of ad tiona'l or supplemental

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information;

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A detailed description o he uipment,. components and processes

(,).

involved and the interface.i h other plant systems; d-4)

An evaluation of the chan

,w

h shows the predicted releases c

of radioactive material in liq Ed and gaseous effluents and/or quantity of solid was that diff y from those previously predicted in the Li nse applicatio' and amendments theretc; l

5)

An evaluation o EMBER OF THE PUBLIC in k. the expected maximum the change, which sh e UNRESTRICTED AREA and exposures to to the gene population that differ from those previously estimated n the License application and am' dments thereto; j.

h 6)

A com rison of the predicted releases of radio tive materials, T

in' quid and gaseous effluents and in solid wast to the actual r eases for the period prior to when the changes a

..to be made:

7)

An estimate of the exposure to plant operating personne as a result of the change; and

' *Li' nSees may chose to submit the information called for in this specification part of the annual FSAR update.

CALLAWAY - UNIT 1 6-25 w______-_____-__

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REVISlay

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- V ADMINISTRATIVE' CONTROLS

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4 MAJOR CHAN O LIQUIDi GASEOUS, AND SOLID RADWAS TREATMENT' SYSTEMS

.(Continued) s

8).Documentat1B

. fact that the change was reviewed and found 3

acceptab1pAff

'DA approval by the ORC and in

... bome effective upon revi

'Sha p~ dance with Specification 6.5.3.1.

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CALLAWAY - UN]1 1 6-26

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. ULNRC-20 7 0 -

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SAFETY EVALUATION This amendment. request implements changes concerning.

I the radiological and environmental Technical Specifications

.(TS)..'The changes simplify the TS, while maintaining regulatory requirements.

Procedural details of the Radiological Effluent Technical Specifications (RETS) are-relocated from TS to the Offsite Dose Calculation Manual

-(ODCM), and for solid radioactive wastes to the Process Control Program (PCP).

In all cases the programmatic controls are retained in the Administrative Controls section of the TS. ~The! changes are based upon the guidance given in Generic Letter _89-01.

.In adoition an inappropriate footnote.

~

reference to Callaway as'a multiple unit-station is deleted.

This is a purely administrative change.

In Generic Letter 89-01 the NRC staff determined that

~

programmatic controls can be implementedzin the Administrative' Controls section of TS to' satisfy existing regulatory requirements ~for RETS.

At the same time the procedural details can be relocated to the ODCM of the PCP as appropriate.

The changes are consistent with the Commission's' goals for TS Improvements.

The proposed changes do not alter the content of the involved programs nor their implementation to meet.the regulatory requirements.

Revisions to the RETS remain under adequate controls and allow continued reporting for NRC review and oversight.

The substance of the proposed changes involves only administrative and documentation revisions, without1 a lessening of commitments in these areas.

The changes do-not impact the severity or the consequences of an accident.

They do not impact on the probability of an accident occurring or a>different accident than one already evaluated.

Based on the above discussion, the proposed Technical Specification changes do not adversely effect or endanger the health or the safety of the general public and do not involve an unreviewed safety question.

ULNRC-2070 SIGNIFICANT_ HAZARD EVALUATION This amendment requent implements changes concerning the radiological and environmental Technical Specifications (TS).

The changes simplify the TS, while' maintaining regulatory requirements.

Procedural details of the Radiological Effluent Technical Specifications (RETS) are relocated from TS to the Offsite Dose Calculation Manual (ODCM), and for solid radioactive wastes to the Process Control Program (PCP).

In all cases the programmatic controls are retained in the Administrative Controls section of the TS..The changes are based upon the guidance given in Generic Letter 89-01.

In addition an inappropriate footnote reference to Callaway as a multiple unit station is deleted.

.This is a purely administrative change.

In Generic Letter 89-01 the NRC staff determined that programmatic controls can be implemented in the Administrative Controls section of TS to satisfy existing regulatory requirements for RETS.

At the same time the procedural details can be relocated to the ODCM of the PCP as appropriate.

The changes are consistent with the Commission's-goals for TS Improvements.

Union Electric has reviewed the proposed changes and determined that:

1.

The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated because the_ proposed changes do not alter the content of the involved programs nor their implementation to meet the regulatory requirements.

2.

The proposed amendment does not create the possibility of a new or different kind of accident than previously evaluated because the change is administrative in nature, and no physical alterations of plant configuration or changes to setpoints or operating parameters are proposed.

3.

The proposed amendment involves an administrative type change and does not involve a significant reduction in a margin of safety.

Revisions to the RETS remain under adequate controls j

and allow continued reporting for NRC review and oversight.

The substance of the proposed changes involves only administrative and documentation revisions, without a lessening of commitments in these areas.

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l ULNRC-2070 1

)

The Commission has provided guidance concerning the

)

application of the standards in 10CFR50.92 by providing i

certain examples (48 FR 14870),

One of the examples of actions involving no significant hazards consideration j

relates to a purely administrative change to Technical Specifications.

.These requests do not involve a significant increase in the probability or consequence of an accident or other j

adverse condition over previous evaluations; or create the l

possibility of a new or different kind of accident or conditions over previous evaluations; or involve a significant reduction in a margin of safety.

Based on this information, the requested license amendment does not present a significant hazard.

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ML20247D823

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