ML18022A524

Proposed Tech Specs,Allowing Continuous Releases from Secondary Waste Sys

ML18022A524
Person / Time
Site:	Harris
Issue date:	05/14/1987
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18022A523	List: ML18022A522 ML18022A524
References
NUDOCS 8705190412
Download: ML18022A524 (13)

Text

ENCLOSURE 1 05190412 870514 PDR ADocr osooosoo ',

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INSTRUMENTATION RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with the',r Alarm/Trip Setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The Alarm/

Trip Setpoints of these chanrels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (OOCM).

APPLICABILITY:. At all times.

ACTION:

'a 0 Mith a radioactive liquid effluent aonitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above specification, immediately (1) suspend the re1ease of radioactive liquid effluents monitored by the affected channel or (2) declare the charnel inoperable and take ACTION as directed by b. below.

kith less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12. Exert best effort to return the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluert Release Report pursuant to Specification 6.9.1.4 why this inoperability was not corrected in a timely manner.

The provisions of Specifications 3.0.3 and 3.0.4, are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE channe'hall CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST at the fre-quencies shown in Table 4.3-8.

SHEARON HARRIS - UNIT 1 3/4 3-75

TABLE 3.3-12 RADIOACTIVE LI UID EFFLUENT HONITORING INSTRUHENTATION HINIHUH CHANNELS 1NSTRIIHjNT OPERABLE ACTION

l. Radioactivity Honitors Providing Alarm and Automatic Termination Q of Release

a. Liquid Radwaste Effluent Lines

1) Treated Laundry and llot Shower Tanks Discharge Honitor 35

2) Waste Honitor Tanks and Maste Evaporator Condensate Tanks 35 Discharge Honitor

3) Secondary Waste Sample Tank Discharge Honitor 35

b. Turbine Building Floor Drains Effluent Line

c. Outdoor lank brea Drain Transfer Pump Honitor 37

2. Radioactivity Honitors Providing Alarm But Not Providing Automatic Termination of Release

a. Normal Service Water System Return From Maste Processing 39 Building to the Circulating Water System

b. Normal Service Mater System Return From the Reactor Auxiliary 39 Building to the Circulating Mater System

3. Flow Rate Heasurement Devices

a. Liqui'd Radwaste Effluent Lines

1) Treated laundry and llot. Shower Tanks Oischarge

2) Waste Honitor Tanks and Waste Evaporator Condensate 38 links Oischarge

TABLE 3.3-$ 2 Continued}

RADIOACTIVE LI UID EFFLUENT HONITORING INSTRUHENTATION HINIHUH CHANNELS INSTRUHENT OPERABLE ACTION

3. Flow Rntr Hensuremant Oavicas (Continued)

3) Secondary Maste Sample Tank 38

b. Cooling Tower Slowdown 38 (dhcn Wc. ><~ 0~ khsde. Cyst~ i~ &i~ users'n rnid'de Acti~ Hb

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TABLE 3. 3-12 Continued ACTION STATEMENTS ACTION 35- With the number of channels OP&ABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway. diffluent ACTION 36- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, releases via this pathway may continue provided grab samples are analyzed fcr radioactivity at a lower limit of detection of no more than 10-~ microCurie/ml:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microCurie/gram OOSE E)UIVALENT I-131, or

b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microCurie/gram OOSE E(UIVALENT I-131.

ACTION 37- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requ'rement, effluent releases via this path~ay may continue prov'ded that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are col'ected and analyzed for radio-activity at a lower limit of detection of no more than 10-'icroCurie/ml.

ACTION 38 W th the number of channels OPERABLE less than required by the Minimum Channels OPERABLE req.'rement, effluent releases via this pathway mav continue prov'"ed the flow rate is estimated at least once pe". 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump perfo-.=

ance curves generated in place may be used to estimate flow.

ACTION 39- With the number o channels OP"=iABLE less than required by the Minimum Channels OPERABLE requ rement, effluents releases via th'.s pathway mav continue provided the weekly Cooling Tower B', a-down weir surve'.llance is pe. :rmed as required by Specifica-tion 4. 11. l. 1. l. Otherwise fc.low the ACTION specified in ACTION 37 above.

SHEARON HARRIS - UNIT 1 3/4 3-78

TABLE 4.3-8 RADIOACTIVE LlgUIO EFFLUENT HONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS DIGITAL CIIANNEL CHANNEL SOURCE CHANNEL OPERATIONAi.

INSTRUMENT CHECK CIIECK CALIBRATION TES1'.

Radioactiity Honitors Providing Alarm and Automatic Termination of Release Liquid Rachraste Effluent Lines

1) Treated Laundry and Hot Shower R(3) Q(l)

Tanks Discharge Monitor

2) Maste Honitor Tanks and R(3) Q(l)

Waste Evaporator Condensate lanks IIIscl>argo Monitor

3) Secondary Waste Sample Tank Q(I)

Oischarge Monitor

b. Turbine Building Floor Drains R(3) Q(i)

Effluent Line

c. OutElnor Tank Area Drain Transfer R(3) Q(i)

Pump Monitor

2. Radioactivity Honitors Providing Alarm But Not Providing Automatic Termination of Release

a. Normal Service Water System return From the Waste Processing ilui Iding to ll>r Circulating Water System R(3) Q(2)

TABLE 4.3-B ConL~Inned I'tQ t't t I NON I Rl G I I I Tl II R~NILI N E RE <<II 5 Cl DIGITAL CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL IHSTRUHEHf CHECK CIIECK CALIBRATION TEST

2. Radioactivity Honltors Providing Alarm Q But Not Provldlng Automatic lermlnation M of Release (Cont inued)

b. Normal Service Mater System Return R(3) O(2)

From the Reactor Auxiliary Building to the Circulating Mater System

3. Flow Rate Measurement Devices CAB a0 Liquid Radwaste Effluent Lines tel Treated Laundry and Hot Shower D(4) N.A. H.A.

I Tanks Discharge CO CB I

?) Waste Honitor Tanks and Maste D(4) N.A. H.A.

f.vnporator Condensato Tanks Discharge

3) Secondary Waste Sample Tank D(4) N.A. N.A.

b. Cooling Tower Blowduwn D(4) N.A. H.A.

TABLE 4.3-8 Continued TABLE NOTATIONS (1) The DIGITAL CHANNEL OPERA; IQNAL TEST shall also demonstrate'.that automatic isolation of this pathway and control room alarm annunciation occu~ if any of the following concitians exists:

a. Instrument indicates aeasured levels above the Alarm/Trip Setpoint, or

b. Circuit failure (mon;tor loss of coamunications (alarm only), detec.or

. loss of counts (Ala~ only) or monitor loss of power), or

c. Detector check source test failure (alarm only), or

d. Detector channel ou. of service (alarm only), or

e. Monitor loss af samp'~e flaw (alarm only).

(2) The DIGITAL CHANNEL OPERA;IONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm Setpoint, or

b. Circuit failure (moritor loss of communications (alarm only), detector loss of counts, or aanitor loss of power), or

c. Detector'heck source test failure, or

d. Detector channel out of service, or e.. Monitor loss of sample flow.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards .hat have been obtained fram suppliers that participate in measurement assurance activities with NBS. These standards shall permi calibrating the system over its intended range of energy anc measurement range. For subsequent CHANNEL CALIBRATION, sources tha have been related to the init'.al calibration shall be used.

(4) CHANNEL CHECK shall consist of verifying indication of flow during periacs of release. CHANNEL CHE:< shal1 be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on l.'ays on which con.inuous, periodic, or batch releases are mace.

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SHEARON HARRIS - UNIT 1 3/4 3-81

3/4. 11 RADIOACTIVE EFFLUENTS 3/4.11.1 LI UID EFFLUENTS CO!i"ENTRATION LIl'.:TING CONDITION FOR OPERATION 3.U..l.l The concentration of ra.ioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix 8, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-i microCurie/al total activity.

APPLICA8ILITY: At all times.

ACTION:

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concen-tration to within the above limi=s.

SURVEILLANCE RE UIREblENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4. 11-1.

4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and par ameters in the DDT to assure that the. concentrations

--at the point of release are mainwined within the limits of Specification

3. 11.1. 1.

SHEARON HARRIS - UNIT 1 3/4 11-1

TABLE 4.11-1 RAOIOACT!VE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM OF DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLO)(1)

TYPE FREQUENCY FREQUENCY ANALYSIS

1. Batch Waste P P PrincipaI>)astra Release Each Ba.ch Each Batch Emitters Sx10-7 Tanks I-131 1x10-s

a. Waste Monitor P Oissolved and 1xl0-s ~

Tanks One Batch/M Entt ained Gases

b. Waste (Gamma Emitters)

Evaporator P M H-3 ix10-s Condensate Tank Each Ba ch Composite( )

Gross Alpha 1 10-~ .

c. Secondary Waste (s P Sr-89, Sr-90 5x10 s Sample Tank Each Ba.ch Composite Fe-55 1 10-6

d. Treated Laundry and Hot

, Shower Tanks

2. Continuo')(7) W Principa J3gamme Sx10-6 7 Releases Continuous Compos i te Emi tters'

a. Cool ing M(7) M(7) Dissolved and 1x10-Tower Weir Gr ab S~,pie Entrained Gase~

(Gamma Emitters)

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I-131 1xl0-s (V) M H 3 ix10>>s 6 7 Contin~=us( Composi te Gross A aha 1x'l 0>> 7 Sr-89, 5x10 s Q Sr 90

) Composite 6 7 Con.i".." s Fe-55 1x10-6 SHEARON HARRIS - UNIT 1 3/4 11-2

TABLE 4. 11-1 Continued TABLE NOTATIONS (1) The LLD is defined, for purposes of these spe ifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95K probability with only 5X probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include rad'.ochemical separation:

4.66 sb E ~

V ~

2.22 x 106 ~

Y~ exp (-AAt)

Where:

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

sb = the standard deviation of the backg ound counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

l E = the counting efficiency (counts per disintegration),

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

2.22 x 10' the number of disintegrations per minute per microCurie, Y = the fractional radiochemical yield, when applicable, A, = the radioactive decay constant for tne particular radionuclide (sec-~), and bt = the elapsed time between the midpc'.nt of sample collection and the time of counting (sec).

Typical values of E, V, Y, and ht shoul" be used in the calculation.

It should be recognized that the LLD is defined as an a isriori (before the fact) lim.'t representing the capability o. a measurement system and l!: i(ft, f )1i ~::'. p A batch release is the discharge of liquid was es of a discrete volume.

Prior to samp'.in'or analyses, each batch s-all be isolated, and then

'thoroughly mixed by a method described in tne OOCM to assure representative sampling.

SHEARON HARRIS - UNIT 1 3/4 11-3

TABLE 4. 11-1 Continued TABLE NOTATIONS Continued (3) The principal gamma emmiters for which the LLO specification'pplies include the following radionuclides: Hn-54, Fe-59, Co-58, Co-60, En-65, Ho-99, Cs"134, Cs-137, and Ce-141. Ce-144 shall also be measured but with a LLO of 5 x 10-8. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are ident.'fiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specifica-tion 6.9.1.4 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(4) A composite sample is one in which the quantity of liquid sampled is ~

proportional to the quantity of liquid waste discharged and in which the

.method of sampling eaployed results in a specimen that is representative of the liquids released.

(5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(6) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to..the rate, of flow-of the"effluent stream.- Prior to analyses',

all samples taken for the composite shall be thoroughly mixed in order for the composite saurple to be representative of the effluent release.

(7) Thd point>monitor)f g potential release pathway~only and not ~ actual release pathways The potential contamination points are in the Normal Service Mater (NSW)~SystemP Action under this specification is as follows: ~~3 Se~d~ ~pc. (cw)

~p/ jask4. (Q5D ar SAX a) If the~ monitors in Table 3.3-12 are OPERABLE and not in I alarm, the.. no analysis unde~ this specification is required but weekly composites will be collected.

b) If monitor is out of service, then the weekly analysis for pnncipal gamma emi .:ers will be performed.

licccb4 c) If< ':nitor is in a',arm or if the pr'.ncipal gamma emitter analysis indicates the presence of radioactivity as defined in the OOCM, then all other analyses of this specification shall be performed a: the indicated frequency as long as the initia ing conditions exist.

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