ML18011A551

Proposed Tech Specs,Incorporating Programmatic Controls for Radioactive Effluents,Radiological Environ Monitoring & Solid Wastes in Administrative Controls Section of TS & Relocating Procedural Details of RETS Into ODCM or PCP

ML18011A551
Person / Time
Site:	Harris
Issue date:	08/19/1994
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18011A550	List: HNP-94-025, Application for Amend to License NPF-63,incorporating Programmatic Controls for Radioactive Effluents,Radiological Environ Monitoring & Solid Wastes in Administrative Controls Section of TS & Relocating RETS to ODCM or Pcp,Per GL 89-01 ML18011A551
References
NUDOCS 9408250031
Download: ML18011A551 (89)

Text

ENCLOSURE 5

SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS TECHNICAL SPECIFICATION PAGES

'7408250031 940819 PDR ADOCK 05000400 p

PDR

INDEX DEFINITIONS SiCTIQN PAGE

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1-5 l.33 1;34

l. 35 SOURCE CHECK..

1.36 STAGGERED TEST BASIS SLAVE RELAY TEST............

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1. 37

l. 38 THERMAL POWERo ~ ~ ~ ~ o ~ ~ ~ ~ ~

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TRIP ACTUATING DEVICE OPERATIONAL TEST....

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l. 39 UNIDENTIFIED LEAKAGE..

1.40 UNRESTRICTED AREA............

'. 4l YENTILATION EXHAUST TREATMENT SYSTEM.

'.42'ENTING..........

TABLE 1. 1 FREQUENCY NOTATION.

TABLE 1 2 OPERATIONAL MODES 1-6 1-7 1-7 1-8 SHEARON HARRIS - UNIT 1

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INDEX LIMITINC CONDITIONS FOR OPERATION AHD SURVEILLANCE REQUIREMENTS SECTION PACE TABLE 3-3-6 RADIATION MONITORIHC INSTRUMENTATION FOR PLANT OPERATIOHS......,.......,......................

TABLE 4.3-3 RADIATIOH MONITORING INSTRUMEHTATIOH FOR PLAhT OPERATIOHS SURVEI LLAHCE REQUIREMENTS.....................

Movable Incore Detectors.................................

Seismic Instrumentation.

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TABLE 3 '

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TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................

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Met coro log ical In s trumentat ion..... ~.....................

3/4 3-51 3/4 3-54 3/4 3-56 3/4 3-57 3/4 3"58 3/4 3-59 3/4 3"60 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION.............

3/4'"61 TABLE 4.3-5 METEOROLOGICAL MONITORINC INSTRUMENTATION SURVEILLANCE REQUIREMENTS ~

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Remote Shutdown System........,....,.....................

TABLE 3.3-9 REMOTE SHUTDOWN SYSTEM.....,...,....................:.

TABLE 4,3"6 REMOTE SHUTDOWN MONITORINC INSTRUMEHTATION SURVEILLANCE REQUIREMENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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Accident Monitoring Instrumentation......................

3/4 3-62 3/4 3"63 3/4 3"64 3/4 3-65 3/4 3-66 TABLE 3.3" 1.0 ACCIDENT MONITORINC INSTRUMENTATION....~.............

3/4 3-68 TABLE 4. 3-7 ACCIDENT MONITORINC INSTRUMENTATION SURVEILLANCE REQUIREMENTS'~

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Metal Impact Monitoring System.

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3/4 3"70 3/4 3-73 3/4 3-74 3/4 3-75 CX

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TABLE 3.3-13 MONITORINC INSTRUMENTATION.~.. ~.. ~ ~ ~ ~

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TABLE 4.3"9 MONITORING INSTRUMENTATION SURVEILLANCE REQUIRKMENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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3/4'.4 TURBINE OVERSPEED PROTECTIONAL.....o.

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3/4 3-82 3/4 3"83 3/4 3-86 3/4 3-89 SHEARON HARRIS - UNIT 1

V1 Amendment No.

LIMITING CONDITIONS FOR OPERATION ANO SURVEILLANCE REQUIREMENTS SECTION 3/4.11

.RADIOACTIVE EFFLUENTS 3/4. 11. 1 LIQUID EFFLUENTS CDW"ader PAGE (DE4NcgL OnCen atian oo\\ ~ oo ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ o ~ o ~

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. 11-1 DIOACTI LIQUI WASTE S PLING AND ALYSIS P ROG

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Liquid Ho'tdup Tanks..................-..

3/4. 11. 2 GASEOUS EFFLUEHTS ose at 0

T BLE 4 11-2 DIOACTs.VE GASEQ WASiE S PLING AND ANALYSIS P R RAMo

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3/4 11-l 3/4

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/4 11-6 3/4 11-7 3/4 2 8 3/4 11-9 3 4 11-12 3/4 11-13 3/4 2-o) 3/4.11.

3/4. 11. 4 Expkosi ve Gas Mixtureo

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3/4 11"15 3/4 11-16 3/4 11-17 3/4 11-19 3/4. 12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4. 12.

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. 12 PQRTIH LEVELS F RADIOA VITY CON TION IN VIRONM AL SAMP S.......

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ANA 3/4.12.2 ND SE CE US 3/4.12o 3 ER BQRAT Y COM ARISO PRQG g) 3/4 12-1 3/4

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/4 12-9 3/4 3/4 12-13 3/4 12"l4 SHEAROH HARRIS - UNIT 1 Xi1

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INDEX BASES 3/4.10.2 GROUP HEIGHT, INSERTION, ANQ POWER DISTRIBUTION 3/4.10.3 PHYSICS TESTS...................................

3/4.10.4 REACTOR COOLANT LOOPS.............

3/4.10.5 POSITION INDICATION SYSTEM - SHUTQQW.

3/4. 11 RADIOACTIVE EFF LUENTS 3/4.11. 1 LIQUID EFFLUENiS........

3/4.11.2 GASEOUS EFFLUENTS

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11. 3 ID 0 IOA VE 5 i 3/4. 11. 4 T

Q 3/4. 12 RADIOLOGICAL ENVIRONMENTAL MONITORING LDIITS....

SECTION 3/4. 10 SPECIAL TEST EXCEPTIONS 3/4.10. 1 SHUTDOWN NRCIN...........................................

PAGE B 3/4 10-1 B 3/4 10-1 B 3/4 10-1 S 3/4 10-1 B 3/4 10"1 B 3/4 11-1 B 3/4 11-2 B 3/4 11-5 B 3/4 11-5 3/4.12.1 NI R

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S 3/4 12-1 8 3/4 12-1 B 3/4 12-2 SHEARON HARRIS - UNIT 1 XV1

INDEX ADMINISTRATIVE CONTROLS SECTION 6 ' '

CORPORATE NUCLEAR SAFETY SECTION PACE Funct Lon ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

6-11 0rganxzation...............................................'.

6"11 Revlev'

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6-12 Records.woo.o..o.....o.o.......o............................

6-13 6.5.4 CORPORATE QUALITY ASSURANCE AUDIT PROGRAM Audits ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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6-14 Records......................................

6-15 Authority..

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6-15 6 ~ 5 ~ 5 OUTSIDE ACENCY INSPECTION AND AUDIT PROCRAM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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6-15 6.6 REPORTABLE EVENT ACTION... ~.. ~. ~.oo..o...oo...

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6-15 6 ~ 7 SAFETY LIMIT VIOLATION~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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6-16 6 ~ 8 PROCEDURES AND PROGRAMS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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6.9 REPORTINC RE UIREMENTS 6-16 6.9.1 ROUTINE REPORTS'.

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6-20 Startup Report..............................................

Annual Reports. "..............................

6-20 6-20 Annual Radiological Environmental Operating Repo nnual Radioactive Effluent Release Report..

Monthly Operating Reports.......................

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6"21 6-22 6-23 Core Operating Limits Report..

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6-24 6.9.2 SPECIAL REPORTS'

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6-24 6.10 RECORD RETENTION.. ~....................................

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6"24 6.11 RADIATION PROTECTION PROCRAM.................

6-26 6.12 HIGH RADIATION AREA.... ~ ~. ~

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6-26 6.13 PROCESS CONTROL PROGRAM (PCP)..o

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~. ~ ~ ~ ooo 6-27 SHEARON HARRIS UNIT 1

XIX Amendment No.

INOEX AOHINISTRATIYE CONTROLS Sii.TION PAGc

6. 14 OFFSITE OOSE CALCULATION MANUAL OOCM.....................

6-27 6.15 MA R

C NGE TO

OUI, EOUS ANO SO 0

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(OElEff Dg'HEARON HARRIS - UNIT 1

DEFINITIONS MASTER RELAY TEST

1. 18 A MASTER RELAY TEST shall be the energization of each master relay and verification of OPERABILITY of each relay.

The MASTER RELAY TEST shall include' continuity check of each associated slave relay.

MEMBER S OF THE PUBLIC 1.19 MEMBER(S)

OF THE PUBLIC shall include all persons who are not occupa-tionally associated with the plant.

This category does not include employees of the licensee, its contractors, or vendors.

Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

This category does include persons who use portions of the site for recre-ational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL grsu4wy Asm 1.20 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contai the methodology and parameters used in the calculation of offsite doses radioac.ive I

gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Envi ron-mental Radiological Monitoring Program.

OPERABLE - OPERABILITY Spr$4'R T g 1.21 A system, subsystem, train, component or'device shall be OPERABLE or 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, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).

OPERATIONAL MODE - MODE 1.22 An OPERATIONAL MODE (i.e.,

MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.

PHYSICS TESTS 1.23 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation:

(1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE, 1.24 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault, in a Reactor Coolant System component body, pipe wall, or vessel wall.

SHEARON HARRIS - UNIT 1 1-4

INSERT 1 (on Page 1-4)

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 Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.3 and 6.9.1.4.

DEFINITIONS PROCESS CONTROL PROGRAM 1.25 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas,

sampling, analyses,

tesroii, and determinations to be made to ensure that i

processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a wa as to assure compliance with 10 CFR Parts 20, 61, and 71 and State regulations, burial ground requirements, and other require-men s governing the disposal of rad>oactive waste.

PURGE -

PURGING Solid 1.26 PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature,

pressure, humidity, concentration or other operating condition, in such

'a manner that replacement air or gas is required to purify the confinement.

UADRANT POWER TILT RATIO 1.27 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector cali-brated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.

With one excore detector inoperable, the remaining three detectors shall be used for computing the average.

RATED THERMAL POWER 1.28 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2775 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME 1.29 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE EVENT 1.30 A REPORTABLE EVENT shall be any of those conditions specified in Section

50. 73 of 10 CFR Part 50.

SHUTDOWN MARGIN 1.31 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

SITE BOUNDARY 1.32 For these Specifications, the SITE BOUNDARY shall be identical to the EXCLUSION AREA BOUNDARY defined above.

SHEARON HARRIS - UNIT 1

DEFINITIONS SLAVE RELAY TEST 1.33 A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERABILITY of each relay.

The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.

SOLIDIFICATION SOURCE CHECK

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Osfriia'go~ TE,Iu c~Z, Speci/ '"o~

~~~ ~~bc lid ro yAz pCP.

L.35 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

STAGGERED TEST BASIS 1.36 A STAGGERED TEST BASIS shall consist of:

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 othe~ designated component at the beginning of each subinterval.

THERMAL POWER 1.37 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TRIP ACTUATING DEVICE OPERATIONAL TEST 1.38 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating 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.

UNIDENTIFIED LEAKAGE 1.39 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

UNRESTRICTED AREA 1.40 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to wbich is not controlled by the licensee for purposes of protection o

individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, coaeercial, institutional, and/or recreational purposes.

SHEARON HARRIS - UNIT 1 1-6

INSTRUMENTATION RADIOACTIVE LIOUID EFFLUEHT MONITORING INSTRUMENTATION MITIHG CONDITION FOR OPERATIO 3.3.3.

0 The radioactive liquid effluent monitoring instrumentation ch nels shown i Table 3.3-12 shall be OPERABLE with the r Alarm/Trip Setpoin set to ensure tha the limits of Specification 3.11.1.1 are not exceeded.

he Alarm/

Trip Setpoin of these channels shall be determined and adjusted n accordance with the metho logy and parameters in the OFFSITE DOSE CALCULA ON MANUAL (QQCM).

APPLICABILITY:. At a times.

ACTION:

a.

With a radioactive

'quid effluent mon oring instrumentation channel Alarm/Trip Setpoint 1

s conservativ than required by the above specification, immediat (1) sus nd the release of radioactive liquid effluents monitore by th affected channel or (2) declare the channel inoperable and take C

ON as directed by b. belo~.

b.

With less than the minimu numbe of radioactive liquid effluent monitoring instrumentat' channel OPERABLE, take the ACTION shown in Table 3.3-12.

Exe best effort return the instrument to OPERABLE status wit n 30 days and, if nsuccessful, explain in the next, Semiannual R

ioactive Effluent Rel se Report pursuant to Specification 6

.1.4 why this inoperabili was not corrected in a timely mann c.

The provi sans of Specifications 3.0.3 and 3.0.4, re not applicable.

SURVEILLANCE EOUIREMEHTS 4.3.3.1 Each radioactive liquid effluent monitoring instrumentation annel shall e demonstrated OPERABLE by performance of the CHANNEL CHECK, SOUR CH, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TFST at the fre encies shown in Table 4.3-8.

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SHEARON HARRIS - UNIT 1 3/4 3-75

TABLE 3.3-12 RADlOACTIVE LI UID EFFLUEHT HotlITORltlG IHSTRUthftlTATIOH IHSTRUHEtlT l.

Radioactivity Ho tors Providing Alarm and Automatic Termination of Release a.

Liquid Radwaste Ef ent lines 1)

Treated Laundry and t Shower Tanks Discharge tlonit 2)

Maste Honitor Tanks and te Evaporator Conde te Tanks Discharge Honitor 3)

Secondary Waste Sample Tank Disch e

itor b.

Turbine Building Floor Drains Effluent ne c.

Outdoor Tank Area Drain Transfer P

ap tlonitor 2.

Radioactivity Honitors Providing arm Out Hot Providing hu atic Termination of Release a.

Hormal Service Water stem Return From Maste Processing Building to the Ci ulating Mater System b.

Hormal Servi Mater System Return From the Reactor Auxiliary Building t the Circulating Mater System 3.

Flow Rate asurement Devices t 11 HIHUt 1 CllhtlHELS OPERABLE ACTION 35 35 35, 36" 36 3T 39 a.

lquid Radwaste Effluent Lines 1)

Treated Laundry and Ilot Shower Tanks Discharge 2)

Maste Honi tor Tanks and Waste Evaporator Condensate Tanks Discharge I

38

TABLE. 3. 3-12 Continued)

RADIOACTIVE LI UID Ei:FLUENT liOHITORING IHSTRUt1ENTATIOH IHSTRUHEH 3.

Flow Rate surement Devices (Continued) 3)

Second Waste Sample Tank b.

Cooling Tower 01o own HININUN CilANNELS OPERMLE ACTION 38 "When the Secondary Waste System is being ed in the cont'ous release;mode, Action 36 shall be taken when the monitor is inoperable.

In the bate release de, Action 35 is applicable.

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TABLE 3. 3"12 Continued ACTION STATEMENTS ACTION With the number of channels OPERABLK less than required the Minimum Channels OPERABLE requirement, effluent releas via this pathway may continue provided that prior to init'ing a release:

ACTION 36-At least two independent samples are analyze in accordance with Specification 4.I1.1.1.1, and b.

At least two technically qualified membe s of the facility taff independently verify the release ate calculations a d discharge line valving.

Otherwis suspend release of radioac.i effluents via this pathway.

With he n

of channels OPERABL less than required by the Hinimum Channe s

OPERABLE requir nt, diffluent releases via this path~ay ma continue provid grab samples are analyzed for radioactivity at lower limit f detection of no more than 10-~ microCurie/ml ACTION 37-a.

At least once p

12 urs when the specific activity of the secondary coo an is greater than 0.01 microCurie/gram

~

OOSE E/UIVALENTI-, or b.

At least once pe 24 ours when the specifi,c activity of the secondary c olant less than or equal to 0.01 microCur

/gram 00 EQUIVALENT I-?3l.

With the number f channels OP BLE less than required by the Hinimum Channe OPERABLE requir ent', effluent releases via this pathway ay continue provided that, at least once per

?2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, gr samples are collecte and analyzed for radio-activity a a lower limit of detectio of no more than 10-~ micr Curie/ml.

ACTION 38-ACTION 39-With e number of channels OPERABLE les than required by the mini Channels OPERABLE requirement, ef uent releases via th'i pathway may continue provided the flow ate is estimated at east once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual rele es.

Pump perform-ce curves generated in place may be used to timate flow.

With the number of channels OPERABLE less than re uired by the Minimum Channels OPERABLE requirement, effluents r leases via this pathway may continue provided the weekly Cooli Tower Blow-down weir surveillance fs performed as required by 5 cifica-tion 4. L1.1.1.1.

Otherwise follow the ACTION specific in ACTION 37 above.

SHEARON HARRIS - UNIT 1 3/4 3-78

TABLE 4'-8 RADIOACTIVE LI UID EFFLUENT HONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS INSTRUHENT 1.

Radioactivity Ho tors Providing Alarm and Automatic Terms tion of Release CHANNEL CHECK SOURCE CHECK CHANNEL CALIBR ON DIGITAL CHANNEL OPERATIONAL TEST a.

Liquid Radwaste Eff nt Lines 1)

Treated Laundry and t Shower Tanks Discharge Honitor 2)

Waste Honitor Tanks and Waste Evaporator Condensate Tanks Discharge Honitor 3)

Secondary Waste Sample Tan Discharge Monitor b.

Turbine Building Floor rains Effluent Line c.

Outdoor Tank a Drain Transfer Pump Monito 2.

Radioactiv y Monitors Providing Alarm But No roviding Automatic Termination of ease P, H(5)

R(3)

R(3)

R(3)

R(3)

R(3) q(I) q(I) q(1) q(I) q(1) a.

Normal Service Water System Return From the Waste Processing Building to the Circulating Water System R(3)

~Il 4.

RADIOACTIVE Ll UID EFFLUENT HONITORING INSTRUHENTATION SURVEILLANCE RE UIREHENTS C)

IHSTRUHEHT 2.

W Radioactivity itors Providing Alara But Hot Providing tomatic Termination of Release (Continue 3.

Flow Rate Heasureient Devices a.

Liquid Radwaste Effluent Lines b.

Normal Service Mater stem Return From the Reactor Auxilia Building to the Circulating Mater Sy ea CIIANNEL CIIECK SOURCE CIIECK CIIANNEL CALIDRAlIOH R(3)

Dl AL ANNEL ERATIONAL TEST R(2)

D ICl 1)

Treated Laundry and Itot Shower Tanks Discharge 2)

Maste Honitor Tanks an aste Evaporator Condensa Tanks Discharge 3)

Secondary ste Saaple Tank b.

Cool Ing T er Slowdown D(4)

D(4)

D(C)

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

H.A.

N.A.

TABLE 4. 3-8 (Continued)

TABLE NOTATIONS (1) e DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that aut atic is lation of this pathway and control room alarm annunciation occu~ >f any f the following conditions exists:

a.

b.

I trument indicates measured levels above the Alarm/Trip etpoint, or

\\

Circus failure (monitor loss of communications (alar only), detector loss o

counts (Alarm only) or monitor loss of power

, or c.

Detector c eck source test failure (alarm only),

d.

Detectot chan el out of service (alarm only),

o e.

Monitor loss of ample flow (alarm only).

(2)

The DIGITAL CHANNEL OPE TIONAL TEST shall als demonstrate that control room alarm annunciation o curs it any of the ollowing conditions exists:

a.

Instrumeht indicates me sured levels ove the Alarm Setpoint, or b.

Circuit failure (monitor ss of c munications (alarm only), detector loss of counts, or monitor ss o

power), or c.

Detector check source test fai re, or d.

Detector channel out of ser ce, e.

Monitor loss of sample fl w.

(3)

The ini ial CHANNEL CALIBRA ON shall be pe ormed using one or more of the reference standards c tified by the Nati al Bureau of Standards (NBS) or using standards hat have been obtaine from suppliers that participate in measure nt assurance activities ith NBS.

These standards shall permit calibrat' the system over its inte

'ed range of energy and measurement range.

or subsequent CHANNEL CALIBRA ON, sources that have been related to th initial calibration'hall be use (4)

CHANNEL CHECK sh 1 consist of verifying indication of ow during periods of release.

C NNEL CHECK shall be made at least once pe 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which cont nuous, periodic, or batch releases are made.

(5)

Mhen the S

ondary Maste System is being used in the batch re ease

mode, the sourc check shall be prior to release.

Mhen the system i being used in the ntinuous release mode, the source check shall be monthl EARON HARRIS - UNIT 1 3/4 3-81 Amendment No.

~

I

~

~

INSTRUMENTATION FiAosiv GA BRS-VENT MONITORING IHSTRUMEHTATION LIMITING CONOITION FOR OPERATION E~ lOSdrVE 3.3.3.11 The gas monitorin instrumentation channels I

shown fn Table

.3-13 shall be OPERABLE w th their larm/Trip Setpoints set to ensure that the limits of Specificatfo 3.

an

3. ?1.2. 5 are not exceeded.

e A a r p e

o n s o

hese anne mee g Speci ication shall e det fned d adju ed in accor ance wi the m thodolo d pa te fn th OGCM.

APPLICABILITY:

As shown in Table 3.3-U ACTION:

a.

@tv zyu'.as'ith a>

gag~ effluent monitoring instrumentation channel arm/Trip Set oint less conservative than required b

the above specification mme a e s spen he r ease ra i ve seo eff ents onft ed b

the af ected ch nne or RZSTOar PAL parsps'AlhV

~&tOCAtOAI.'A7i~

dec are the channel rnooaraole and take ACTION a d r ShArOIuw iu tAhle J.8 N.

the Wfth the number of OPERABLE ga fnstrumentation channels less than the Mfnfmum Channe take the ACTION shown in Table 3.3-U.

5 to OPERABLE status within 30 days.. f c

e b

t monitoring s

OPERABLE, unsuccessful, PAEiMnfaudsukuti7 8 ~ldll]Fyeag A

+E @~I'ssgou c

pursuant to Speci fication why this fnope fifty was not corrected fn a timely manner.

g ArVrJ 49'4 ta spCoiu The provisions of Specfffcat ons..

and 3.o.4 are not applicable.

SURVEILLANCE RE UIREMEHTS E~4aavs 4.3.3.11 Each g

monftoring instrumentation channel shall be demonstrated OPERABLE b erformance of the CHANNEL CHECK CHANNEL CALIBRATION and A

N OP ON NALOG HANNEL OPERATIOHAL TEST at the requencfes shown fn able 4.3-9.

'f/tE Rdorj~~llvE GJISE'olla EFFLuswl irtsoiti>f~niug PO~Ti~~ uF 5P~<iFi~limu ~/j g.3.J4

/I ESH'u C(fkQSiCu TWV ~l >PE /

lorn 8 4/I S~ Ev IPZlO o p~ 00GN, SHEARON HARRIS - UNIT 1 3/4 3-82

EXPNZSVE TABLE 3.3" l3 GA S

F E

HONITOR ING INSlRUHENTATION Cl IN STRUHENT 1.

GASEOUS MASTE PROCESSING SYSTEH HYDROGEN AND OXYGEN ANALYZERS a.

Recombiner Outlet Hydrogen Honitor b.

Recombiner Outlet Oxygen Honitor c.

Compressor Discharge Oxygen Honitor TURBINE BUILDING VENT STACK a.

ble Gas Activity Honitor b.

Iodine ler c.

Particulate Saap d.

Flow Rate Honitor e.

Sampler Flow Rate Honitor 3.

PLANT VENT STACK a.

Noble Gas Activity Honitor HINIHUH CIIANNELS OPERABLE 1/recombiner 1/recowbiner APPLICABILITY ACTION 50 48 48 47 49 47 b.

C.

d.

e.

Iodine Sampler Particulat ampler F

Rate Honitor Sampler Flow Rate Honitor 49 46 PAGE 3/I' gP h"S kE>u ctELE/Eq.

TABLE 3.3-13 Continuegd RAOIDACTIVE CASFDUS EFFLUENT HDNITDRING INSTRUMENTATIDN C3 INSTRU NT 4.

WASTE PROCESSING ILOING VENT STACK 5 I

a.1 Noble Gas Activi Honitor (PIG) a.2 Noble Gas Activity Hon or (WRGH) b.

Iodine Sampler c.

Particulate-Sampler d.

Flow Rate Honitor e.

Sampler Flow Rate Honitor 5.

WASTE PROCESSING BUILOING STACK 5A a.

Noble Gas Activity Honitor h.

Iodine Sampler c.

Particulate Sampl d.

Flow Rate tor e.

Samp l Flow Rate Honi tor HINIHUH CIIANNELS OPERABLE APPLICABILITY HDO 1,2,3 CTIOH 45, 51 52 46 47 49 46

TABLE 3.3-13 Continued TABLE HOTATIOHS t

I t es.

During GASEOUS ASTE

+ pgocEs52uC

$(57Fm operation ACTION STATBIEHTS ACTION 45-(F07 c/SEOUL the number of channels OPERABI ~ less than required by inim annels OPERABt c requirement, the contents of wast gas decay s) may be released to the environ provided hat prior ta inc ting the release:

At least two indepe t sampl the tank's contents ar

analyzed, and At least two techn' qualifi embers of the facility staff indepen ly verify the release te calculations and dis e valve lineup.

the e,

suspend release of radioactive effluents via s

ACTION 46-er of channels OPERABLE less than'e

(

inimum Channels r

ent releases via his pattway ma ovsde is estimated ACTION 47-(] ~ us~op er o c anne s

ess an require inimum Channe requirement, e

eases via his pathway may continue

'amples are taken at least once s and these samples ed for ACTION 48-ACTION 49-(ear vsse)

Nth the number of channnels OPERABLE less than the Minimum Channels OPERABLE requirement, operation may continue provided grab samples are taken and analyzed at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> dur ing other aperations.

1 ber of channels OP RAB less than requi r Minimum Channe requQement, e

e eases via the affected pathway may conti samples are continuously ol Iected wi sampling equi pme uired in ACTION 50-Ctuo7 usfDJ ACTION 51-(HOT QSEO)

ACTION 52 "

With the number of channels OPERABl c ane less than required by

, the Minimum Channels OPERABLE requirement, suspend oxygen supply to the recombiner.

umber o

channels OPERABLE less than re ui e

Minimum Channe E requirement f e PIG and

WRGM, effluent releases via this continue provided grab samples are t east once per 12 hau ese samples.

ed for radioactivit within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SHEAROH HARRIS - UNIT 1 3/4 3-85

E~gyg GAs TABLE 4.3-9 NITORIHG INSTRUHCHTATIOH SURVEILLANCE RE UIREMEHTS IHSTRUHEHT M

lA 1.

GASEOUS WASTE PROCESSING SYSTEM-

/

IIYDROGEN AtID OXYGEN ANALYZERS CIIAHNEL CIIECK CIIAHtIEL CALIORAT ION w~acos

&Miffy CII L

OPERATIONAL TEST MODES FOR WIIICII SURVEILLANCE

~IS RE UlBED a.

C.

Recombiner Outlet Ilydrogen Monitor Recombiner Outlet Oxygen Monitor Compressor Discharge Oxygen Monitor Q(4)

Q(S)

Q(S) 2.

TURBINE BUILDING VENT STACK a.

C.

e.

e Gas Activity Iodine le r Particulate Sam r

Flow Rate Monitor Sampler Flow Rate Monitor N.h.

N.A.

N.h.

H.A.

N.h.

N.h.

R(3)

N.A.

N.A.

R Q(2)

H.h N.A.

Q 3.

PLAN1'EHT STACK a.

Hoble Gas Activity Monitor Iodine Sampler Particulate Sampler Flow Rate M

or Samp Flow Rate Monitor N.A.

N.A.

N.A.

N.A.

N.A.

H.A.

R(3)

A.

N. A.

R Q(2)

N.A.

N.A.

TABLE 4.3-9 Continuecl CiiANHEL SOURCE CHANNEL ClifCK ClifCK CALIAll~ATI0 R(3)

INSTRUHENT 4.

WASTE PROCESSING BUllD G VENT c

STACK 5

a. 1 Noble Gas Activity Honi.to PIG)

D DIGITAL CIIANNEL NODES FOR CII OPERATIONAL SURVEIL CE TEST IS UlRED r

I CD a.2 Hoble Gas Activity Honitor (WRGH) b.

Iodine Sampler c.

Particulate Sampler d,

Flo~ Rate Monitor e.

Sampler Floe Rate Honitor 5.

WASTE PROCESSING BUILDING VENT STACK 5A a.

Hoble Gas Activity Ho or b.

Iodine Saaplor c.

Particula Sampler d.

Flo ate Honitor e.

Sampler Floe Rate Honitor N.h.

N.A.

H.A.

H.A.

H.h.

N.

H.A.

N.A.

N.h.

N.A.

N.A.

R(3)

N. h.

R(3)

H. A.

H.A.

g(2)

N.A.

H.h.

H.A.

N.A.

TABLE 4.3-9 Continued TABLE NOTATIONS a '.

~ pgocr~sdnlG-p goring GASEOUSlASTE~

SYSTBI operation.

~AN G

NJB.

0 T

(1)

(NOfUSFOJ IGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that au c

isolats

. f this pathway and control room alarm annunciation if any of the follow conditions exists:

a.

Instrument indica measured levels above larplTrip Setpoint, or b.

Circuit failure (monitor los unications - (alarm only)', detec tor loss of counts (al only) oe mon loss, of power), or c.

Detec.or chec urce tes failure (alarm only, d.

Dete channel out of service (alarm only), or onitor loss of sa le flow (alarm onl )

(2) gnnf'sfog room b.

C.

GITAL CHANNEL OPERATIONAL TEST shall also demonstrate that con ala nunciation occurs if any of the following condit'xists:

Instrument in 's measured levels above th rm Setpoint, or Circuit failure (monitor of co cations (alarm only), detec-tor loss of counts, or mani of power), or Detector check so es failure, or Detecto nnel out of service, or nitor loss of s le flow.

(3) dfUSEOQ al CHANNEL CALIBRATION shall be performed using one or mo the reference rds certified by the National Bureau n ards (NBS) or using standa ave been obtai m suppliers that articipate in measurement assuran

~ties with NES.

These standards shall permit calibratin stem over its d range of energy and easurement r or subsequent CHANNEL CALIBRATION, that have be ed to the initial calibration shall be used.

(<)

The CHANNEL CALIBRATION shall include the use of standard gas samples containing hydrogen and nitrogen.

(5)

The CHANNEL CALIBRATION shall include the use of standard gas samples containing oxygen and nitrogen.

SHEARON HARRIS - UNIT j 3/4 3-88

I

~

~ I I

I

~

~

I

~

~

I I

I I l

~

~

~

I

~

I I

i)

I I

~

I

~

I I

I I

I I I

~

I ~,

~

I

)

~

I I

~

~

~

I

~

~ I

~

l

~

~

I

~

~

~

I I

I I ~

~

~

~

~

I I

I I

I I

I I

~

I

~

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TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID LEASE TYPE l.

Batch Was e

. Release Tanks(2) a.

Maste Monitor Tanks b.

Maste Evaporator Condensate Tank SAMP LING FREQUENCY p

Each Batch p

0 Batch/M p

Each Ba ch MINIMUM ANALYSIS FREQUENCY p

Each Batch M

Composite Principa).Gam Emitters' Sx10-7 I-131 lxl0-s Dissol ed and lxl0-s Entr ned Gases (Ga ma Emitters) 3 lxl0-s LOM LIMIT OF ETECTION TYPE OF ACTIVITY LD)(l)

ANALYSIS (pCi/ml )

c.

Secondary Maste Sample (8) d.

Treated Laundry and

Hot, Shower Tanks p

Each Batch mposit Gross Alpha Sr-89, Sr 90 Fe-55 lx"0-7 Sx10-a lxl0-s 2.

Continuous M

Rel eases

(

Conti nuou Composi te PrincipaI.Gamma Sx10-'mitzers a.

Cool i ng Tower Meir M(7 Gral ampl e D'ssolved and

~ml0-s En ained Gases (Ga a Emitters) b.

Secondary Maste Sample Tank(8)

I-"31 M

6 7

H 3 Continuous Composite Gross Alpha Sr 89, Sr 90 Continuous Composite Fe-SS lx10-6 lxl0"

'x10-7 Sx10-s 10-6 SHEARON HARRIS " UNIT 1 3/4 11-2 Amenoment

~

4

TABLE 4. 11-1 Continued)

TABLc NOTATIONS (1) Th LLD is defined, for purposes of these specifications, as the small s.

con ntration of radioactive material in a sample that will yield a

count, above system background, that will be detected with 95 prob ility with o y 5" probability of falsely concluding that a blank observ tion represen s a "real" signal.

For a parts ular measurement

system, which may include radioc mical separation:

Where:

4.66 sb

~ V

~

22 x 10' Y ~ exp (-hht)

LLO = the "a priori'ower limit of detec on (microCurie per unit mass or volume),

sb = the standard deviat on of the ba ground counting rate or of the counting rate of a bla k sample as appropriate (counts per minute),

E = the counting efficiency (c nts per disintegration),

V = the sample size (units mas or volume),

2.22 x 10' the number o

disintegr tions per minute per microCurie, Y = the fractional ra ochemical yield, when applicable, A. = the radioactive decay constant for th particular radionuclide (sec-~),

and At = the claps d time between the midpoint of Ie collection and the time of unting (sec).

Typical v ues of E, V, Y, and st should be used i the calculation.

It shouid he~recognized that tha LLO is defined as an a pr ri (before the fact) Hmit representing the capability of a measuremen~system-and not as an/a postariar$ (after the tact) limit d'or a particula+ measurement.

A bat n release is the discharge of liquid wastes of a discrete Iume.

Pri to sampling for analyses, each batch shall be isolated, and hen th ughly mixed by a method described in the OOQl to assure representative sampling.

SHEARON HARRES - UNlT 1 3)4 11-3

~

~

TABLE 4.11-1 (Continued)

TABLE NOTATIONS (Continued T

principal gamma emmiters for which the LLD specification applies (3) in ude the following radionuclides:

Hn-54, Fe-59, Co-58, Co-60,

-65, Mo-9

, Cs-134, Cs-137, and Ce-141.

Ce-144 shall also be measured ut with a

LLD f 5 x 10-s.

This list does not mean that only these nuc des are to be c nsidered.

Other gamma peaks that are identifiable, to ether with those of he above nuclides, shall. also be analyzed and repor ed in the Semiannual Radioac ive Effluent Release Report pursuant to ecifica-tion 6.9. 1.

in the format. outlined in Regulatory Guide l.

, Appendix B, Revision 1, ne 1974.

A composite samp e is one in which the quantity of li id sampled is (4) proportional to t quantity of liquid waste dischar ed and in which the method of sampling mployed results in a specimen at is representative of the liquids relea d.

A continuous release is he discharge of liqu'astes of a nondiscrete volume, e.g.,

from a volu e of a system that as an input flow during the continuous release.

(6)To be representative of the qu tities d concentrations of radioactive materials in liquid effluents, mples shall be collected continuously in proportion to the rate of flow o th effluent stream.

Prior to analyses, all samples taken for the composit shall be thoroughly mixed in order for the composite sample to be re e entative of the effluent release.

I (7)These points monitor potential release thways only and not actual release pathways.

The poten al contami tion points are in the Normal Service Mater (HSM) and Sec dary Maste (S

Systems.

Action under this specification is as follow :

a)

. If the applica e

(NSW or SM) monitor in Table 3.3-12 are OPERABLE aqd ot in alarm, then no ana sis under this specifica-tion is req red but weekly composites w ll be collected.

b) If the a

licable monitor is out of service then the weekly analysi for principal gamma emitters will b performed.

c)'f t applicable monitor is in alarm or if the rincipal gamma emi ter analysis indicates the presence of radio tivity as de-f ed in the ODCM, then all other analyses of this specification all be performed at the indicated frequency as lo as the initiating conditions exist.

(s) The econdary Maste System releases can be either batch or contin us.

The type of sample required is determined by the mode of operation b

ng used.

HEARON HARRIS - UNIT 1 3/4 11-4 Amendment No.

RADIOACTIVE EFFLUENTS DOSE LI TING CONDITION FOR OPERATION 3.11.1.

The dose or dose commitment to a MEMBER OF THE PUBLIC from ra oactive material in liquid effluents released to UNRESTRICTED AREAS (see Fig e 5.1-3) shall be imited:

a.

Du ing any calendar quarter to less than or equal to 1.

mrems to the hole body and to less than or equal to,5 mrems to any organ, and b.

During y calendar year to less than or equal to mrems to the whole bod and to less than or equal to 10 mrems any organ.

APPLICABILITY: At all times.

ACTION:

a ~

With the calculat dose from the relea of radioac.ive materials in liquid effluents exceeding any of t e above limits, prepare and submit to the Co ission within

days, pursuant to Specification 6.9.2, a Special Repo

~ that identi ies the cause(s) for exceeding the limit(s) and define the corr tive actions that have been taken to reduce the releases a

the p

posed corrective actions to be taken to assure that subs uen releases will be in compliance wi.h the above limits.

b.

The provisions of Specific i

s 3.0.3 and 3.0.4 are not applicable.

SuRVEIlLANCE RE UIREMENTS 4.11.3..2 Cumulative dose co ributions from li id effluents for the current calendar quarter and the cu rent calendar year s ll be determined in accordance with the methodology and rameters in the ODCM at least once per 31 days.

HEARON HARRIS - UNIT L 3(4 11-5

RAOIOACTIVE EFFLUEHTS IOUIO RAOWASTE TREATMENT SYSTEM LIMI HG COHOITION FOR OPERATIO 3.11.1.

The Liquid Radwaste Treatment System shall be OPERABLE and propriate portions f the system shall be used to reduce releases of radioacti ity when the projec d doses due to the liquid effluent, to UNRESTRICTEO AR S (see Figure 5.1-3 would exceed 0.06 mrem t'o the whole body or 0.2 m

to any organ in a 31-day p

iod.

APPLICABILITY: t all times.

ACTION:

a.

With radioa ive liquid waste being discharge without treatment, and in excess of e above limits and any porti of the Liquid Radwaste Treatment, Syst not..in operation, prepare nd submit to the Commis-sion within 30 s, pursuant to Specifi tion 6.9.2, a Special Report that includes the ollowing information l.

Explanation of y liquid radwa was being discharged wi hout treatment, ident ication of a inoperable equipment or subsystems, and th reason f the inoperability, 2.

Action(s) taken to r to the inoperable equipment to OPERABLE

status, and 3.

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

b.

The provisions of Specif cations

.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMEHTS 4.11.1. 3.1 Ooses due to 1'quid releases to UNRES ICTED AREAS shall be projected at least once per 31 day in accordance with the me odology and parameters in the OOCM when Liquid Ra aste Treatment Systems are n t being fully utilized.

4.11.1.3.2 The ins led Liquid Radwaste Treatment'Sys shall be considered OPERAB by meeting Specifications 3.11.1. 1 an 3.11.1.2.

HEARON HARRIS - UNIT 1 3/4 11-6

~

)

~

RAOIOACTIVE EFFLUENTS LIOUIO HOLOUP TANKS" LIMITING CONOITION FOR OPERATION 3.11.1.4 The quantity af radioactive material contained in each of the fallowing unprotected outdoor tanks shall be limited to less than or equal ta 10 Curies, excluding tritium and dissolved ar entrained noble gases:

a.

Outside.temporary tank, excluding demineralizer vessels and liners used to solidify or to dewater radioac ive wastes.

APPLICABILITY: At all times.

ACTION:

a.

'Nth the quantity cf radioactive material in any of the abave listed tanks exceeding the above limit, iaeediately suspend all additians of radioactive material to the tank, within. 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit an describe the events leading to this condition in the next nual Radioactive Effluent Release Report, pursuant ta Specifica ion 6.9.1.4.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the abave listed tanks shall be determined to be within the above limit by analyzing a

representative sample of the tank's contents within 7 days follawing any addition of radioactive material to the tank.

"Tanks included in this specification are those outdoor tanks that are nat surrounded by liners, dikes, or walls capable af holding the tank contents and that do nct have tank overflcws and surraunding area drains connected to the Liquid Radwaste Treatment System.

SHEARON HARRIS - UNIT 1 3/4 11-7

RAQIOACTIVE EFFLUENTS 3/4. 11.2 GASEOUS EFFLUENTS OOSE RATE LIMI rNG CONOITION FOR OPERATION

3. 11. 2. 1 e dose rate due to radioactive materials released in seous effluents fr the site to areas at and beyond the SITE SOUNOARY (see Figure

5. 1-1) shall b

limited to the following:

a.

For'obl gases:

Less than or equal to 500 mre

/yr to the whole body and l s than or equal to 3000 mrems/yr the skin, and For Iodine-131, for Iodine-133, for triti, and for a11 radio-nuclides in parts ulate form with half-ves greater than 8 days:

Less than or equal 1500 mrems/yr t any organ.

APPLICABILITY: At al 1 times.

ACTION:

With the dose rate(s) exceeding th above imits, immediately restore the release rate to within the above imit(s).

SURVEILLANCE RE UIREMENTS 4.11.2.1.1 The dose ate due to noble gases in gaseous ffluents shall be determined to be w'n the above limits in accordance wi the methodology and parameters i

the OOCM.

4.11.2.1.2 e dose rate due to Iodine-131, Iodine-133, tritium, and all radionucli s in particulate form with half-lives greater than 8

s in gaseous fluents shall be determined to be within the above limits accor ce with the methodology'nd parameters in the OOCM by obtainin repr sentative samples and performing analyses in accordance with the sa ling a

analysis program specified in Table 4.11-2.

/o~ya ~/+-7 fko~gP ~/u-Zt'~vs den d~(6f.

SHEARON HARRIS - UNIT 1 3/4 11-8

TABLE 4 ~ 11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM GASEOUS LEASE TYPE SAMPLING FREQUENCY HINIHUH ANALYSIS FREQUENCY TYPE OF ACTIVITY ANALYSIS LO LIMIT Of1 D

CTION (LLO)'1)

(pCi/ml) 1.

Waste Ga Storage Tank Conta nment Purge or Vent P

Each Tank Grab Sam le P

Each Tank Principal Gamma Emi rs (2)

Each PURGE Each PURGE (3)

(3)

Principal G

a Emitters (2) b Sample H-3 id lxlO-lxlO-~

lxlO-~

3.

a.

Plant Vent Stack b.

Turbine Bldg Vent Stack, Waste Pro-cessing Bldg Vent Stacks 555A 4.

All Releas'e Types as ljsted in l., 2.,

and 3.

above H3,,

5 Grab Sample H

Grab Sample Conti ous Continuous Continuous 6

Continuous (6 W

Charcoal Sample W

Particulate Sam le H

Composite Par-ticulate Sam le Q

Composite Par-ticulate Sample Pr cipal Gamma Emitters (2)

M-3 oxide Principal Gamma Emitters (2)

II-3 oxide Turb ne Bldg.

Vent Stack)

I-131 1-133 Principal Gamma Emitt s

2 Gross Alpha Sr-09, Sr-90 lxlO-+

lxlO e lxlO-~

lx10-lxlO-~~

lxlO io lxlO-'i lxlO-'

lxlO-

TABLE 4. 11-2 Continued TABLE NOTATIONS

(

Tne LLO is de ined, far purposes of these specifica ians, as. the small ncentration of radioactive material in a sample that will yield a n t c

nt, above system background, that will be detected with 95" prob ility wit only 5" probability of falsely concluding that a blank observ tion rep ents a "real" signal.

For a p ticular measurement

system, which may include radiac ical separati 4.66 sb E

~

~ 2.22 x 10' Y

~ exp (-Qt)

Where:

LLO = the "a pr ri" lower limit af detec i n (micraCurie per unit mass or volume),

sb = the standard d

iation af the bac round counting rate ar of the counting rate of a blank sample appropriate (coun.s per minute),

E = the counting efficien (cou per disintegration),

V = the sample size (units o

ass or volume),

2.22 x 10

= the number of isi egrations per minute per microCurie, Y = the fractional radi hemical y eld, when applicable, A, ~ the radioactive ay constant fo the'articular radianuclide (sec-~),

and At = the elapse time between the midpairst of sample collec.',on and the time of co ting (sec).

Typical val s of E, Y, Y, and ht should be us d in the calculation.

Et should be cognized that the LLD is defined as an oriori (before the 1'act) 1i it representing the capability os a measu nt system and not as an gosteriori (aster the tact) limit sor a parr ular.measurement o

EARON HARRIS - UNIT 1 3/4 11-10

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TA8LE 4. Ll-2 Continued TA8LE NOTATIONS Continued) e pr inc',pal gamma emitters for which the LLD specificatiorf apolies i

lude the following radionuclides:

Kr 87, Kr 88, Xe-133, Xe-133m Xe-5, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58,

-60, En-6 Ma-99, I-131, Cs-134, Cs-137, Ce-141 and Ce-144 in Iodine nd partic late releases.

This list does not mean that only these n

lides are to be c sidered.

Other gamma peaks that are identifiable, to ether with those of he above nuclides, shall"also be analyzed and repar ed in the Semiannual adiaactive Effluent Release Report pursuant tc ecifica.ion 6.9.1.4 in e format outlined in Regulatory Guide 1.21, pendix 8, Revision 1, J e 1974.

Sampling and ana sis shall also be perfarmed followi g shutdown, startup, or a THERMAL POWER change exceeding L5~ of RATED TH

. MAL POWER within a 1-hour period.

Tritium grab samples sh ll be taken at least o

e per 24 haurs when the refueling canal is flood

("'Tritium grab samples shall b

taken at le once per 7 days from the ventilatian exhaust from the ent fuel ol area, whenever spent fuel is in the spent fuel pool.

The ratio of the sample flow rate the sampled stream flow rate shall be known for the time period covered each dose or dose rate calculation made in accordance with Specific ion 3.11.2.1, 3.11.2.2, and 3.L1.2.3.

Samples shall be changed at 1 ast once p

7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af er changing, r after removal from sampler.

Sampling shall also be per rmed at least o

e per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shu down, startup, or ERMAL POWER change exceeding L5X of RATED THERMAL PO R within a 1-haur per'ad and analyses shall be completed within 48 ho s of changing.

When s

les collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the co esponding LLDs may be incre sed by a factar of LO.

This requirement do not apply if:

(1) analysis ows that the DOSE EQUIVALENT 1-131 c ncentration in the reactor caola has nest increased more than a fac of 3; and (2) the noble gas monito shows that effluent activi has nct, increased more than a factor f 3.

EARON HARRIS - UNIT 1 3/4 11-11

RAOIOACTIVE E;"FLUE, OSE - NOBLE GASES L<i".. ING CQNQITIQN FQR OPERATION 3."'.Z.

The air dose due to noble gases released in gaseous ef luents o

areas at nd beyond the SITE BOUNGARY (see Figure 5.1-3) shall be limi d to the folio ng:

a.

Du 'ng any calendar quarter:

'Less than or equal to 5 mr ds for gamm radiation and less than or equal to 10 mrads for eta radiation, and b.

Ouring a calendar year:

Less than or equal to 1 mrads for gamma.

radiation nd less than or equal to 20 mrads for eta radiation.

" APPLICABILITY: At all times.

ACTION With the calculate air dose from radioa ive noble gases in gaseous effluents exceeding any of the above I'ts, prepare and submit to the Commission withi 30 days, pursua to Specification 6.9.2, a

Special Report that i ntifies the use(s) for exceeding the limi (s) and defines the correct've actions hat have been taken to reduce the releases and the pro sed cor ective actions to be, taken to assure that subsequent rel ases ill be in compliance with the above limits.

The provisions of Specific io s 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIRENENTS 4.U..2.2 Cumulative dose can ributions for the urrent calendar quarter and current calendar year for n le gases shall be de ermined in accordance with the methodology and parame ers in the OOC4l at Ieas once per 3'ays.

EARON HARRIS - UNIT 1 3/4 11-12

O SE - IODINE-131. IODINE-133 TRITIUM, ANO RADIOACTIVE MATERI A

ICULAr E QRM LIMITI CONDITION FOR OPERATiON 3.11.2.3 e dose to a MEMBER OF THE PUBLIC from Iodine-131, Iadine-3, tritium,'n all radionuclides in particulate form with half-lives g ater than 8 days i gaseous effluents released to areas at and beyond th SITE BOUNDARY (see gure 5.1-3) shall be limited to the following:

a.

During y calendar quarter:

Less than or equal to 7.5 mrems to any organ an b.

During any lendar year:

Less than or equal to mrems ta any organ.

APPLICA8ILITY: At all ti s.

ACTION:

With the calculated d

e, from the rel ase of Iodine-131, Iodine-133, ritium, and radionucI>

es in partic ate form with half-lives greater than 8 days, in seous eff uents exceeding any of the above limits, prepare and submi the th Commission wi.hin 30 days, pursuant to Specification

6. 9.2, a

ecia Report that identifies the cause(s) for exceeding the limit(s) a efines'the carrective actions that have been taken ta reduce the rele es and the proposed corrective actions to be taken ta assure that s

s quent releases will be in compliance with the above limits.

b.

The pravisians of'Specif cations 3.

3 and 3.0. 4 are not applicable.

SURVEILLANCE RE UIRBIENTS 4.U..2.3 Cumulative dose ontributions for the curre t calendar quarter and current calendar year fo Iodine-131, Iodine-H3, trit and radianuclides in particulate form wi half-lives greater than 8 days hall be determined in accordance with th methodology and parameters in the CM at least once per 31 days.

HEARON HARRIS - UNIT 1 3/4 11-13

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RAOIOACTIVE =FFLU GASEOUS RADWAST"= TREATMENT SYSTBf LL ~TING CONOITICN FOR. OPERATION 3..2.4 The VENTILATION EXHAUST.TREATMENT SYSTBl and the GASEOUS RA ASTi TREATISE.

SYSTBl shall be OPERABLE and appropriate portions of these systems shall be sed to reduce releases of radioactivity when the praject doses in 31 days du ta gaseous effluent releases to areas at and beyond e SITE BQUN-OARY (see Fi ure 5.1-3} would exceed:

a.

Q.2 ad ta,air from gamma radiation, or b.

0.4 mra ta air fram bow radiation, or c.

0.3 mrem any organ of a HBSER QF THE PUBL i.

APPLICABILITY: At al 1

'mes.

ACiIQN:

a.

Wi.h radioactive ga caus waste being ischarged without tr atmen-and in excess ot the bave limits, repare and submit to the Commission within 30 s, pursua to Specification 6.9.2, a

Special Report that inc des the following information:

1.

Identification af any in erable equipment or subsystems, and the reason for the ino

rability, Z.

Action(s} taken to r sta the inoperable equipment ta OPERABLE

status, and 3.

Suaaary descrip on of action

) taken ta prevent a recurrence.

b.

The provisions of pecifications 3.0.

and 3.0.4 are not applicable.

SURVEILLANCE REOUI RENE 4.U..2.4.1 Oases d

ta gaseous releases to areas at beyond the SITE BOUNOARY shall be jected at leas ance per 31 days in cordance with the methodology and p rameters in the QOQI when the GASEOUS ASTE TREATMENT SYSTEM is not b ng fully utilized.

4; 11 2.4.2 e installed VENTILATION EXHAUST TREATMENT SYSTEM nd GASEOUS RAOWASTE TR THENT SYSTBI shall be considered OPERABLE by meatin Specifica-tians 3.

2.1 and 3.11.2.2 or 3.1'.2.3.

SHEARON HARRIS - UNITI 3/4 0 14

RAOIOACTPIE E'rLUEHTS GAS STORAGE TANKS LIHITIHG CONOITION FOR OPERATION 3.?1.2.8 The quahtfty af radioactivity contained in each gas sta<<ge tank sha11 be limited ta less than ar equal ta LOS x 10'uries af nable gases (cansf dered as Xe-I33 equivalent).

APPLICABILTTY: At all tfmes.

ACTION Nth the quantity of radioactive material in any gas storage exceeding the above limit, immediately suspend a7l addftfans af radioactive material ta the tank, vfthfn 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents ta %thin the 1 mit, and describe the events leading ta this candftion in the next al Radioactive Effluent Release Repar.",

pursuant to Speci ffcatfan G.S.44.

The pravisians af Specfffcatfans 3.0.3 and 3.0.4 are nat appl.fcable.

SURYEILLANCE REQUIREHEHTS

-4.XL'2.6 The quantity af radioactive material contained in each gas storage

'.tank sha11 be determined to be %thin. the above lfmftat least ance per N

'ours &en radioactive materials are being added ta.the tank.

QEARQQ HARRtC QN&1 3/4 ~D XS

RADIOACTIVE EFFi IJEN I S 3/4. 11. 3 SOLID RADIOACTIVE WASTES LIMITING CONDITION FOR OP RATION 3.1 3

Radioactive wastes shall be solidified or dewatered in accordance w

h the P

CESS CONTROL PROGRAM to meet shipping and transportation requireme s

during

ansit, and disposal site requirements when received at the dis sal site.

APPLICABILITY: At al 1 times.

ACTION:

With SOLIDI CATION or dewatering. not meeting posal site and shipping and ansportation requirements, sus end shipment of the inadequately p

essed

~astes and correct e

PROCESS CONTROL PROGRAM, the procedures, a

or the Solid Waste Sy em as necessary to prevent recurrence.

b.

C.

With SOLIDIFICATION or watering performed in accordance with the PROCESS CONTROL PROG

, tes the improperly processed waste in each container to ensure th t meets burial ground and shipping requirements and take approp 'ate administrative action to prevent recurrence.

The provisions of Spec'cations 3..3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.U..3 SOLIDIFICATIO of at least one representative t specimen from at least every tenth b

h of each type of wet radioactive tas (e.g., filter

sludges, spent re ns, evaporator bottoms, boric acid solut ns, and sodium sulfate solutio

) shall be verified in accordance with the CESS CONTROL PROGRAM:

a.

f any test specimen fails to verify SOLIDIFICATION, the OLIDIFICATION of the batch under test shall be suspended until such time s additiona test specimens can be obtained, alternative SOLIDIFICATION p ameters can be determined in accordance with the PROCESS CONTROL PROG and a subsequent test verifies SOLIDIFICATION.

SOLIDIFICATION o the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM; axiom'g ga/ocelot'4 fo Pzpz

~/e J~-l8 g~~ 8~~iv ds(WiZ.

SHEARON HARRIS - UNIT 1 3/4. Q-17

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RADiOACTIVE Er FLUENTS OLID RADIOACTIVE WASTES SUR'LLANCE REQUIREMENTS Continued

4. 11. 3 Continued) b.

C.

f the initial test specimen from a batch of waste fails verify S

IDIFICATION, the PROCESS CONTROL PROGRAM shall provi for the col ection and testing of representative test specimen from each cons utive batch of the same type of wet waste until at least three consec tive initial tes specimens demonstrate SOLI FICAiiON.

The PROCESS ONTROL PROGRAM shall be modified as requi ed, as provided in Speci cation 6.13, to assure SOLIDIFICATION subsequent batches of waste; d

With the inst lied equipment incapable of me ing Specification 3.11.3'or decl ed inoperable, restore the uipment to OPERABL=

status or provi for contrac capability process wastes as necessary to sati fy all applicable tran ortation and disposal requirements.

RON HARRIS - UNIT 1 3/4 11"LS

RAOIOACTIYE -"FFLUEN ~

3/4.11.4 TOTAL OOSE

~MITING CONOiTION FOR OPERATION 3.1 4

The annual (calendar year) dose or dose commitment to any MEMBER OF THE P

LIC due to releases of radioactivity and to radiation from uranium uel cycle urces shall be limited to less than or equal to 25 mrems to the ole body or y organ, except the thy~id, which shall be limited to less an or equal to mrems.

APPLICABILI At all times.

ACTION:

a 0 b.

With the lculated doses from the release of radi active materials in liquid o gaseous effluents exceeding twice t e limits of Specifi-cation 3.U..

2a., 3.11.1.2b.,

3.11.2.2a.,

3.

.2.2b., 3.11.2.3a.,

or 3.11.2.3b

, ca ulations shall be made inclu ng direct radiation contributions f m the units and from outsi storage tanks to deter mine whether the ove limits of Specific ion 3.11.4 have been exceeded.

If such

's the case, prepare nd submit to the Commission within 30 days, purs nt to Specificat n 6.9.2, a Special Report that defines the corre tive action to e taken to reduce subsequent releases to prevent rec rence of ceding the above limits and includes the schedule for chievi conformance with the above limits.

This Special

Report, as de 'ned 10 CFR 20.405(c), shall include an analysis that estimates the ation exposure (dose) to a MEMBER QF THE PUBLIC from uranium fuel cle sources, including all effluent pathways and direct radiati r the calendar year that includes the release(s) covered by is re ort. It shall also describe levels of radiation and concent tions of adioactive material involved, and the cause of the expos levels or ncentrations.

If the estimated dose(s) exceeds the ove limits, and f the release condition result-ing in violation of CFR Part 190 has ot already been corrected, the Special Repor shall include a reques for a variance in accor dance with the p visions of 40 CFR Part Submittal of the report is considered timely request, and a varian e is granted until staff action on the request is complete.

The provis ons of Specifications 3.0.3 and 3.0.4 re not applicable.

SVRYEILLANCE RE IREMENTS

4. 11.4. 1 C

ulative dose contributions from liquid and gaseous eff ents shall be termined in accordance with Specifications 4.11.1.2, 4.11+.2, and 4.11.2.3 and in accordance with the methodology and parameters in the'QDCM.

4.11.

.2 Cumulative dose contributions from direct radiation from the un s

and rom radwaste storage tanks shall be determined in accordance with the odology and parameters in the OOCM.

This requirement is applicable only der conditions sat forth in ACTION a. of Specification 3.Q.4.

SHEARON HARRIS. - UNIT 1 3/4 11-19

3/<. U RAOIOLQGIC NVIRONHENTAL MONITORING 3/4. 2.1 MONITORING PROGRAM LIH.>NG C"NO:7 ON FOR OPERATION 3.12.1 Radiological Environmental Monitoring Program shall be con cted as specific in Table 3.12-1.

APPLICABILITY: t all imes.

AC i ION:

a.

With the Rad logical Environmental Honitaring ogram not being conducted as s

cified in Table 3.12-1, prepa and submit ta the Commission, the Annual Radiological vironmental Operating Report required by pecification 6.9.1.3, descriptian of the reasons for not conducting program as requi d and the plans for preventing a recurrence.

b.

With the level of radioact'ty a

the result of plant effluents in an environmental sampling me i at a specified locatian exceeding the reporting levels of Table 12-2 when averaged over any cale.;car

quarter, prepare and submit o t Commission within 30 days, pursuan-to Specification 6.9.2, a

ecial eport that identifies the cause(s) for exceeding the limit and defin s the corrective actions ta be taken to reduce radioa ive effluents o that the potential annual dose" ta a HEHBER OF E PUBLIC,is less an the calendar year limits of Specifications

.D.1.2, 3.11.2.2, or 11.2.3.

When mare than one of the radio clides in Table 3.12-2 a

detec ed in the sampling medium, this r ort shall be submitted if:

conc tration 1

concentration 2

+

rep sng eve reporting eve When dianuclides other than those in Table 3.L?-2 are etected and are he result of plant effluents, this report shall be s

mitted if t

potential annual dose" to a HEWER OF THE PUBLIC from a I radio-uclides is equal to or greater than the calendar year limit af Specification 3.11.1.2, 3.11.2.2, or 3.U..2.3.

This report is ot required if the measured level of radioactivity was not the resu "

of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.3.

c I IfjdP /g gg gP ly (g p p~J Zf~'pe'~ ~ Yr ~re/+g+g+~+Nw gF Spra~ibfjak gud'Z<afzJ'~ rk ODCA sag po7-g TApoop) 9/g gg -$5! ggyr gg

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e meth ology an arameter use o

1mate t po en I annua se to a HBS OF THE P

LIC shall e indic ed in th report.

SHEARON HARRIS - UNIT' 3/4 12-1

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RAG IOLOGICAL ENVI.

ENTAL MONITORING ITORING PROGRAM L.~I 9G CONG TION FOR OP RAT.QN ACTION C.

ontinued):

W 'h milk or fresh leafy vegetation samples unavailable om one or mor of the sample locations required by Table 3.12"1, dentify spec fic locations for obtainingreplacement samples d add them withi 30 days to the Radiological Environmental Hon'ring Program given i he 00'.

The specific locations from wh h samples were unavail le may then be deleted from the moni.ori g program.

Pursuant to Specift ation 6.14, submit in the next Semia ual Radioac ive Effluent Re ease Report documentation for a ch nge in the 00CN including a vised figure(s) and table for e

COCA reflecting the new location(s with supporting information dentifying the cause o

the unavailabil ty of samples and justifyi,g the selection of the new loca ion(s) r obtaining samples.

d.

The provisions of S ecifications 3.0.

and 3.0.4 are not applicable.

SURVEILLANCE REOUIRBIENTS

4. 12;1 The radiological environment nitoring samples shall be collected pursuant to Table 3.12"1 from the spec'c locations given in the table and figure(s) in the GOD, and shall be a

zed pursuant to the requirements of Table 3.i&-1 and the detection cap lit> s required by Table 4.12-1.

SHEARON HARRIS - UNIT 1 3/4 12-2

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--I EXPOSURE TIIWY AND/OR SAH 1.

Direct Radiat TABLE 3.12-1 RADIOLOGICAL ENVIRONHENTAL HONITORING PROGRAN" NADER OF REPRESENTATIVE SAHPLES AND SAHPLING AND SAHPLE LOCATIONS~

IIE II%

"EIIIIEIII Forty routine moni toring stations quarterly.

either with two or more dosimeters or with one Instrument for suring and recording dose rat continuously, placed as fo1 low An inner ri of stations, one in each oeteorolo cal sector in the ge>>eral area of t SITE BOUtIDARY; An outer ri>>g of stati, one in each meteorological secto in the 6-to 8-km range from t site; and The balance of the sta ons to be placed in spe al interest areas such as po ation centers, nearby residen

, Schools, and in one or t areas to serve as control ations.

TYPE AND f qUENCY OF A

YSIS G

a dose quarterly.

TABLE 3. 12-1 Continued RADIOLOGICAl. EHVIROXHENTAL HOHITORIHG PROGRN EXPOSURE Phl Y

AXD/OR SANPLE 2.

Airborne Radioiodine and Particulates NUHOKR OF REPRESENTATIVE SAHPLES AXD SAW t.E LOCATIONS( )

Samp>es from five locations:

Thte amples from close to the ee SITE BOUNDARY locations;.

n different

sectors, of t highest calculated annua average ground-level 0/Q; One sample from the vicinity of a community having the highest calcu-lated annual average grou level 0/g; and One sample from a ontrol

location, as f example 15 to 30 km dista and in the least prevalen ind direction.

- SAHPLING AXO COLLECTIOH FRE UEHCY Continuous sampler oper-ation with sample collec-tion weekly or more frequent'ly )f require y

dust loading.

TYP5 AXO EgUENCY OF ALYSIS dioiodine Cdnnistel".

ana ys s wee ly.

Particulate Sa Ter:

ross e

a ra oactivity analys is fo1 lowing filter change; and (3) ganna isotopic analysis of c9mposite (by location) quarter ly.

3.

Materborne a.

Surface One sample upstream.

One sample downstream.

Composite sample over I-month period. (6) b.

Gr d

Samples from one or two sources quarterly.

only if likely to be affected(

Gaeaa isotopic analysis (4) thly.

Cbiposite for trit analysis quarterly.

Gawiia iso ic and

(<)

tritium anal s quarterly.

TABLE 3.12-1 Continued EXPOSURE TIINY AHD/OR SAM 3.

Materborne SNPLIHG AND COLLECTION FRE UEHCY RAOIOLOGICAL ENVIRONHENTAL HONITORIHG PROGRN HUHDER OF REPRESENTATIVE SAHPLES ANO SAW i.E l.OCATIONS ntinued)

TYPE AN REqUEHCY 0

HALYSIS c.

Orinking d.

Sediment from Shoreline One sample in the vicinity the nearest downstream eu ipal water supply intake from e Cape Fear River.

One sample om a control location.

One sample in the vicinity the cooling tower blowdo discharge in an area h

existing or potent recreational value.

Composite sample over 2-week period whe 1-131 analysis is formed; monthly om-posite othe se.

Semiannually.

I-131 analysis on each composite when the dose calculated for the con-sumption of the water ls greater than 1 mrem per year Composite (8) for gross beta and gamma isotopic analyses (4) eonthly.

Composite for tritium analysis quarterly.

Gaeaa isotopic analysis semiannually.

Ingestion a.

Hilk Samp from milking anieal s hree locations within 5 ke stance having the highest dose potential.

If there are none, then one sample from milking animals in each of three areas between 5 to 0 km distant where doses are calculate]n)o be greater

.than I mrem per yr.

One sample from milking anieals at a control location 15 to 30 km distant and in the least prevalent wind direction.

Semiebnthly when anieals are on pastur

'onthly at othe) times.

Genoa tsotoptc and 0

1-131 analysis semi-monthly when animals are on pasture; monthly at other times.

TABLE 3.12-1 Continue RADIOLOGICAL ENVIRONMENTAL HONITORIHG PROGRAM EXPOSURE PA AY AND/OR SAMPL NUMBER OF REPRESENTATIVE SAMPLES AHO SAMPLE LOCATIONS SAMPLIHG AND COLLECTION FRE UENCY TYPE A FREqUENCY ANALYSIS 4.

Ingestion (Cont ed) b.

Fish and Inverte-brates c.

Food Products sample of Sunfish, Cat-fis

, and Large-Mouth Bass species n vicinity of plant discharge ea.

One sample of me species in areas not fnfluen d by plant discharge.

Samples of three differen kinds of broad leaf vegeta-tion gro~n nearest each. of two different offsite lo tions of highest predf ed annual average grou level 0/g if milk samp ng is not performed.

One sam of each of the simil broad leaf vegeta-tf grown 15 to 30 km dis-ant in the le'ast prevalent wind direction ff milk sam-pifng is not performed.

Sample in season, or semiannually if the are not seasonal.

onthly during growing season.

Monthly during growfng season.

-Gamma fsotopfc analysis (4) on edible portions.

Gama f~otopfc and I 13L analysfs.

Gaena isotopic 'nd I"131 (Ql analys is.

TABLE 3. iU-1 Continued TABLE NOTATIONS (2)

(3)

Specific parameters of dis:ance and direction sec or from the center ne f one reactor, and additional description where pertinent, shall b

pro-v ed for each and every sample location in Table 3.U.-1 in a tab and fi re(s) in the OQCM.

Refer to NUREt -OI33, "Preparation of Rad'ological Eff1 nt Technical Specifications for Nuclear Power Plants,"

0 ober %78, and Radiological Assessment Branch Technical Position, Rev'sion 1, Novembe U79.

Oeviations are permitted from the required s

ling

.schedule f specimens are unobtainable due to circumstance such as hazardous onditions, seasonal unavailability, and malfu ion of auto-matic sampI g equipment.

If specimens are unobtainabl due to sampling equipment ma unction, effort shall be made to complet corrective action prior to the e

of the next sampling period.

All d iations from the sampling schedu shall be documented in the Annual adiological Environ-mental Operating eport pursuant to Specification

.8.1.3. lt is recog-nized that, at tim

, it may not be possible or'ac~icable to continue to obtain samples of ".n media of choice at the m

t, desired location or time.

In these instances su'table 'alternative media and locations may be chosen i'or the particular pat ay in question and propriate subs itutions made within 30 days in the Ra iologicaI'nviron nta1 Monitoring Program.

Pur suant to Speci ication 6.

, submit in t next Semiannual Radioactive Effluent Release Report do mentation f a change in the OOCM including a revised figure(s) and tabl for the CM reflecting the new location(s) with supporting information i ntify g the cause of the unavailability of samples for that pathway an us ifying the selection of the new loca-tion(s) for obtaining samples.

One or more instruments, such a

ssurized ion chamber, for measuring and recording dose rate conti uously y be used in place of, or in addi-tion to, integrating dosime rs.

For e purposes of this table, a

thermoluminescent dosimete (TLO) is co idered to be one phosphor; two or more phosphors in a p ket are conside as two or more dosimeters.

Film badges shall not b used as dosimete for measuring direct radiation.

(The 40 stations is no an absolute number.

The number of direct radiation monitoring stations y be reduced according geographical limitations; e.g., at an ocean s',

some sectors will be o r water so that the number of dosimeters may e reduced accordingly.

The quency of analysis or readout for TLD stems will. depend upon the char ristics of the speci-fic system use and should be selected to obtain o

imum dose information within minima fading.)

.Airborne p iculate sample filters shall be analyzed r gross beta

-radioacti ity 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-or more after sampling to allow f r radon and thoron ughter decay.

If gross beta activity in air pa culate samples is gre ter than 10 times the yearly mean of control samples gamma isot ic analysis shall be performed on the individual sampl G

i<otopic analysis means the identification and quantifica ion of amna-emi'tting radionuclides that may be attributable to the eff ents from the facility.

SHEARON HARRIS - UNIT 1 3/4 Z2-7

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TABL."- 3. I2-I Cont inued)

TABL=" NQTATIQNS Continued (S) he "upstream sample" shall be taken at a dis ance beyond significant i

luence of the discharge.

The downstream" sample shall be taken n an are beyond but near

.he mixing zone.

"Upstream" samples in an es ary mus e taken far enough upstream to be beyond the. plant influen Sal water hall be sampled only when the receiving water is utilize for recreat'onal ac.ivities.

(o)

A composit sample is one in which the quantity (aliquot) o liquid sampled is proporti al to the quantity of flowing liquid and in ich the method of sampling ployed results in a specimen that is repre entative of the liquid flow.

his program composite sample aliquot shall be collec ed at time interva that ar very short (e.g., hourly) lative to the ccmpositing perio (e. g., monthly) in order to assur obtaining a

representative s

le.

(7)

Groundwater samples s all be taken when this so ce is tapoed for drinking or irrigation purposes n areas where the hydr ulic gradient or recharge properties are sui'table or contamina ion.

(8)

The dose shall be calculate for the maxi m organ and age group, using the methodology and paramete s in the 00 SHEARQN HARRIS - UNIT 1 3/4 12-8

tel Rl C3 TABLE 3. 12-2 REPORTING LEVELS FOR RADIOACTIVITYCONCENTRATIONS IH ENVIROHHEHTAL SAHPLES

~

ANALVSIS ll-3 MATER (pCi/I) 2

, oo*

AIRBORNE PARTICULATE OR GASES (pCI/ma)

FISll (pCi/kg, set)

HILK (pCi/I)

FOOD PRODUCTS (pCi/kg, Met)

~ ~f-I

~D Hn-54 Fe-59 Co-50 Co-60 Ln-65 ir-Nb-95 1-131 Cs-134 Cs-137 Da-La-140 1,000 400 1,000 300 300 400 2@A 30 50 200 0.9 10 30,000 10,000 30,000 10, 20,000 2,000 6o 70 300 100 1,000 2,000

• for drinking eater s

les.

This is 40 CFR Part 141 value.

If no drinking eat athway exists, a value of 30,000 pCi/I m e used.

"*Iifno drinkin ater pathway exists, a value of 20 pCi/l way be used.

f'll Xt C3 TNLE 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SlNPLE ANALYSIS LOMER LIHIT OF DETECTION LLD ( )

MA s

ANALYSIS (pCI AIROORNE PAR I ICULATE FISll HILK OR GASES (pCI/e3)

(pCI/kg, wet). (pCI/I)

FOOD P

UCTS SEDIHENT (pC g, set)

(pCi/kg, dry)

I

~

-1 l

I ED Gross Octa ll-3 Hn-54 Fe-59 Co-58,60 7.n-65 7r-Nb-95 I-131 Cs-134 Cs-137 Oa-La-140 2000" 15 30 15 30 15 15 18

0. 01

.07

0. 05

0. 06 130 260 130 130 150 15 18 15 60 80 150 180 "If no dri ng eater patlway exists, a value of 3000 pCI/1 may be.used.

"*Ifn rinking eater path~ay exists, a value of 15 pCI/1 may be used.

TABLE 4. 12-1.

Continued TABLE NOTATIONS (1

his lis does not mean that only these nuclides are to be con@dered.

her peaks tha: are iden ifiable, together wi.h those o

the above nu lides, shall also be analyzed and reported in the Annual Radiologi al Envi onmental Operating Report pursuant to Specification 6.9.1.3.

(2)Requir detec ion capabilities for thermoluminescent dosimeters sed for envs onmental measurements shall be in accordance with the commenda" tions of egulatory Guide 4.13-.

(3)The LLO is fined, for purposes of Nese specifications, a

the smallest concentration oi radioac.ive material in a sample that wil yield a net

count, above s

tern background, that will be detected wi

. 9~ probabi li y with only ~" pro ability of falsely concluding that a b ank observation represents a "rea " signal.

For a par.icular mea urement

system, which may incl de radiochemical separation:

Where:

LLO =

E

~

V 4.66 sb

~

22

~

Y exp(-

t)

LLO

= the "a priori" lower

'mit of tection (picoCuries per unit mass or volume),

sb

= the, standard deviation of e background counting rate or of the counting rate of a blank le as appropriate (counts per minute),

E

= the counting efficien (coun per disintegration),

V

= the sample size (un of mass o

volume),

2.22 = the number of di ntegrations per m'nute per picoCurie, Y

-" the fractional radiochemical yield, w

n applicable, A,

= the radioac ive decay constant for the p

icular radionuclide (sec->),

d bt

. = the el sed time between environmental colle ion, or end of the s

le collection period, and time of coun ing (sec).

Typical v ues of E, V, Y, and ht should be used in the alculation.

EARON HARRIS - UNIT 1 3/4 X2-11

TABLE 4. 12-I Con.inued TABLE HOTATIONS Continued t should be recognized that the LB is defined as an a oriori (before " e ct) 'limit representing the capability of a measurement sysrem and no as an a oos eriori (after the fact) limit for a particular measurement.

Ana sos sna S be performed in such a manner that the stated LU)s w 1

be achie ed under routine conditions.

Occasionally background fluctu tions, unavoi ble small sample sizes, the presence of interfering nucli es, or other u

ontrol lable circumstances may render these LLOs unachi able.

In such c

es, the contributing fac+wrs shall be identified a described in the Ann 1 Radiological Environmental Operating Report pu uant to Speci ficatio 6.9.'.3.

EARON HARRIS - UNIT 1 3/4 32-12

RAOIQLQGICAL ENVIRONMENTAL MONITORING 4.12.2 LANO USE CENSUS LIMiiTNG CONG TIQN

.."QR OPERATION

3. 12.2 Land Use Census shall be conducted and shall identify withi a

distance 8

km (5 miles) the location in each of the 16 meteoroIo cal sectors of e nearest milk animal, the nearest residence, and the earest garden" of g ater than 50 aR (500 ft~) producing broad leaf veg ation.

APPLICABILITY:

all times.

ACTION:

a.

C.

Rth a Land Use Census identifying a location(

that yields a

calculated d

e or dose commitment greater th n the. values currently being calculat d in Specifica ion 4.11.2.3, ursuant to Specifica-tion 6.9.1.4, i ntify the new location(s) n the next Semiannual Radioactive Effl nt Release Report.

With a Land Use Cen us identifying a lo ation(s) tha yields a calcu-lated dose or dose c

itment (via th same exposure pathway) 20~

greater than at a loc ion from whic samples are currently being obtained in accordance ith Speci,i ation 3.12.1, add the new loca-tion(s) within 30 days the Rad logical Environmental Monitoring Program given in the OOQl.

The ampling location(s),

excluding the control station location, h vi the lowest calculated dose or dose commitment(s), via the same osure pathway, may be deleted from this monitoring program aft ctober 31 of the year in which this Land Use Census was candu d.

ursuant to Specification 6.9.1.4, submit in the next Semian ual Ra oactive Effluent Release Report documentation for a ch e in the Qf including a revised figure(s) and table(s) for the 0 reflectin the new location(s) with informa-tion supporting the ange in samplin locations.

The provisions of ecifications 3.0.3 d 3.0.4 are not applicable.

SURVEILLANCE REQUIRBIENT 4.12.2 The Land Use ensus..shall be conducted during the rowing season at least once per 12 ths using that information that will vide the best

results, such as b

a door to-door survey, aerial

survey, o

by consulting local agriculture authorities.

The results of the Land Use C

sus shall be included in the nnual Radiological Environmental Operating Re rt pursuant to Specification

. 9. 1.3.

"Broad leaf egetation sampling of at least three different kinds o

vegetation may be pe formed at the SITE BOUNOARY in each of two different dire tion sectors ith the highest predicted D/gs in lieu of the garden census.

Speci" ficati s for broad leaf vegetation sampling in Table 3.12-1, Part 4.c

, shall be fo owed, including analysis of control 'samples.

EARON HARRIS - UNIT 1 3/4 12-13

RAOIOLQGICAL ENVY>>

ENTAL MONITORING

/<. 12.3 INTERLABQRATORY CGMPARISON PROGRAM LIM 'G CQNQ 'TIQN FOR QP

'RATION 3.i&.3 nalyses shall be performed on all radioactive materials, suppl as part of a Interlaboratory Comparison Program that has been approved b

the Commission, that correspond to samples required by Table 3.12-1.

APPLICABILI A

al 1 times.

ACTION:

a.

With ana ses not being performed as required abov, report the corrective actions taken to prevent a recurrence o the Commission in the Annu 1 Radiological Environmental Opera ng Repor. pursuant to Specifica on 6.9.1.3.

b.

The provisions

'Specifications 3.0.3 and

.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

4. 12.3 The Interlaboratory Compa ison Progr shall be described in the 00CM.

A summary of the results obtained part o the above required Interlaboratory Comparison Program shall be include in t Annual Radiological Environmental Operating Report pursuant to Specific ti n 6.9.1.3.

HEARQN HARRIS - UNIT 1 3/4 12-14

INSTRUMENTATION BASES REMOTE SHUTDOWN SYSTEM (Continued)

This capability is consistent with General Design Criterion 3 and Appendix R

to 10 CFR Part 50.

3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION The OPERABIL'ITY of the accident monitoring instrumentation ensures that suffi-cient information is available on selected plant parameters to monitor and assess these variabLes following an accident.

This capabiLity is consistent with the recommendations of Regulatory Guide 1.97, Revision 3, "Instrumentation for Light-Water"CooLed Nuclear Power PLants to Assess Plant Conditions During and Following an Accident," May 1983 and NUREG-0737, "Clarification of TMI Action Plan Requirements,"

November 1980.

3/4.3.3 '

DELETED 3/4.3.3.8 DELETED 3/4.3.3.9 METAL IMPACT MONITORING SYSTEM The OPERABILITY of the Metal Impact Monitoring System ensures that sufficient capability is available to detect loose metallic parts in the Reactor System and avoid or mitigate damage to Reactor System components.

The aLLowable out-of-service times and surveillance requirements are consistent with the recom-mendations of Regulatory Guide 1.133, "Loose-Part Detection Program for the II Primary System of Light Water Cooled Reactors, May 1981.

pEL 3/4 ~ 3 ~ 3 ~ I DIOA IVE LI UID FFLUENT M IIITORINC NSTRIIMENTAT N

The r dioactive quid efflu t instru ntation i provided t monitor and on-trol as applic Le, the re eases of r dioactive materials i Liquid effl ents dur'ng actual potential reLeases o

Liquid fluents.

T e Alarm/Trip Set-po'nts for th e instrume ts shall b

caLculat d and adjus ed in accor nce w'th the met dology and parameters in the OD M to ensure that the al rm/trip xLL occur ior to exc ding the imits of 0

CFR Part 0.

The OP BILITY nd use of his instr ntation i consiste t with the equiremen of General Design Cri eria 60, 6, and 64 of Appendix A to 10 CF Part 50.

SHEARON HARRIS - UNIT 1

8 3/4 3"5 Amendment No. ~

INSTRUMENTATION BASES ExWcvjvs

/...

INNNKCNE, I I, I 'I The r coactive g seous e

u sns rumen t>on is p

vided to m

ftor and cont al, as appl cable, the r leases of r dioactive m terfals in aseaus efflu-ent during ac al or poten al release of gaseous ffluents.

he Alarm/Trip S

points for Nese inst nts shall calculate and adjus d in accordance th the met dology and arameters i

the OOCM ensure tha the alarm/trip fll occur ior to exce din th 'ts of CF Part 20 fs sns rumen tian prav1 r manftonng an cantrollin the cancentratians of potentially explosive gas tures fn the SKOUS RAOWAST REATMENT SYSTBl.

The OPERABILITY and use of this instrumentation is consistent with the require-ments of General Oesi n Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

e ensit'ty. af ny nob e

ac

>vs y m 1

rs u e o s ow comp c

th gaseo efflu t rele se requi ements Specff cation

.11.2.2 shall e

s h tha concen ations as low 1 x 10 pCf/ml are me urable.

3/4 3 <

TURBINE OVERSPE=D PROT=CTION This specffication is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will pra-tec. the turbine from excessive overspeed.

Protectfon fram turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related com-

ponents, equipment or structures.

SHEARON HARRIS - UNIT 1 B 3/4 3-6

3 4.11 RADIOACTIVE E VENTS BASES 3 4.11.1 LI UID EFFLUENTS 3 4.11.1.1 is specification is provided to ensure that the concentration of radioact'at

'als released in liquid waste effluents to UNRESTRICTED AREAS will less th 10 times the concentration levels specified in 10 CFR Part

. Appendix B, bl.e 2, Column 2.

This limitation provides additio assurance that the levels radioactive materials in bodies of water i NRESTRICTED AREAS will result i exposures within:

(1) the Section I design objectives of Appendix I, 10 CFR t 50, to a

MEMBER OF THE PUB and (2) the limits of 10 CFR Part 20. 1302 to population.

The co ntration limit for dissolved or entrained noble g

s is based u

the assumption that Xe-135 is the controlling radioisotope and i HPC i ir (submersion) was converted to an equivalent concentration in water u

the methods described in International Commission on Radiol cal tection (ICRP) Publication 2.

The required detection cap 'ties for radioacti materials in liquid waste samples are tabulated i

erms of the lower limits o tection (LLDs).

Detailed discussion the LLD, and other detection limit an be found in HASL Procedures

nual, HASL-300 (revised annually), Currie, A., "Limits for Qualitat' Detection and Quantitative Determination

- Applic ion to Radioche 'ry," Anal.

Chem.

40, 586-93 (1968),

and Hartwell, J. K.,

"Det ion Limits for Radioanalytical Counting Techniques," Atlantic Ric

'eld ord Company Report ARH-SA-215 (June 1975).

3 4.11.1.2

- D c'r1ig

's specification is provided to implement the requirements of Sections II III.,

and IV.A of Appendix I, 10 CFR Part 50.

The Limiting Condition Operatio

'mplements the guides set forth in Section II.A of Append' The ACTION state ts provide the required operating flexibility an the same time implement t ui'des set forth in Section IV.A of Appe to assure that the releases o

dioactive material in liquid effl ts to UNRESTRICTED AREAS will be kept "as as is reasonably achievab The dose calculation methodology and parameters s

he ODCH implement e requirements in Section III.A of Appendix I tha nformance th the guides of Appendix I be shown by calculational procedures ba models and data, such that the actual exposure of a MEMBER OF THE P

hrough appropriate pathways is unlikely to be substantially und stimated.

he equations specified in the ODCH for calculating the dos due to the actua lease rates of radioactive materials in liquid effl ts are consistent with t ethodology provided in Regulatory Guide

1. 1

, "Calculation of Annual Doses to from Routine Releases of Reac Effluents for the Purpose of Evaluating pliance with 10 CFR Part

, Appendix I," Revision 1, October 1977 and Regul ry Guide 1.

, "Estimating Aquatic Dispersion of Effluents from Acci al and Rout'eactor Releases for the Purpose of Implementing Appendix I,"

'1 SHEARON HARRIS - UNIT 1

B 3/4 11-1 Amendment No. py'

RADIOACTVlE EFFLUENTS BASES 3/4.11.1.3 U

RA A

c T A i T

RABILITY of the Liquid Radwaste Treatment System ensures that this iem will be a

le for use whenever liquid effluents require treatm rior to release to the en 'ent.

The requirement that the appr e portions of this system be used when ified provides assuran t the releases of radioactive materials in liqui ents wi ept "as low as is reasonably achievable."

This specification impl the requirements of 0 CFR 50.36a, General Design Criterion 60 of ndix A to Part 50 and the design objective given in Secti

.D of Appendix I to 10 rt 50.

The specified limits governin se of appropriate portions of the Liqu dwaste Treat-ment Syst re specified as a suitable fraction of he dose desig

'ec=ives set

. in Section II.A of Appendix I, 10 CFR Part 50 for liquid effluen 3/4. 11. 1. 4 LIOOID HOLDUP TANKS The tanks listed in this specification include all those outdoor radwaste tanks that are not surrounded by'iners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains con" nected to the Liquid Radwaste Treatment System.

Restricting the quantity of radioac ive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the resul.',ng concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable wa er supply and the nearest surface water supply in an UNR~ICTEG AREA.

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 specification is provided to ensure that the dose at any time at and bey the 7E BOUNDARY from gaseous effluents from all units on the site will within thhannual dose limits of 10 CFR Part 20 to UNRESTRICTEQ AREAS e

annual dose T'ts are the doses associated with the concentratio of 10 CFR Part 20, Appendix

~Table II, Column I.

These limits provid asonable assurance that radioa

've material discharged in gaseous

,luents will not result in the exposure o

~MEMBER OF THE PUBLIC in a RE~iICTEO AREA, either within or outside the S~i BOUNDARY, to annual av ge concentrations exceed-ing the limits specified in Appendix B, Table of 10 CFR Part 20 (10 CFR Part 20.106(b)).

For MEMBERS OF THE PUBL who may at times be within the SITE BOUNDARY, the occupancy of that MEMBE THE PUBLIC will usually be suffi-ciently low to compensate for an

'rease in the atmospheric diffusion fac or above that for the SITE BOUND Examples of calculations for such MB1BERS 0F THE PUBLIC, with the appr iate occupancy factors, sMl be given in the ODCM.

The specified releas te limits restrict, at all times, the corresponding gamma and beta do rates above background to a MEMBER OF THE PUBLIC at or beyond the SI BOUNDARY to less than or equal to 500 mrems/year tb~the whole body or ess han or equal to 3000 mrems/year to the skin.

These release rate its also restrict, at all times, the corresponding thyroid dose ra SHEARON HARRIS - UNIT 1 B 3/4 11-2

RADIOACTIVE EFFLUENTS BASES OOSc

"- (Continued above background 1500 mrems/year.

child via the inhalation pathway to less n or equal to The required detection capabilities rad ive material in gaseous was.e samples are tabulated in terms of the e

mits of detection (LLOs). Detailed discussion of the LLD, and othe ection limi n be found in HASL Pro-cedures

Manual, HASL-300 ised annually), Currie, "Limits for guali-tative Detection an antitative Determination - Applicatio Radiochemis ry,"

Anal.

Chem.

6-93 (1968),

and Hartwell, J.i(., "Detection Limi or Radia-ana yti ounting Techniques,"

A lantic Richfield Hanford Company Repo A

-2i5 (June 1975).

3/4. 11. 2. 2 s specification is provided to implement the requirements of Sec ions II.B, III.

d IV.A of Appendix I, 10 CFR Part 50.

The Limiting Condition for Qp tion imp ents he guides set forth in Section I'.B of Appendix I.

The ON s atements p

ide the required operating flexibility and at the sam ime implement the gui s set forth in Section IV.A of Appendix I to ure that he releases of radioacti material in gaseous effluents to UNR ICTED AREAS will be kept "as low as reasonably. achievable."

The eillance Requirements implement the requirements i

ection III.Aof Appen I that conformance with the guides of Appendix I be show calculation procedures based on models and data such that the ac ual exposu of a ER OF THE PUBLIC. through appro-priate pathways is unlikely to be substa ally underestimated.

The dose cal-culation methodology and parameters lis in the QOCM for calculating the doses due to the actual release es of radioa e noble gases in gaseous effluents are consistent wi e methodology provi in Regulatory Guide 1.109, "Calculation of Annual 0

s to Man from Routine Release f Reactor Effluents for the Purpose of E uating Compliance with 10 CFR Part 5

ppendix I,"

Revision I, Octo I977 and Regulatory Guide 1.111, "Methods f stimating Atmospheric nsport and Dispersion of Gaseous Effluents in Routin eleases from Li ater Cooled Reactors,"

Revision 1, July 1977.

The OOCM eq ons prov' for determining the air doses at and beyond the SITE BOUNDARY are ed n the historical average atmospheric conditions.

3/4.11.2.3 E -

QO E-1.

E-3 I

M c7wgr ANO AOI E

AT.

A cification is provided to implement the requirements of Sections III.A and Appendix I, 10 CFR Part, 50.

The Limiting Con 'or Operation are the gu t forth in Section II.C of x I.

The ACTION statements provide the require ating fl y and at the same time implement the guides set forth in S of Appendix I to assure that the releases of'adioactive ma s in gaseous ef to UNRESTRICTED AREAS will be kept "as is reasonably achievable."

The ulational methods ied in the Surveillance Requirements implement the re ents SHEARON HARRIS - UNIT i B 8/4 U.-3

RADIOACTIVE EFFLUENTS BASES

" " IODiNE-131. IODINE-133. TRITIUM, ANO RADIOACTIVE MAT=RIAL IN A ii LAi rORM (Continued) in Section

.A of Appendix I that conformance with the guides of endix I be shown by ca

'ational procedures based on models and data su that the ac.ual exposure o

MBlBER QF THE PUBLIC through appropriat athways is unlikely to be substa al.ly underestimated.

The 00& ca

~lational methodology and parameters for calcu ing the doses due to the a

al release rat s of the subject materials are consisi t with the methodol provided in Regulatory Guide 1.109, "Calculation of Ann I Doses to Ma rom Routine Releases of Reacto~ Effluents for the Purpose o

valua Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 egulatory Guide 1.IU., "Methods for Estimating Atmospheric Transport and spe ion of Gaseous Effluents in Routine Releases from Light-Water Cooled ctors,"

ision 1, July i977.

These equa-tions also provide for determi

'ng the actual do based upon the historical average atmospheric conditi s.

The release rate sp ifications for Iodine-I31 Iodine-333, tritium, an adiondclides in particulate with half-lives greater than 8 days e dependent upon the existing radion ide pathways to man in the areas at beyond the SITE BOUNDARY.

The pathways were examined in the develo nt of the calculations were:

(I) individual ipha tion of air borne radi

uclides, (2) deposition of radionuclides onto green Iea egetation with s equent consumption by man, (3) deposition onto g~assy areas whe milk ani s and meat producing animals graze with consumption of the milk and m t

man, and (4) deposition on the ound with subseouent ex osure of man.

3/4.11.2.4 S"

U ERABILITY of the WASTE'AS HOLDUP SYSTEM and the VENTILATION EXHAUS TREATM

~i ensures that the systems will be available for us never gaseous efflue quire treatment prior to release to the nment.

The requirement that the riate portions of these s

be used, when spec~-

fied, provides reasonable a

nce that the re es of radioactive materials in gaseous effluents will be kept o

is reasonably achievable."

This specification implements the requi n

10 CFR 50.36a, General Design Cri-terion 60 of Appendix A to r

Part 50 and sign objec.ives given in Section II.O of Appe 'o LO CFR Part 50.

The spe ed limits governing-the use of ap ate portions of the systems were specific a suitable fraction e dose design objectives set forD in Sections II.B a I.C of A

ix I,- M CFR Part 50, for gaseous effluents.

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 GASEOUS RAOWASTE TREATMENT SYSTEM down-stream of the hydrogen recombiners 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 flamma-bility limits.

These automatic control features include isolation of the sourc

'f oxygen to reduce the concentration below the flammability limits.

Maintain-ing the concentration of hydrogen and oxygen below their flammability limits SHEARON HARRIS - UNIT 1 B 3/4 0"4

RAG IOACTrVE -.<<.='ENTS BASES EXPLOSIVE GAS MIXTURE (Continued) provides assurance that the releases of radiaac.ive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appen-dix A to 10 CFR Par. 50.

-3/4:11.2.6 GAS STORAGE TANKS The tanks included in this speci, ication are those tanks for which the quant.y of radioactivity contained is not limited directly ar indirectly by another Technical Saec'.fication.

Res.ric ing the quantity of radioac.ivity contained

-in each gas storage tank provides assurance that in the event of an uncontrolled release af the tank's contents, the resulting ~hole body expasure to a'MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem. This is consistent with Standard Review"Plan '1.3, Branch Technical Position ETSB 11-5, "Postulated Radioactive Releases Oue to a Waste Gas System Leak or Failure," in NUREG-OBOO, July 1981.

3/4. 11. 3 L

A 0

T E

AS S

-Oz4ygo/

This tion implements the requirements of 10 CFR 50.36a and General Design Cri of Appendix A ta 10 CFR he process param-eters included in establishing PROGRAM may include, but are nat limi ed ta, waste e pH, was

'OLIDIFICATIONagent/

catalyst ratio oil content, waste principal chemica

'nts, and mi curin times.

3/4.11.4 T

0 s specification is provided ta meet the dose limitatians of 10 CFR Part that ve been'incorporated inta 10 CFR Part 20 by 46 FR 1B525.

The spe 'a-tion req 's the preparation and submittal of a Special Repart whene the calculated es due to releases of radioac ivity and to radiatio rom ur anium fuel cycle sou exceed 25 mrems ta the ~hale bady or any o

, except the thyroid, which sha e limited ta less than or equal to 7 rems.

For sites containing up to four ctars, it is highly unlikely t the resultant dase to a MEMBER OF THE PUBLIC 1 exceed the dose limi of 40 CFR Part 190 if the individual reactors remain wi twice t!ie dos esign objectives of Appendix I and if direc.'adiation dases fra e uni d from outside storage tanks ar kept small.

The Special Report wi11

'be a course of action that should result in the limitation of the annu d

to a MEMBER OF THF PUBLIC ta within the 40 CFR Part 190 limits.

For e purpose f the Special Report, it may be assumed that the dose commi to the MBIBER o the PUBLIC from other uranium fuel cycle sources is ne 'ble, with the exceptio hat dose contributions from other nuclear fu cycle facilities at the same s

or within a radius of 8

km must be consi red.

If the dose to any MEMBER OF THE BLIC is estimated to exceed the irements af 40 CFR Part 190, the Special Rep with a reaues for a vari e {provided the release conditions resulting in viola an of 40 CFR Part 19 ave not already been corrected),

in accordance with the pro 'ans o

40 190.& and 10 CFR 20.405c, is considered ta be a timely request an ful" ls the re uirements of 40 CFR Part 190 until NRC staff action is ceaplete SHEARQN HARRIS - UNIT 1 B 3/4 11-5

RAOIOACTIVE """.-."LUENTS BASES

>0

" (Continued The variance only relate e limits of 40 CFR, and does not apply in any way to the other requiremen imitation of 10 CFR Part 20, as addressed in Specifications and 3.

An individual is not con-sidered a

MEMBER 0 I.IC during any period in w i she is engaged in carryin ny operation that is par of the nuclear fuel cyc SHEARON HARRIS - UNIT L B 3/4 0-6

3/4. U RAOIOLQGICAL ENVIRONMENTAL KNITORING BASES 3/4. 12. 1 T

IG

.0

-o~+f<Z e Radiological Environmental Monitoring Program required by this specificati pro des representative measurements of radiation and of radioactive materi s

in tho exposure pathways and for those radionuclides that lead to the

'ghest potentia adiation exposure of MEMBERS OF THE PUBLIC resulting from e plant operation.

is monitoring program implements Section IY.B.2 of A ndix I to 10 CFR Part 50 nd thereby supplements the Radiological Effluen onitoring Program by verify g that the measurable concentrations of ra oactive materials and levels of radia are, not higher than expected on th asis of the effluent measurements d the modeling of the environme al exposure pathways.

Guidance for this monitor program is provided by e Radiological Assessment Branch Technical Position on nvironmental Monitor g, Revision 1, November 1979 The initially specified monito g program will e effective for at least the first 3 years of commercial opera

'on.

Foll sng this period, program changes may be initiated based on operationa exp cence.

The required detec.ion capabilities r e ironmental sample analyses are abulated in terms of the lower I'ts of de c ion (LLQs).

The LLOs required by Table 4. 12-1 are considered ptimum for rout e environmental measurements in industrial laboratories.

t should be recogni that the LLO is defined as an a oriori (before the f t) limit representing the apability of a measure-menr. system and not as n

a oostariori (after the fact imit for a particular measurement.

Detailed disc sion of the LLQ, and other detection limits, can e found in HASL Proc s Manual, HASL-300 (revised annually), Currie, L.A., "Limits for Oualita oetection anouuuantitative oetermination - Appiicatian adio-

'chemi ry," Anal.

Chem.

40, 586-93.(1968),

and HartweII, J. K., "Getect n

Li'c l* 'A1 i

i*a Id t

o an R ort ARH-SA-215 (June 1975).

3/4. iU. 2 specifica ion is provided to ensure that changes in the use of areas a

and be the SITE BOUNOARY are identified and that modifications to Radiologica ironmental Monitoring Program are made if requi y the results of >is ce The best. information from the doo

-door survey, from aerial survey or consulting with local agri ural authorities shall be used.

This census satis, e requiremen Section IV.B.3 of Appendix I to 10 CFR Part 50.

Restricting the su gardens of greater than 50 m

provides assurance that significant o

athways via leafy vegetables will be identified and monitored si a garden of size is the minimum required to produce the quantity g/year) of leafy vege s

assumed in Regulatory Guide 1m 109 for co tion by a child.

To determine ths

'nimum garden size, the.followin sumptions were made:

(1) 2'f the garden wa ed for growing broad I vegetation (i.e., similar to lettuce and cabbage),

and (

vegeta-yield of 2 kg/m-".

SHEARON HARRIS - UNIT 1 B 3/4 12"1

RAOIOLQGICAL ENVIRONMENTAL HONITORING BASES 3/4.12.3 i

cR 8

A R

0 P

Th d Interlabora~o Corno e

ni d'or par scipatson sn an approve ry Program is prove ure that independent checks on 1s>on and accuracy of the measurements o

-ive

>n environmental sample matrices are performed as part ua 1

nce pr ogram for environmental monitoring in ord onstrate that the results are r the purposes of S

. 2 of Appendix I to 10 CrR Par. 50.

SHEARON HARRIS - UNIT 1 8 3/4 >U-2

0 AOMINISTRATIVE CONTROLS PROCEOURES ANO PROGRAMS Continued}

C.

Seconda.

Mater Chemistr Continued) d.

e.

6.

A procedure identifying (a) the authority responsible for the interpretation of the data and (b) the sequence and timing of administrative events required to initiate corrective action.

Backup Method for Oeterminin Subcoolina Margin A progi am that will ensure the capability to monitor accurately the Reactor Coolant Sys em subcooling margin.

This program shall include the following:

I.

Training of personnel, and 2.

Procedures for monitoring.

Post-Accident Samolin A program that will ensure the capability to obtain and analyze, under accident conditions, reactor coolant, radioac.ive i.odines and particulates in plant gaseous effluents, and containment atmosphere samples.

The program shall include the following:

1.

Training of personnel, 2.

Procedures for sampling and analysis, and 3.

Provisions for maintenance of sampling and analysis equipment.

Insoectioiis of later Control Structures g.

A program to implement an ongoing. inspection program in accordance with Regulatory Guide LI27 (Revision I, March 1978) for the main and auxiliary dams, the auxiliary separating dike, the emergency.

service water intake and discharge

channels, and the auxiliary reservoir channel.

The program shall include the following:

1.

The provisions of Regulatory Guide 1.127, Revision 1, to be implemented as a part of plant startup operations.

2.

Subsequent inspections at yearly intervals for at leas the

~ next 3 years.

If adverse conditions are not revealed by these inspections, inspection at S-year intervals will be performed.

Turbine Rotor Inspection A program to implement an ongoing inspec.ion of the low pressure turbine rotor.

The program shall be based upon:

Vendor recommendations for low pressure turbine rotor inspec ion

'intervals and procedural guidelines, and 2.

Using vendor methodology to recalculate the inspection interval if cracking in the roto~ is ever found.

SHEARON HARRIS - UNIT I

INSERT 2

(on Page 6-19) h.

Radioactive Effluent Controls Pro ram 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 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 times the concentration values in Appendix.B, Table 2, Column 2 to 10 CFR 20.1001

- 20.2402, 3)

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents pursuant to 10 CFR 20.1302 and with the methodology and parameters in the

ODCM, 4)

Limitations on the annual and quarterly doses or dose commitment to a

MEMBER OF THE PUBLIC from 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 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 radioactivity 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, 7)

Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following:

For Noble gases:

Less than or equal to a dose rate of 500 mrems/yr to the total body and less than or equal to a dose rate of 3000 mrems/yr to the skin, and For Iodine-131, Iodine-133,

Tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:

Less than or equal to a dose rate of 1500 mrems/yr to any organ.

INSERT 2 (on Page 6-19) continued 6.8.4 h. Radioactive Effluent Controls Pro ram Cont.

8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9)

Limitations on the annual and quarterly doses to 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 to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and 10)

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

i.

Radiolo ical Environmental Monitorin Pro ram A

program shall be provided to monitor the radiation and radionuclides in the environs of the plant.

The program shall provide (1) representative measurements of radioactivity in the highest potential exposure

pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental 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, 2)

A Land Use, Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and 3)

Participation in a

Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

ADMINISTRATIVECONTROLS ANNUAL REPORTS Continued film badge measurements.

Small exposures totaling less. than 20 of the individual total dose need not be'ccaunted for.'n the aggregate, at least 8Q" of the total whole-body dose received from externaI saurces shauld be assigned to specific major work functions; b-The results of specific activi y analyses in which the reactor coolant exceeded the limits of Specificatian 3.4.8.

The following information shall be included:

(1) reactor power history starting 48 hou~s prior to the. first sample in which the limit was exceeded (in graphic and tabular format); (2) results of the last isatopic analysis for radio-iodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radio-iodine activity was reduced ta less than limit.

Each result should include date and time of sampling and the radioiodine cancentrations; (3) cleanup flaw history starting 4& hours prior to the first sample in which the limit was exceeded; (4) graph of the I-131 concentra-tion (pCi/gm) and one other radioidine isotope cancentra.ion (pCi/gm) as a function of time for the duration of the specific ac.ivity above the steady-state level; and (5) the time duration when the specific activi y of the reactor coolant exceeded the radioiodine limit.

c.

Documentation of all challenges to the pressurizer power operated relief valves

{PORVs) and safety valves.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.L3 Routine Annual Radiological Environmental Operating Reports, coverin e operation of the unit during the previous calendar year, shall be subm ed pri to May 1 of each year.

The initial report shall be submitted pr'a May 1 the year following initial criticality.

The Annual Ra ological Environmental Operating Reports sha nclude summaries, interpretations, d an analysis of trends of the resul f the radialogical environmental surve ance activities for the report riod, including a com-parison with preoperati I studies, with operati 1 controls, as appropriate, and with previous enviranme 1 surveillance

arts, and an assessment, of the observed impacts of the plant eratian on e environment.

The reports shall also include the results of the U

ensus required by Specification 3.12.2.

The Annual Radiological Envira 1

Op ting Reports shall include the results of analysis of all olagical env nmental samples and of all enviranmental radiation surements taken duri the period pursuant ta the locations specified i e table and figures in th FFSITE DOSE CALCULATION MANUAL, as well a ummarized and tabulated results o

ese analyses and measurements i

e format of the table in the Radiologic Assessment Branch Technical P

tion, Revision 1, November 1979.

In the event at same individ-ual res are'ot available for inclusion with De report, th eport shall be mitted noting and explaining the reasons for the missing resu The sing data shall be submitted as saon as possible in a supplementary part.

SHEARON HARRIS - UNIT 1

INSERT 3

(on Page 6-21) 6.9.1.3 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.

INSERT 4 (on Page 6-22) 6.9.1.4 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year.

The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.l of Appendix I to 10 CFR Part 50.

ADMINISTRATIVECONTROLS A

RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Continued The reports s

also include the following:

a. summary descri n of the Radiological Envi tal Monitoring Program; at least t egible maps" covering all sampling lo ons keyed to a table gi distances and directions from the centerline of the rea

. the resul licensee participation in the Interlaboratory Comparison Prog e corrective action taken if the specified program is not being pe ed quired by Specification 3.K.3; reasons for not conducting adiological En ental Monitoring'rogram as required by Specificat

.L2.1, and discussion of deviations from the sampling schedul able 3.22-1; discussion of environm 1 sample measure-ments that ed the reporting levels of Table 3.%-2 but are the result of pl effluents, pursuant to ACTION b. of Specification 3.12.1; a

iscussion 1 analyses in which the LLD required by Table 4.12-1 was not, achiev NNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.4 Routine Semiannual Radioactive Effluent Release Reports covering the ration of the unit during the previous 6 months of operation sha11 be sub-mi d within 60 days after January 1 and July 1 of each year.

The period f

the rst report shall begin with the date of ini axial criticality.

The Semia ual Radioactive Effluent Release Reports shall include a

ummary of the quantiti of radioactive liquid and gaseous effluents and so d ~aste released from e unit as outlined in Regulatory Guide 1.21, "

suring, Eval-

uating, and Repo ng.Radioactivity in Solid Wastes and Rele es of Radioactive Materials in Liqui d Gaseous Effluents from Light-Mater oled Nuclear Power Plants," Revision 1, e 1974, with data summarized on quarterly basis following the format of endix B thereof.

For soli

astes, the format for Table 3 in Appendix B shal e supplemented with th e additional categories:

class of solid wastes (as de ed by 10 CFR Part

), type of container (e.g.,

Type A, Type B) and SOLIQIFICA agent or ab ent (e.g.,

cement).

The Semiannual Radioactive Effluent eas Report to be submitted within 60 days after January 1 of each year sh include an annual summary of hourly meteorological data collected over th pre

'ous year.

This annual summary may be either in the form of an hour b

our lis ng on magnetic tape of wind speed, wind direction, atmospheric-stabi ty, and prec'tation (if measured),

or in the form of joint frequency di ributions of wind

eed, wind direction, and atmospheric s~ility.

Th'ame report shall inc de an assessment of the radiation doses due to th adioactive liquid and gase s effluents released "One map shall over stations near the EXCLUSION AREA BOUNDARY; econd shall include the ore distant stations.

~In lieu submission with the Semiannual Radioactive Effluent Release Repo

, the licensee has the option of retaining this.suaeary of require met rological data on site in a file that shall be provided to the NRC n request.

SHEARQN HARRIS -'UNIT 1

AOHINISTRATIVE CONTROLS SEMIANNUAL RAOIOACTIVE EFFLUENT RELEASE REPORT Continued fra the unit or station during the previous calendar year.

This same repo shall isa include an assessment of the radiation doses from radioactive quid and gas us effluents to MEHBERS OF THE PUBLIC due to their activities side the SITE UNDARY (Figure 5.1-3) during the report period.

All ass ions used in mak g these assessments, i.e., specific activity, exposure

ime, and

location, sha be included in these reports.

The meteorological onditions concurrent with e time af release of radioactive materials in seaus efflu-

eats, as determin by sampling frequency and measurement, sha be used for determining the gas us pathway doses.

The assessment of ra ation doses shall be performed in acco nce with the methodology and parame rs in the OFFSITE OOSE CALCULATION MANUAL OOCM).

The Semiannual Radiaactive ffluent Release Report to e submitted within 60 days after January I of e year shall also inc de an assessment of radia-tion doses to'he likely most osed HEHBER OF PUBLIC from reactor releases and other nearby uranium fuel cy e saurces, in uding doses from primary efflu-ent pathways and direct radiation, or the pr ious calendar year to show con-formance with 40 CFR Part 190, "Envi nmen Radiatian Protection Standards for Nuclear Po~er Operation."

Acceptable th ds for calculating the dose contribu-tion fram liquid and gaseous effluents a

given in Regulatory Guide 1.IO.,

Revisian 1, October 1977.

The Semiannual Radioactive Effluen elease Re rts shall include a list and description of unplanned release

, from the site to UNRESTRICTEO AREAS, of radioactive materials in gasea and liquid efflue ts made during the reporting period.

The Semiannual Radioactiv Effluent Release Reports sha include any changes made during the reporti period to the PROCESS CONTROL P

GRAM and the

OOCM, pursuant to Specifica

'ons 6.13 and 6.14, respectively, as 11 as any major change to Liquid, G

eous, or Salid Radwaste Treatment System pursuant to Specification 6.15 It shall also include a listing af new lac ions for dose calculations and r environmental monitoring identified by the La Use Census pursuant ta Sp ification 3.12.2.

The Semian al Radioactive Effluent Release Reports shall also include he, followin an explanation as ta why the inoperability of liquid or gase s

ef'fluen monitoring instrumentation was not corrected within the time spec ied in Sp ification 3.3.3.10 or 3.3.3.11, respectively; and a description of th eve leading ta liquid holdup tank's or gas storage tanks exceeding the limits of Specification 3.11.1.4 or 3.1I 2.6, respectively.

MONTHLY OPERATING REPORTS 6.9.1.5 Routine reports af aperating statistics and shutdown experience shall be submitted on a monthly basis to the Oirector, Office of Resource Management,.U.S.

Nuclear Regulatory Commission, Washington, O.C.

20555, with 'a copy to the Regional Administrator. of the Regional Office of the

NRC, no later than the 15th of each month fallowing the calendar month covered by the repar--

SHEARON HARRIS - UNIT 1

ADMINISi RATIVE CONTROLS RECORD RETENTION (Continued) effective at specified times and QA records showing that these procedoree were followed;(gP o.

Records of facility radiation and contamination survey

6. 11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Par 20 and shall be approved, maintained, and adhered to for al.l operatians involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 Pursuant to Paragraph 20.203(c)(5) of 10 CFR Part 20, in lieu of the "control device" or "alarm. signaI" required by Paragraph 20.203(c),

each hign radiation area, as defined in 10 CFR Part 20, in which the intensity of radia-tion is equal to or less than 1000 mR/h at 45 cm (18 in. ) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance af a Radiation Mark Permit (RMP).

Individuals qualified in radiation protection procedures (e.g.,

Health Physics Technicians) or personnel continuously escorted by such individuals may be exempt from the SIP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/h, pro-vided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or mare of the fallowing:

a.

A radiation monitoring device that continuously indicates the radiation dose rate in the area; or b.

c A radiation monitoring device that continuously integrates the radiation 'dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been es~-

lished and personnel have been made knowledgeable of them; or An individual qualified in radiation protection procedures, with a radiation dose rate monitoring device, who is responsible for pro-viding positive control over the activities within the area and who shall perform periadic radiation surveillance at the frequency specified by the Radiation Control Supervisor in the RWP.

6.12.2 In addition ta the requirements of Specification 6.12.1, accessible areas with radiation levels greater than 1000 mR/h at 45 cm (1S in.) from the radiation source or from any surface which the radiation penetrates, shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the shift Foreman on duty SHEARON HARRIS - UNIT 1 6-26

INSERT 5

(on Page 6-26) p.

Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

INSERT 6

(on Page 6-27)

Changes to the PCP:

a

~

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p.

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 PNSC and the approval of the Plant General Manager.

INSERT 7 (on Page 6-27)

Changes to the ODCM:

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p.

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

'20.1302, 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 PNSC and the approval of the Plant General Manager.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected

pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,

month/year) the change was implemented.

AOMINISTRATIVE CONTROLS HIGH RAOIATION AREA (Continued) and/or health physics supervision.

Ooors shall remain locked except during periods of access by personnel under an approved KiP which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area.

In lieu of the stay time specification of the RMP, direct or remote (such as closed circuit TV cameras) continuous sur veillance may be made by personnel qualified in radiation protection procedures

-to-provide positive exposure control over the activities being performed within the area.

Ouri'ng emergency situations that involve personal injury or actions taken to prevent major equipment

damage, continuous surveillance and radiation monitoring of the work area by a qualified individual may be substituted for the routine RMP procedure.

For accessible individual high radiation areas, with radiation levels of greater than 1000 mR/h, that are located within large areas, such as l%R containment,

~here no enclosure exists for purposes of locking and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded and conspicuously

posted, and a flashing l.ight shall be activated as a warning device.

6 13 PROCESS CONTROL PROGRAM PCP

.1 The. PCP shall be approved by the Commission prior to implementation.

6. E3.2 a0 ense initiated changes to the PCP:

Shall submitted to the Commission in the Semian Radioactive Effluent ase Report for the period in which e change(s) was made.

This s ttal shall contain:

L.

Sufficiently deta d informati to totally support. the rationale for the ch wi ut benefit of additional or suppl cmental informatio, 2.

A determination t the change 'ot reduce the overall conformance the solidified ~aste duct to existing criteria for soli astes; and 3.

entation of the fac that the change has be r viewed and found acceptable by the PNSC.

Shall become effective upon review and acceptance by the PNSC.

6. 14 OFFSITE OOSE CALCULATION MANUAL OOCM The OOCM shall be approved by the Commission prior to implementatio 6.14;2 Licensee-initia s to the OOCM:

a.

Shall be submit ommission in

'annual Radioac-ive Eff1 ase Report for the period in which the was e effective.

This submittal shall contain:

SHEARON HARRIS - UNIT 1

ADMINISTRATIVECONTROLS DOSE CALCULATION MANUAL ODCM Continued Sufficiently detailed, information to totally support the

'onale for the change without benefit of addftio or supple-menta formation.

Information submitted sho consist of a package c

ose pages of the ODCM to be ged with each page

numbered, date d containing the r an number, together with appropriate analys r evaluat justifying the change{s);

2.

A-.determinatian that c

e will not reduce the accuracy or reliability of d calculation setpoint determinations; and 3.

0 entation of the fact that the change ha een reviewed 'arid ound acceptable by the PNSC.

Shall become effective upon review and acceptance by.he PNSC.

8. 15 MAJOR CHANGES TO LIOUID GASEOUS AND SOLID RAOWASTE TREATMENT SY~S" 6.15.

Licensee-initiated major changes to the Radwaste Treatment Systems (liquid,

aseous, and solid):

a.

Sh 1 be reported to the Commission in the Semiannual Ra 'ctive Effl t Release Report for the periad in which the ev uaticn was reviewe in accordance with Specifica~ion 6.5.

The scussion of each chan shall contain:

L.

A summa~ f'he evaluation that led ta e determinaticn that the change ld be made in accardan with 10 CFR 50.59; Z.

Sufficient detai information totally support the reason fcr the change wi benefi of additional or supplemental informati an; 3.

A detailed descriptia f

e equipment, components, and pro-cesses involved and e inte aces with other plant systems; 4.

An evaluation the change, whi shows the predicted releases af radioacti materials in liquid d gaseous effluents and/or quantity solid waste that differ f those previously predi in the License application an endments thereto; 5.

An valuatian af the change, which shows the ected maximum

osures, to a MEMBER OF THE PUBLIC in the UN ICTED AREA and to the general papulatian, that differ from se previously estimated in the License application and amendments ereto; censees may choose to submit the information called for in this Specifi tion as part of the annual FSAR update.

SHEARON HARRIS - UNIT 1

ADMINISTRATIVECONTROLS

AJOR CHANGES TO LIOUIO GASEOUS.

ANO SOLID RAOWASTE TREATMENT SYSTBIS inued 6.

comparison of the predicted releases of radioa materials, in 'd and gaseous effluents and in soli ste, to the actual re s for the period prior en the change is to be made; 7.

An estimate of the expo result of the chan, and plant operating personnel as a

Documen on of the fact that the change reviewed and fo acceptable in accordance with Speci ficaton b.

all become effective upon review and acceptance in accordance h

Specification 6.5.

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SHEARON HARRIS - UNIT 1