Text

Proposed Tech Specs Re Implementation of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent TS in Administrative Controls Section of TS & Relocation of Procedural Details of RETS to Odcm....
	ML17306A473
Person / Time
Site:	Palo Verde
Issue date:	02/14/1992
From:	; ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	;
Shared Package
ML17306A472	List: ML17306A473; ML17306A474;
References
	GL-89-01, GL-89-1, NUDOCS 9202250217
	Download: ML17306A473 (164)
	v • d • e

INDEX DEFINITIONS SECTION PAGE

l. 0 DEFINITIONS 1 1

~ ACTION. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

1.2 AXIAL SHAPE INDEX......

1.3 AZIMUTHAL POWER TILT' Tq...............

1. 4 CHANNEL CALIBRATION......................

1.5 - CHANNEL CHECK... ~ \ ~

l. 6 CHANNEL FUNCTIONAL TEST................. 1"2

1. 7 CONTAIHMEHT INTEGRITY 1-2

1. 8 CONTROLLED LEAKAGE.................

1.9 CORE ALTERATION....................................,........ 1-2

1. 10 DOSE E(UIVALEHT I-131................

E-AVERAGE DISINTEGRATION ENERGY 1-3

l. 12 ENGINEERED SAFETY FEATURES RESPOHSE TIME

l. 13 FRE(UEHCY HOTATION. 1-3

l. 14 GASEOUS RAOWASTE SYSTEM. 1" 3

1. 15 IDENTIFIED LEAKAGE................................ 1-3 1 .16 KH 1. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1-4 1.17 MEMBER(S) OF THE PUBLIC................

1.18 OFFSITE DOSE CALCULATIOH MANUAL (OOCM).

1. 19 OPERABLE - OPERABILITY................. 1-4 1.20 OPERATIONAL MODE - MODE. 1-4

1. 21 PHYSICS TESTS a-g 5 1.22 PLANAR RADIAL PEAKIHG FACTOR - F xy'.

23 PRESSURE BOUNDARY LEAKAGE.......... ~ ~ 1-5 1.24 PROCESS CONTROL PROGRAM (PCP).. 1-5 1.25 PURGE - PURGIHG.......

1. 26 RATED THERMAL POWER............

1.27 REACTOR TRIP SYSTEM RESPONSE TIME...

1.28 REPORTABLE EVENT..

1. 29 SHUTDOWN MARGIN........ ~ ~ ~ ~ y ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1-6

l. 30 SITE BDUNDARY.......... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1-6 9202250217 9202IA PDR ADOCK 05000528 P PDR PALO VERDE - UNIT 1 . AMENOMEHT H054~:;.'","~,.

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INDEX DEFINITIONS SECTIOH PAGE 1-. 31 . SOFTMARE.. 1" 6

'hZ" ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ o l.'R$ SOURCE CHECK. 1-6.

l.g STAGGERED TEST BASIS.

1. THERMAL POMER............... 1-6 1.'@ UNIDENTIFIED LEAKAGE. ~ ~ ~ ~ ~ ~ 1-7 1.@ UNRESTRICTED AREA... 1" 7 1.$$ VENTILATIDN EXHAUST TREATMENT SYSTEM ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ 1-7 1.Q VENTING.............. 1"7 PALO VEROE - UNIT 1 AMEHDMEHT HO. P~

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CONTROLLED BY USER INDEX LIMITING CONDITIONS FOR. OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/4. 2 POWER DISTRIBUTION LIMITS 3/4.2. 1 LINEAR HEAT RATE... 3/4 2-1 3/4. 2. 2 PLANAR RADIAL PEAKING FACTORS - F.. 3/4 2-2 3/4. 2. 3 AZIMUTHAL POWER TILT - Tq.. 3/4 2-3 3/4.2.4 DHBR MARGIN.o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 2-5 3/4.2.5 RCS FLOW RATE....... 3/4 2-8 3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE.............. 3/4 2-9 3/4.2.7 AXIAL SHAPE INDEX. 3/4 2-11 3/4.2.8 PRESSURIZER PRESSURE ......... 3/4 2-12 3/4. 3 'NSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION....... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM IHSTRUMENTATION.. 3/4 3-17 3/4. 3. 3 MONITORING 'INSTRUMENTATION RADIATIOH MONITORING INSTRUMENTATION.. 3/4 3-37 3-41

'/4 INCORE DETECTORS SEISMIC IHSTRUMENTATIOH. 3/4 3-42 METEOROLOGICAL INSTRUMENTATION .. 3/4 3-45 REMOTE SHUTDOWN SYSTEM............................... 3/4 3-48 POST-ACCIDENT MOHITORING IHSTRUMENTATIOH............. 3/4 3-57 LOOSE-PART DETECTION INSTRUMENTATION. 3/4 3-61 pgpi~SX~8 gaa MONITORING INSTRUMENTATION... 3/4 3-63 3/4 ' REACTOR COOLANT SYSTEM 3/4.4. 1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION............................. 3/4 4-1 H OT STANDBY........................................ ~ .... 3/4 4-2 MOT SHUTDOWNo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 4-3 COLO SHUTDOWN - LOOPS FILLED......... 3/4 4-5 COLO SHUTDOWN " LOOPS NOT FILLED...................:.... 3/4 +6 PALO VERDE - UNIT 1 AMENDMENT NO. 27

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMEHTS SECTION PAGE 3/4.10.4 CEA POSITION, REGULATING CEA INSERTION LIMITS AND REACTOR COOLANT COLD.LEG TEMPERATURE....... . 3/4 10"4 3/4.10.5 MINIMUM TEMPERATURE AND PRESSURE FOR CRITICALITY. 3/4 10"5 3/4. 10.6 SAFETY INJECTION TANKS 3/4 10-6 3/4.10.7 SPENT FUEL POOL LEVEL........ 3/4 10-7 3/4.10.8 SAFETY INJECTION TANK PRESSURE........ 3/4 10-8 3/4 10 9 SHUTDOMH MARGIN AND KH"1 CEOMS TESTIHG 3/4 10-9 3/4. 11 RADIOACTIVE EFFLUENTS

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EXPLOSIVE GAS MIXTURE......,............ 3/4 11"~ 2 GAS STORAGE TANKS 3/4 11-'Si 3

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PALO V'ERDE " UHIT 1 X AMENDMEHT HO. 54

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SECTION PAGE 3/4.9, 7 CRANE TRAVEL " SPENT FUEL STORAGE POOL BUILDING.-....-.. 8 3/4 9"2 0

3/4.9..8,.SHUTDOWN.t;OOLIHG AHD COOLANT CIRCULATION................ 8 3/4 9-2 3/4.9 ~ 9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM........... 8 3/4 9-3 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE POOL 8 3/4 9-3 3/4.9.12 FUEL BUILDING ESSENTIAL VENTILATION SYSTEM.............. 8 3/4 9-3 3/4. 10 SPECIAL TEST EXCEPTIONS 3 4'0 1 SHUTDOWN MARGIN AND KH-1 CEA WORTH TESTS.. 8 3/4 10-1 3/4. 10. 2 MODERATOR TEMPERATURE COEFFICIENT, GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS........... 8 3/4 10-1 3/4.10.3 REACTOR COOLANT LOOPS 8 3/4 10-1 3/4.10.4 CEA POSITION, REGULATIHG CEA INSERTION LIMITS I

AND REACTOR COOLANT COLD LEG TEMPERATURE........... 8 3/4 10-1 3/4.10.5 MINIMUM TEMPERATURE AND PRESSURE FOR CRITICALITY........ 8 3/4 10-1 3/4.10. 6 SAFETY INJECTION TANKS... 8 3/4 10-2 3/4.10.7 SPENT FUEL POOL LEVEL.................. 8 3/4 10-2 3/4.10.8 SAFETY INJECTION TANK PRESSURE............. 8 3/4 10"2 3/4.10.9 SHUTDOWN MARGIN AND KH

" CEDMS TESTIHG 8 3/4 10"2 1

3/4. 11 3/4. 11. 1 RADIOACTIVE EFFLUENTS 4<%~4D HciQoe re,

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 3/4 ll-l 6,'C~&a46, +~a ~~~~~~q.

3/4. 11. 2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 3'/4 11"3, i Qh s N'orb QC 'v~~QQ 3/4. 11. 3 8 3/4 11-g l PALO VERDE " UNIT 1 XIV AMEHDMEHT HO. 23

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CONTROLLED BY USER INOEX ADMINISTRATIVE CONTROLS "

SECTION PAGE

6. 5. 3 NUCLEAR SAFETY GROUP FUNCTION.... 6-10 COMPOSITIOH............... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-10 CONSULTANTS.................... 6"10 R EVI EMo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-10 AUDITS. 6-11 AUTHORITY....... 6-12 RECORDS.. ~ ~ ~ ~ ~ 6-12 6.6 REPORTABLE EVENT ACTION........................ ......... . .. 6-12

6. 7 SAFETY LIMIT VIOLATIOH.........'........................ 6-13 6.8 PROCEDURES AND PROGRAMS....................... .. ........... 6-13

6. 9 REPORTING RE UIREMENTS

6. 9. 1 ROUTINE REPORTS...... 6-K.c 0 STARTUP REPORT.. 6-K ~

ANNUAL REPORTS......................................-...,.. 6-K ~e MOHTHLY OPERATING REPORT........

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT. 6-%.Zc SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT..... 6-% ZO 6o 9o 2 SPECIAL REPORTS' ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-M. 2(

6. 10 RECORD RETENTION. 6-21 6.11 RADIATION PROTECTION PROGRAM............................... 6"22 6.12 HIGH RADIATION AREA............................... 6"'22 'R 5

6. 13 PROCESS CONTROL PROGRAM......................'.............. 6-+Z~

PALO VERDE " UNIT 1 XVII AMENDMEHT NO 27

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FOR lNFORMATlON ONLY INDEX LIST OF TABLES PAGE 3.'3-9C REMOTE'HUTDOMH CONTROL CIRCUITS. 3/4 3-53 4.3-6 REMOTE SHUTDOWN INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........., 3/4 3-56

3. 3-10 POST-ACCIDEHT MONITORING IHSTRUMEHTATION ............... 3/4 3-58

4. 3-7 POST-ACCIDENT MONITORING INSTRUMEHTATION SURVEILLANCE REQUIREMENTS............................... 3/4 3-60

3. 3-11 LOOSE PARTS SENSOR LOCATIONS............... 3/4 3-62 B %Pal wT.w 3.3 12 K'ONITORING IHSTRUMEHTATION. 3/4 3-64 Kx,P4cwxu%. C ~W 4.3-8 MOHITORING w5 INSTRUMENTATIOH SURVEILLANCE REQUIREMENTS 3/4 3-M.

4. 4-1 MINIMUM NUMBER OF STEAM GEHERATORS TO BE INSPECTED DURIHG IHSERVICE INSPECTION.. 3/4 4-16

4. 4-2 STEAM GENERATOR TUBE INSPECTION......................... 3/4 4-17

3. 4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES........ 3/4 4-21

3. 4-2 REACTOR COOLANT SYSTEM CHEMISTRY........................ 3/4 4-23 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS... 3/4 4-24 4-4 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM.... 3/4 4-27

3. 4" 3 REACTOR COOLANT SYSTEM MAXIMUM ALLOMABLE HEATUP AND COOLDOMN RATES............................... 3/4 4-28a

4. 4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM MITHDRAMAL SCHEDULE... 3/4 4-31 4.6-1 TENDON SURVEILLANCE

- FIRST YEAR........................ 3/4 6-12

4. 6-2 TENDON LIFT-OFF FORCE - FIRST YEAR...................... 3/4 6-13

3. 6-1 CONTAINMENT ISOLATION VALVES....... 3/4 6-21 3~7 1 STEAM LINE SAFETY VALVES Pf R LOOPS....... 3/4 7-2 PALO VERDE - UNIT 1 XXI AMENDMENT NO. 52

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CONTROLLED BY USER INDEX LIST OF TABLES PAGE

3. 7-2 MAXIMUM ALLOWABLE STEADY STATE POWER LEVEL AND MAXIMUM VARIABLE OVERPOWER TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES...... 3/4 7-3

4. 7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM.... 3/4 7-8

4. 8-1 DIESEL GENERATOR TEST SCHEDULE. 3/4 8"7

3. 8" 1 D. C. ELECTRICAL SOURCES...... 3/4 8-11

4. 8" 2 BATTERY SURVEILLANCE RE(UIREMEHTS 3/4 8"12

3. 8-2 'CONTAINMENT PEHETRATIOH CONDUCTOR OVERCURREHT PROTECTIVE DEVICES........ 3/4 8-19

3. 8-3 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AHD/OR BYPASS DEVICES................................... 3/4 8-41 88@t e ~ o ~ ~ ~ ~ e ~ o ~ ~ o e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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B 3/4.4-1 REACTOR VESSEL TOUGHNESS..................... B 3/4 4-8

5. 7-1 COMPONENT CYCLIC OR TRANSIENT I

LIMITS..............,...... 5"7

5. 7-2 PRESSURIZER SPRAY NOZZLE USAGE FACTOR......'....'......... 5-9

6. 2-1 MIHIMUM SHIFT CREW COMPOSITIOH...............'o 6-5 PALO VERDE - UNIT 1 XXII AMENDMENT NO.

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CONTROLLED BV USER DEFI H ITIOHS N-'I-1.16 K 'is the k effective calculated by considering the actual CEA con-figurat(oh and assuming that the fully or partially inserted full-length CEA of the highest worth is fully withdrawn.

MEt 1B ER(S) OF .THE PUBLIC 1.17 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 'lic'en'see,ts 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 recrea-tional, occupational, or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.18 OSE CALCULATION MANUAL shall contain the current and parameters'sed sn n of offsite dos a coactive gaseous 'and liquid effluents,

' in th eous and liquid effluent monitoring alarm/t s, and in the conduct of the env r monitoring program.

OPERABLE " OPERABILITY 1.19 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 1.20 An OPERATIONAL MODE (i.e. MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and cold leg reactor coolant temperature specified in Table 1.2.

I PHYSICS TESTS 1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and (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.

PLANAR RADIAL PEAKING FACTOR " Fx 1.22 The PLANAR RADIAL PEAKING FACTOR is the ratio of the peak to plane average power density of the individual fuel rods in a given horizontal plane, excluding the effects of azimuthal tilt.

.PALO VERDE - UNIT 1 1-4 AMENDMEHT NO. 23

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INSERT 1 1.18 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. 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 Semiannual Radioactive Effluent Release Reports required by Specifications 6.9.1.7 and 6.9.1.8.

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CONTROLLED BY USER DEFINITIONS PRESSURE BOUNDARY LEAKAGE 1.23 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.

PROCESS CONTROL PROGRAM (PCP 1.24 PROCESS CONTROL PROGRAM shall contain the provisions to assure the SOLIDI ON of wet radioactive wastes results in a waste for h properties that m the requirements of 10 CFR Part 61 and of level radioactive waste dispo sites. The PCP shall identif ocess parameters influencing SOLIDIFICATION s as pH, oil content content, solids content, ratio of solidification agent to e and/or essa/y additives for each type of anticipated waste, and the acce e boundary conditions for the process parameters shall be identi for e waste type, based on laboratory scale and full-scale testin hall also include an identification 'of cond testing, to assur sludges ' wil experience. The ns that must be satisfied, ba at dewatering of bead resins, powdered r suit in volumes of free water, at the time of dispo on full-scale and filter within the 1 of 10 CFR Part 61 and of low level radioactive waste disposa s.

PURGE " PURGING 1.25 PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentra-tion, or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POMER 1.26 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3800 Mwt.

REACTOR TRIP SYSTEM RESPONSE TIME 1.27 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 electrical power is interrupted to the CEA drive mechanism.

REPORTABLE EVENT mouw,4 page l-t 1.28 A REPORTABLE EVENT shall be any of those conditions specified in Sections 50.72 and 50.73 to 10 CFR Part 50.

0 PALO VERDE - UNIT 1 1-5 AMENDMENT NO. 2~

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INSERT 2 1.24 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

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DEFINITIONS--

SHUTDOWN MARGIN 1.29 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

a. No change in part-length control element assembly position, and

b. All full-length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully withdrawn.

SITE BOUNDARY 1.30 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

SOFTWARE 1.31 The digital computer SOFTWARE for the reactor protection system shall be the program codes including their associated data, documentation, and procedures.

SOURCE CHECK 1.3$ A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

STAGGEREO TEST BASIS 3

1.3$ A STAGGERED TEST BASIS shall consist of:

a. A test schedule for n systems,'ubsystems, trains, or other designated components obtained by dividing the specified test interval into n equal subintervals, and

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

THERMAL POWER 1.3$ THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

PALO VERDE " UNIT 1 1-6 AMENDMENT NO. 23

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DEFIHITIONS UNIOEHTIF.IED., LEAKAGE 35 1.3$ UNIDENTIFIED LEAKAGE shall be all leakage which does not constitute either IDENTIFIED LEAKAGE or reactor coolant pump controlled bleed-off flow.

UNRESTRICTED AREA 34 1.3lt An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

VENTILATIOH EXHAUST TREATMENT SYSTEM 3%

1.3$ A VEHTILATIOH EXHAUST TREATMENT SYSTEM shall be any system designed and installed .to reduce, gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or partic-ulates from the gaseous exhaust stream prior to the release to the environment.

Such a system is not considered to have any effect on noble gas effluents.

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATIOH EXHAUST TREATMENT SYSTEM components.

VENTING 3'5 1.3~ VENTING shall be the 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 not provided or required during VENTING. ,Vent, used in system names, does not imply a VENTING process.

PALO VERDE - UNIT 1 1-7 AMEHDMEHT HO 23

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CONTROLLED BY USER INSTRUMENTATION E,XP<O>%ATE'~S

/MONITOR IHG INSTRUrl<ENTATION LIMITING CONOITION FOR OPERATION Q.g.ph~S'i+ + QZ4+

3.3.3.8 The monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3. 11.2. are not exceeded.

APPLICABILITY: As shown in Table 3.3-12.

ACTION:

Q.aa. phD%,iM g Cf 8 S a ~ With moni torino instrumenta-tion channel alarm/trip setpoint less conservative than required by the above Specification, declare, the channel inoperable@

<Elmer 9e gs3 (gal Ms%Std~ %~she~ iw Wo ohcs- iL.E-A ~

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~(@it.yo. gas monitoring instrumentation channels OPERABLE, take the ACTION shown in Tab1e 3.3-12. Restore the inoperab1e instrumentation to OPERABLE status within 30 days and, if not corrected l& Ea

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SURVEILLANCE REQUIREMENTS Chas @Kern>s,~q, +eL5

.4.3.3.8 Each monitor ing instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, ~fKE-

~F, CHANNEL CALIBRATION, and CHANNEL FUHCTIONAL TEST operations at frequencies shown in Table 4.3-8.

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PALO VEROE - UNIT I 3/4 3-63 AHENDPEHT. NO.

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C2 HONITORING INSTRUMENTATION C2 m MINIHUH CHANNELS I INSTRUMENT OPERABLE APPLICABILITY ACTION

1. GASEOUS RADWASTE SYSTEH

a. Noble Gas Activity Monitor- QQQc, YC Providing Alarm and Automatic Termination of Release 8RU-12 35 A

b. Flow Rate Monitor 0 R

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HONITORIHG SYSTEM EXPLOSIVE GAS 0

a. Oxygen Moni tor 39 IYi D

63 M

rsvp Xl ACTION 39 " With the number of channnels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of the GASEOUS RAOWASTE SYSTEM may continue provided grab samples are taken and analyzed daily. With both channels inoperable rn C) operation may continue provided grab .samples are taken and m analyzed (1) every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during degassing operations, and

<2) daily during other operations.

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RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INS MENT OPERABLE APPLICABILITY ACTION CONDENSER EVAC ION SYSTEM A. Low Range Mons rs

a. Noble Gas Act ity Honitor 8RU-141 1 3 *'Jt* 4*%* 37 3

b. Iodine Sampler 1 3 )KATE 4**% 40

c. Particulate Sampler 1 3 **8 4'A'A* 40

d. Flow Rate Monitor 1 3 A'A'A' A'AA 36 0

e. Sampler Flow Rate Measuring De ce- 1 3 'A'kill 4*** 36 l B. High Range Monitors U AA'* 4K*A D3

a. Noble Gas Activity Monitor 8RU-142 3 42

b. Iodine Sampler 1 3 'AA* 4*** 42 C

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c. Particulate Sampler 1 3 42 N

d. Sampler Flow Rate Heasuring Device 1 3

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.PLANT VENT 'SYSTEM A. Low Range Monitors

a. Noble Gas Activity Monitor PRU-143 1 37

b. Iodine Sampler 1 40

c. Particulate Sampler 1 4O

d. Flow Rate Monitor 1 36

e. Sampler Flow Rate Measur ing Device 1 o

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TARLF. 3.3-12 (Continued)

RAO IOACT I VE GAS EOlJS FFFl lJEHT HOH I TOR I HG IHSTRlJHEHTAT ION H IH IHUH CJJAHHELS IH UHEHT OPERABLE APPL I CAB I L IT Y ACTION

4. PLANT YEHT SY (Continued)

B. lligh Range Honi s

a. Hoble Gas Actlv Honitor PRlJ-144

b. Iodine Sampler 1 4P

c. Particulate Sampler 1 42

d. Sampler Flow Rate Heasuring ice I

5. FUEL BUILDIHG VEHTILATIOH SYSTEH &%RE.~R A. Low Range Honitors

a. Noble Gas Activity Honitor Nl/-145 37,41

b. Iodine Sampler 40

c. Particulate Sampler 4n

d. Flow Rate Honitor 36

e. Sampler Flow Rate Heasuring Oevice 36 R, lligh Range Honitors

a. Hoble Gas Activity Honitor PRlJ- 146 41,42

b. Iodine Sampler 42 c~ Particulate Sampler

d. Sampler Flow Rate Heasuring Device

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, " A all times.

TABLE NOTATION EQQYG Dur' GASEOUS RAOWASTE SYSTEM operation.

~*~,;When er the condenser air removal system is in operation, or whenever turbin glands are being supplied with steam from sources other than the au~xi 1 ia boi 1 er(s).

¹ During wa te gas release.

¹¹ In MODES 1, 2, 3, and 4 or when irradiated fuel is in the fuel storage pool.

ACTION 35 - Wi the number of channels OPERABLE less than required by the Mini um Channels OPERABLE requirement, the contents of the tank( may be released to the environment provided that prior to init ating the release:

a. At le st two independent samples of the tank's contents are an lyzed, and

b. At least o technically qualified members of the facility staff indep ndently verify the release rate calculations and discharg valve lineup; Otherwise, suspend r lease of radioactive effluents via this pathway.

ACTION 36 " t Wi h the number of charm s OPERABLE less than required by the Minimum Channels OPERABLE quirement, effluent releases via this pathway may continue p vided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 37- - With the number of channels OPER LE less than required by the Minimum Channels OPERABLE require nt, effluent releases via this pathway may continue provided e act;ions of (a) or (b) or (c) are performed:

a. Initiate the Preplanned Alternate mpling Program to monitor the appropriate parameter(s).

b. Place moveable air monitors in-line.

c.'ake grab samples at least once per 12 hou ACTION 38 With the number of channels OPERABLE less than req ired by the Minimum Channels OPERABLE requirement, immediately spend PURGING of radioactive effluents via this pathway.

ACTION 39- With the number of channnels OPERABLE one less than requ red by the Minimum Channels OPERABLE requirement, operation o the GASEOUS RADWASTE SYSTEM may continue provided grab samples're taken and analyzed daily. With both channels inoperable operation may continue provided grab .samples are taken and analyzed (1) every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during degassing operations, and (2) daily during other operations.

PALO VERDE " UNIT 1 3/4 3-67 AMENDMENT NO.

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CONTROLLED BY USER TABLE 3.3-12 (Continued)

TABLE NOTATION A ON 40 " With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the effected pathway may continue provided samples are contin-uously collected with auxiliary sampling equipment as required Table 4.11-2 within one hour after the channel has been de red inoperable.

ACTION 41- With the ber of channels OPERABLE less than required by the Minimum Chan ls OPERABLE requirements, comply with the ACTION b of Specificatio .9. 12 or operate the fuel building essential ventilation system ile moving irradiated fuel.

ACTION 42 - With the number of channe OPERABLE less than required by the Minimum Channels OPERABLE re irement restore the channel to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

'a 0 Initiate the Preplanned Alternate ampling Program to monitor the appropriate parameter(s en it is needed.

b. Prepare and submit a Special Report to the mmission pursuant to Specification 6.9.2 within 30 day ollowing the event outlining the action(s} taken, the cau of the inoperability, and the plans and schedule for restor the system to OPERABLE status.

E4EY PALO VERDE - UNIT 1 ,

3/4 3-68 AMENDMENT NO. 27

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MONITORING INSTRUMENTATIOH SURVEILLANCE RE UIREMENTS CHANNEL 'ODES IH MHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK 'HECK CALIBRATIOH . TEST IS RE UIRED l.. GASEOUS RADMASTE SYSTEM

a. Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release RU-'12 P(7) R(3) Q(l), (2), P¹¹¹ ¹

b. Flow Rate Monitor H.A. Q,P¹¹¹ z

2. GASEOUS RAOMASTE SYSTEM 0 EXPLOSIVE GAS MONITORING SYSTEM 33

a. Oxygen Monitor (Surge tank) 0 H.A. Q(4)

b. Oxygen Monitor (Waste gas header) O H.A. a(4) 0 z

0 z

(4) The CHANNEL CALIBRATIOH shall include the use of standard gas samples containing a nominal:

1. One volume percent oxygen, balance nitrogen, and

2. Four volume pe".cent oxygen, balance nitrogen.

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4.3-8 (Continued) 0 RADIOACTIVE GASE04~ EFFLUEHT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMEHTS CHANNEL MODES IH MHICM CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLAHCE INSTRUMENT CHECK CHECK CALIBRATION TEST IS RE UIRED

3. CONDENSER EVACUATIO SYSTEM (RU-141 and RU-142)

a. Noble Gas Activity Monit D(5) M(7) R(3) 3 %*A 4%)k A

b. Iodine Sampler H.A. H.A. N.A. H.A. 3 *lac* 4*%*

XI

c. Particulate Sampler H.A. H.A. H,A. 3

'kA 4k**

z, A'*A 4)k**

d. Flow Rate Monitor D(6) H.A. 3

.A. 3 *A* 4**4

e. Sampler Flow Rate Measuring D(6) l Device CD

4. PLANT VENT SYSTEM 0 (RU-143 and RU-144) r.

a. Noble Gas Activity Monitor D(5) M(7) R(3) a(2)

b. Iodine Sampler N.A. H.A. N.A. N.A.

c. Particulate Sampler H.A. H.A. H.A. .A.

d. Flow Rate Monitor D(6) - H.A.

CD m e. Sampler Flow Rate Measuring D(6) N.A.

Device CD

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TABLE 4.3-8 (Continued)

RADIOACTIVE GASEOUS EFFLUEHT MONITORING INSTRUMEHTATIOH SURVEILLANCE RE UIREMEHTS m

C7 CHANNEL MODES IH WHICH .

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE CHECK CALIBRATIOH TEST IS RE UIRED g INSTRUMENT CHECK

5. FUEL BUILDING VEHTILA OH SYSTEM (RU-145 and RU-146)

a. Noble Gas Actvity Monitor D(5) M(7) R(3) s(~)

b. Iodine Sampler N.A. H.A. H.A. N.A.

c. Particulate Sampler H.A. H.A. H.A.

d. Flow Rate Monitor D(6) N.A. 0 Xl Sampler Flow*Rate Measuring D(6)

Device 0

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ring TABLE NOTATIONS GASEOUS RADWASTE SYSTEM operation.

Wh ever the condenser air removal system is in operation, or whenever turb e glands are being supplied with steam from sources other than the auxil> ry boiler(s).

¹ During ste gas release.

During M ES j., 2, 3 or 4 or with irradiated fuel in the fuel storage pool.

¹¹¹ Functional test should consist of, but not be limited to, a verification of system isola ion capability by the insertion of a simulated alarm condition.

The CHANNEL FU TIOHAL TEST shall also demonstrate that automatic isolation of this pathway curs if the instrument indicates measured, levels above the alarm/trip set oint.

(2) The CHANNEL FUNCTION TEST shall also demonstrate that control room alarm annunciation occ s if any of the following conditions exists:

1. Instrument indicate measure ~ve the alarm setpoint.

2. Circuit failure.

3. Instrument indicates a d n a> ure.

4. Instrument controls not se in operate mode.

(3) The initial CHANNEL CALIBRATIOH sh 1 be performed using one or more of the reference standards certified by the National Bureau of Standards (HBS) or using standards that have be obtained from suppliers that participate in measurement assurance ac ivities with NBS. These standards shall permit calibrating the system over ts intended range of energy and measurement range. For subsequent CHANNEL ALIBRATIOH, sources that have been related to the initial calibration shal be used.

(4) The CHANNEL CALIBRATIOH shall include the use o standard gas samples containing a nominal:

1. One volume percent oxygen, balance nitrogen, a

2. Four volume pe~cent oxygen, balance nitrogen.

(5) The channel check for channels in standby status shall con ist of verification that the channel is "on-line and reachable."

(6) Daily channel check not required for flow monitors in standby 'tus.

(7) LED may be utilized as the check source in lieu of a source of in eased radioactivity.

PALO VERDE - UNIT 1 3/4 3-72 AMEHDMEHT NO. 56

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3 .11 RADIOACTIVE EFFLUEHTS 3/4.1 1 SECONDARY SYSTEM LI UID WASTE DISCHARGES TO ONSITE EVAPORATION PONDS CONCEN TION LIMITING COND ION FOR OPERATION l.

3. 11. 1 The conce tration of radioactive material discharged from secondary system liquid waste t the onsite evaporation ponds shall be limited to the lower limit of detectab'ty (LLD) defined as 5 x 10-7 pCi/ml for the prin-cipal gamma emitters or 1 10- pCi/ml for I-131.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

When any secondary system liquid wast discharge pathway concentration determined in 'accordance with the surve'ance requirements given below exceeds the specified LLD, divert -that discharge thway to the liquid radwaste system without delay or process the liquid wastes meet the specified limits prior to release to the onsite evaporation ponds.

SURVEILLANCE RE UIREMENTS 4.11.1.1.1 Radioactive liquid wastes collected in the ch ical waste neutralizer tank shall be sampled and analyzed prior to their batchwise ischarge to the onsite evaporation pond in accordance with the sampling and a lysis program specified in Table 4.11-1.

4. 11. l. 1.2 With the concentration of radioactive material in the c ical waste neutralizer tank exceeding the specified LLD, sample and analyze other secondary system discharge pathways in accordance with the samplin'g and alysis program specified in Table 4.11-1.

U%4%Y E PALO VERDE - UNIT 1 3/4'1-1 AMEHDMEHT NO. 54

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TABLE 4.11"1 RADIOACTIVE LI UID WASTE SAMPLIHG AHD ANALYSIS PROGRAM v.

SECONDARY SYSTEM LI~VIO RELEASE PATHWAY i x AMPLING FREQUENCY MINIMUM ANALYSIS FREQUENCY TYPE OF.

ACTIVITY ANALYSIS LOWER LIMIT OF DETECLIOH (LLD)

(pCi/mL) b A. ~Bh di 1; Chemical Waste P P Principa) Gamma 5x10-~

Neutralizer Tank Ea Each Emitters Bat Batch I"131 1x10-6

2. Steam Generator P P Principa) Gamma 5xlO-7 Blowdown Low Each ach Emitters TDS Sump" Batch tch I"131 1x10-s

3. Condensate P P. 'Principa) Gamma 5x10-~

Polishing Low Each Each Emi tters TDS Sump""- Batch Batch "131 1xl0-a B. Continuous Releases d

1. Turbine Building 0 0 Principa) Gamma 5x10-7 Sump" Grab Grab Emitters Sample Sample I-131 1x10-6

2. Condenser Area 0 0 Principa) Gaaaaa 5x10-7 Sumps" Grab Grab Emi tters Sampl e Sample "I-131 1x 0-6 t "Sampling and analysis for pathwa s 2 and 3 un ous r ea req waste neutralizer tank pathway exceeds a

ed o er batch discharges and when he LLD.

entr at for 1 and 2 al

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TABLE NOTATION

~ he LLD is defined, for purposes of these specifications, as the smallest c centration of radioactive material in a sample that will yield a net cou t, above system background, that will be detected with 95% probability with nly 5% probability of falsely concluding that a blank observation repres ts a "real" signal.

For a par 'cular measurement system, which may include radiochemical separation:

4.66 sb LLD =

E ~ V:i 2.22 x 106 ~

Y ~

exp (-Mt)

I Where: ti LLD is the "a prior"e lower limit of detection as defined above, as microcuries per u t,mass or volume, ls I

s is the standard devia ion of the background counting rate or of tile counting rate of a bl k<sample as appropriate, as counts per minute, E is the counting efficiency, counts per disintegration, V is the sample size in units of ss or volume,

., 2.22 x 106 is the number of disinteg tions per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A, is the radioactive decay constant for the articular radionuclide, and bt for plant effluents is the elapsed time betwe n the midpoint of sample collection and time of counting.

Typical values of E, V, Y, and bt should be used in e calculation.

It should be recognized that the LLD is defined as an a grior'before the fact) limit representing the capability of a measurement s tern and not as an a ~osteriori (after the fact) limit for a particular m surement.

b 4 A batch release is the discharge of liquid wastes of a discrete vol e.

to sampling for analyses, each batch shall be isolated, and the 'rior thoroughly mixed to assure representative sampling.

PALO VERDE - UNIT 1 3/4 11-3

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TABLE NOTATION incipal gamma emitters for which the LLO specification applies include ollowing radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, - 37 and Ce-141. Ce-144 shall also .be measured, but with an LLO of 5 x 10- . list does not mean that only these nuclides are to be considered. Other gam aks that are identifiable, together with those of the above nuclides, shall ge analyzed and reported in the Semiannual Radioactive Effluent Release e pursuant to Specifica-tion 6.9. 1.8.

d A continuous release is the discharge of liquid wastes of a no crete volume, e.g., from a volume of a system that has an input flow durin continuous release.

PALO VERDE - UNIT 1 3/4 11-4 ILILED H'SEIR

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ADIOACTIVE EFFLUENTS DOS LIMITING ONDITION FOR OPERATION 3.11.1.2 The. se or dose commitment to a MEMBER OF THE PUBLIC from radioactive mate 'als in liquid effluents released, from each reactor unit, to areas at and be nd the SITE BOUNDARY (See Figure 5.1-1) shall be limited:

a. During any c lendar quarter to less than or equal to 1.5 mrems to the total body an to less than or equal to 5 mrems to any organ, and

b. During any calend year to less than or equal to 3 mrems to the total body and to 1 s than or equal to 10 mrems to any organ.

APPLICABIL'ITY: At al 1 times.

ACTION:

a. With the calculated dose from e release of radioactive materials in liquid.,effluents exceeding an of the above limits, prepare and submit to the Commission within 3 days, pursuant to Specifica-tion 6. 9. 2, a Special Report that i ntifies the cause(s) for exceeding the l,imit(s) and defines th corrective actions that have been taken to reduce the releases and t proposed corrective actions to be taken to assure that subsequent rel ses will be in compliance with the above limits.

b. The provisions of Specifications 3.0.3 and 3.0. are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the r rent calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the OOCM at least once 31 days.

PALO VERDE - UNIT 1 3/4 11-5

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3/, iq RADIOACTIVE EFFLUENTS (9'IMITING CONDITION FOR OPERATION

3. 11. 1.+ The quantity of radioactive material contained in each outside temporary tank and the reactor makeup water tank shall be limited to less than or equal to 60 curies, excluding tritium and dissolved or entrained noble gases'PPLICABILITY:

At al 1 times.

ACTION:

With the quantity of radioactive material in any outside temporary tank or the reactor makeup water tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit.

b. The provisions of Specifications 3. 0. 3 and 3. 0. 4 are not applicable.

SURVEILLANCE REQUIREt1ENTS 4.11.1.+ The quantity of radioactive material contained in each outside temporary tank and the reactor makeup water tank shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

PALO VERDE - UNIT 1 3/4 11-(

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'DIOACTIVE EFFLUENTS 3/4. 1.2 GASEOUS EFFLUENTS DOSE RA LIMITING CON TION FOR OPERATION 3.11.2.1 The dose ate due to radioactive materials released in gaseous effluents from the s e (see Figures 5.1-1 and 5.1-3) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less tha or equal to 3000 mrems/yr to the skin, and

b. For I-131 and I-133, or tritium, and for all radionuclides in particulate form with h lf-lives greater than 8 days: Less than or equal to 1500 mrems/y to any organ.

APPLICABILITY: At al times.

1 HEQKY6 ACTI>N:

With the dose rate(s) exceeding the above lim'ts, immediately decrease the release rate to within, the above limit(s).

SURVEILLANCE RE UIREMENTS

4. 11.2. l. 1 The dose rate due to noble gases in gaseous ef uents shall be determined to be within the above limits in accordance with e methods and procedures of the ODCM.

4.11.2. 1.2 The dose rate due to I-131, I-133, Tritium and all ra onuclides in particulate form with half-lives greater than 8 days in gaseous eff ents shall be determined to be within the above limits in accordance with the me ods and procedures of the ODCM by obtaining representative samples and performs analyses in accordance with the sampling and analysis program specified Table 4. 11-2.

PALO VERDE - UNIT 1 3/4 11-7

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TABLE 4. 11-2 RAOIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT OF SAMPLING ~

ANALYSIS TYPE OF OETECTION (LLO)

GASEOUS RELEASE TYP FRE UENCY ACTIVITY ANALYSIS FRE UENCY ( Ci/ml)

P P A. Waste Gas Storage ch Tank Each Tank Principal Gamma Emitters lx10 Tank Gra Sam le P P B. Containment Purge Each Purge G ra b c

Each Purge 'rincipal b,c Gamma Emitters 1x10 Sam le H-3 lxlO

1. Condenser Vacuum ',e C. H Principal Gamma Emitters 1xlO Pump Exhaust Grab

2. Plant Vent Sample

3. Fuel Bldg. 1x10 Exhaust Continuous 4/M lxlO Charcoal Sam le I-133 lxlO Continuous 4/H Principal Gam Emitters lxlO Particulate (I-131, Others)

Sam le Continuous f H Gross Alpha lxlO Composite Particulate Sam le Continuous f Sr-89, Sr-90 O-ll Composite Particulate Sam le D. All Radwaste Types Continuous f Noble Gas Noble Gases 1xlO as listed in A., B., Monitor Gross Beta or Gamma and C. above.

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CONTROLLED B')t'SER TABLE 4. 11-2 Continued TABLE NOTATION ilityy The D is the smallest concentration of radioactive material in a sample that will ys ld a net count above background that will be detected with 95K.probab-wi 5~ probability of falsely concluding that a blank observation repres-ents a "re 1" signal.

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

4.66 sb LLD E ~

V ~

.22 x 10 ~

Y . exp I

(-&t)

Mhere:

LLD is the "a prio i" lower limit of detection as defined above (apr pCi per unit mass or volume Current literature defines the LLD as the thtection capability for the in trumentation, onl and the HDC minimum detectable con-centration, as the dete tion c 1 t a given instrument procedure and type of sample.

EcEW s is the standard deviati the b c round counting rate or of: the coun-t)ng rate of a blank sample appr priate (as counts per minute),

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

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

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

A, is the radioactive decay constant for he particular radionuclide, and bt is the elapsed time between the midpoin of sample collection aod time of counting (for plant effluents, not enviro mental samples).

The value of sb used in the calculation of the LLD for a detectionrsystem shall be based on the actual observed variance the background counting or of the counting rate of the blank samples (as appropriate) rather 'ate than on an unverified theoretically predicted varia ce. In calculating the LLD for a radionuclide determined by gamma-ray spect metry the background should include the typical contributions of other rado nuclides normally present in the samples. Typical values of E, V, Y, and t

'1'"

should be used in the calculation.

It should be recognized that the LL0 is defined as an a priori (b fore the fact)

(after v

the il fact) limit for a particular measurement".

!' E limits, v

For a more complete discussion of the LLD, and other detection e the following:

(I) HASL Procedures Manual, HSAL-300 (revised annually).

(2) Currie, L. A., "Limits for gualitative Oetection and guantitative Deter in-ation - Application to Radiochemisty" Anal. Chem 40, 586-93 (1968).

(3) Hartwell, J. K., "Detection Limits for Radioisotopic Counting Techniques,"

Atlatic Richfield Hanford Company Report (ARH-2537 (June 22, 1972).

PALO VERDE " UNIT 1 3/4 11-9 AMENDMENT NO. 27

If 4

TABLE 4. 11-2 (Continued)

TABLE NOTATION b

Analyses shall also be performed following SHUTDOWN, STARTUP, or a ERHAL POWER change exceeding 15K of the RATED THERl1AL POWER within a 1- our period if 1) analysis shows that the DOSE EQUIVALENT I-131 con ntration in the primary coolant has increased more than a factor of 3; an 2) the noble gas activity monitor on the plant vent shows that efflue activity has increased by more than a factor of 3. If the associat d noble gas vent monitor is inoperable, samples must be obtained as soon a possible. Analyses shall be performed within a four-hour period. Th's requirement does not apply to the Fuel Building Exhaust.

Sampling and a lyses shall also be performed at least once per 31 days when purging ti exceeds 30 days continuous.

d Samples shall be ch nged at least 4 times a month and analyses shall be completed within 48 urs after changing (or after removal from sampler).

When samples collecte for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a f tor of 10 ~

e Tritium grab samples shall e taken at least monthly from the ventilation

-exhaust from the spent fuel ol area, whenever spent fuel is in the spent fuel pool.

fThe ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period cover by each dose or dose rate calculation made in accordance with Specificatio 3. 11. 2. 1, 3. 11. 2. 2, and 3. 11. 2. 3.

The principal gamma emitters for which e LLD specification applies include the following radionuclides: Kr- 7, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions a t1n-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce- 44 for particulate emissions.

This list does not mean that only these nucli s are to be detected and reported. Other peaks which are measureable an identifiable, together with the above nuclides, shall also be identifie and reported in the Semiannual Radioactive Effluent Release Report.

PALO VERDE - UNIT 1 3/4 11-10

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RADIOACTIVE EFFLUENTS SE - NOBLE GASES LIMI G COHDITIOH FOR OPERATION t

3.11.2,2 e air dose.due to noble gases released in gaseous effluents, from each reactor nit, to areas at and beyond the SITE BOUHDARY (see Figures 5. 1-1 and 5.1-3)'sha 1 be limited to the following:

a. During ny calendar quarter: Less than or equal to 5 mrads for gamma radiatio and less than or equal to 10 mrads for beta radiation and,

b. During any lendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY: At al 1 tim ACTION With the calculated ai dose from radioa"tive noble gases in gaseous effluents exceeding any the above limits, prepare and submit to the Commission within 30 s, pursuant to Specification 6.9.2, a Special, Report that identif s the cause(s) for exceeding the limit(s) and defines the corrective ac ions that have been taken to reduce the releases and the proposed corr tive 'actions to be taken to assure that subsequent releases will be in compliance with the above limits.

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

SURVEILLANCE RE UIREMENTS

4. 11.2.2 Cumulative dose contributions for the curren calendar quarter and current calendar year for noble gases shall be determin in accordance with the methodology and parameters in the ODCM at least once r 31 days.

PALO VERDE - UNIT 1 3/4 11-11

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RADIOACTIVE EFFLUENTS 0 E - IODINE-131, IODINE-133 TRITIUM, ANO RADIONUCLIOES IN PARTICULATE FORM

'LIMIT G CONDITION FOR OPERATION 3.11.2.3 T dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and ll radionuclides in particulate form with half-lives greater than 8 days in gase s e ff1uents released, fr om each reactor unit, to areas at and beyond the SITE OUNDARY (see Figures 5.1-1 and 5.1-3) shall be limited to the following:

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

b. During any cale dar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY: At al l times.

ACTION:

a. With the calculated dose om the release of iodine-131, iodine-133, tritium, and radionuclides particulate form with half-lives greater than 8 days, in gaseous efflu ts exceeding any of the above limits, prepare and submit to the Comm sion within 30 days, pursuant to Specification 6.9.2, a Special R ort that identifies the cause(s) for exceeding the limit and define the corrective actions that have been taken to reduce the releases a the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions'of Specifications 3.0.3 an 3.0.4 are not applicable.

SURVEILLANCE RE UIREh1ENTS 4.11.2.3 Cumulative dose contributions for the current calen r quarter and current calendar year for iodine-131, iodine-133, tritium, nd radionuclides in particulate form with half-lives greater than 8 days shall be etermined in accordance with the methodology and parameters in the ODCM at leas once per 31 days.

PALO VERDE - UNIT 1 3/4 11-12

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3. 11.2.4 he GASEOUS RADWASTE SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shal be used to reduce radioactive materials in gaseous waste prior to their discha e when the projected gaseous effluent air doses due to gaseous effluent relea es, from each reactor unit, from the site (see Figures S. 1-1 and 5. 1-3), whe averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 rad for beta radiation.'he VENTILATION EXHAUST TREATMENT SYSTEM shall be use to reduce radioactive materials in gaseous waste prior to their discharge w n the projected doses due to gaseous effluent releases, from each reactor unit to areas at and beyond the SITE BOUNDARY (see Figures 5. 1-1 and 5. 1-3 when averaged over 31 days would exceed 0. 3 mrem to any organ of a MEMBER OF E PUBLIC.

APPLICABILITY: At al 1 times.

ACTION:

a. With radioactive gaseous aste being discharge'd without treatment and in excess of the above limits, prepare and submit to the Commis-sion within 30 days, pursua to Specification 6.9,2, a Special Report which includes the following 'ormation:

~l.-~ the Identification of the inope ble reason for inoperability, equipment or subsystems and

2. Action(s) taken to restore the 1 operable equipment to OPERABLE status,'nd

3. Summary description of action(s) tak to prevent a recurrence.

b. The provisions of Specifications 3.0.3 and 3..4 are not applicable.

SURVEILI ANCE RE UIREMENTS

4. 11.2.4 Doses due to gaseous releases from the site shall be p jected at least once per 31 days, in accordance with the methodology and pa meters in the ODCM.

PALO VERDE - UNIT 1 3/4 11-13

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,'ll. p GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION

3. ll.gg shall The quantity of radioactivity contained be limited to less than or equal to 170,000 in each gas storage tank curies noble gases (considered as Xe-133).

APPLICABILITY: At all times.

ACTION'.

With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit.

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

SURVEILLANCE RE UIRB1ENTS

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4. 11.+g The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 7 days when radioactive materials are being added to the tank and the quantity of radioactivity contained in the tank is less than or equal to one-half of the above limit; otherwise, determine the quantity of radioactive material contained in the tank at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during addition.

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/4. 11. 3 SOLID RADIOACTIVE WASTE LIM ING CONDITION FOR OPERATION 3.11.3 e solid radwaste system shall be OPERABLE and used, as-'applicable in accordance i th a PROCESS CONTROL PROGRAM, for the SOLIDIFICATION and packaging of radioacti e wastes to ensure meeting the requirements of 10 CFR Part 20 and of 10 CFR Par 71 prior to shipment of radioactive wastes from the site.

APPLICABILITY: al 1 times.

ACTION:

a ~ With the pac ging requirements of 10 CFR Part 20 and/or 10 CFR Part 71 not sa isfied, suspend shipments of defectively packaged solid radioactiv wastes from the site.

b. With the solid radw ste system inoperable for more than 31 days, prepare and submit t the Commission within 30 days pursuant to Specification 6.9.2 a ecial Report which includes the foll;.wing information:

AGLEY'.

Identification of the noperable equipment or subsystems and the reason for inoperabi lit

2. Action(s} taken to restore he inoperable equipment to OPERABLE status,

3. A description of the alternativ used for SOLIDIFICATION and packaging of radioactive wastes, nd

4. Summary description of action(s) tak n to prevent a recurrence.

I C. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.3.1 The solid radwaste system shall be demonstrated OPERABLE t least once per 92 days by:

a. Operating the solid radwaste system at least once in the pre ous 92 days in accordance with the PROCESS CONTROL PROGRAM, or

b. Verification of the existence of a valid contract for SOLIDIFICAT N

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PALO VERDE - UNIT 1 3/4 11-16

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CC'NTRQKEEB SV MUSER DIOACTIVE EFFLUENTS SURVEILL CE 'REQUIREMENTS (Continued) 4.11.3.2 THE PR SS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION of at least one rep sentative test specimen from at least every tenth batch of each type of wet r ioactive waste (e.g., spent resins, evaporator bottoms, and boric acid solutions

a. If any test specime fails to verify SOLIDIFICATION, the SOLIDIFICATION of the tch under test shall be suspended until such time as additional test ecimens can be obtained, alternative

, SOLIDIFICATION parameters be determined in accordance with the PROCESS CONTROL PROGRAM, and subsequent test verifies SOLIDIFICA-TION. SOLIDIFICATION of the bat may then be resumed using the alternative SOLIDIFICATION paramet s determined by the PROCESS CONTROL PROGRAM.

b."'f the initial test specimen from a batch waste fails to verify all provide for the SOLIDIFICATION, the PROCESS CONTROL PROGRAM collection and testing of representative test s cimens from each consecutive batch of the same type of wet waste u il at least three consecutive initial test specimens demonstrate OLIDIFICATION.

'he PROCESS CONTROL PROGRAM shall be modified as requi d, as provided in Specification 6.13, to assure SOLIDIFICATION of subseq nt batches of waste.

PALO VERDE - UNIT 1 3/4 11-17

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/4.11.4 TOTAL DOSE LIMI NG CONDITION FOR OPERATION 3.11.4 e annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLI due to releases of radioactivity and to radiation from uranium fuel cycle sourc shall be limited to less than or equal to 25 mrems to the total body or any o an, except the thyroid, which shall be limited to less than or equa'l to 75 mr s.

APPLICABILITY: A al 1 times.

ACTION:

a. With the calc lated doses from the release of radioactive materials in liquid and seous effluents exceeding twice the limits of Speci-fications.3. 11. 1. a., 3. 11. 1.2b., 3. 11.2.2a., 3. 11.2.2b., 3. 11.2.3a.,

or 3. 11.2.3b., ca ulations should be made including direct radiation contributions from' reactor units and from outside storage tanks to determine whether he above, limits of Specification 3. 11.4 have been exceeded. If suc is the case, prepare and submit to the Commission within 30 day pursuant to Specification 6.9.2, a Special Report that defines the co rective action to be taken to reduce sub-sequent releases to prevent ecurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, defined in 10 CFR 20.405c, shall include an analysis that estimat s the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium uel cycle sources, including all effluent pathways and direct radiat n, for the calendar year that includes the release(s) covered by th's report. It shall also describe levels of radiation and concentrations f radioactive material involved, and the cause of the exposure levels or oncentrations. If the esti-mated dose(s) exceeds the above limits, a if the release condition resulting in violation of 40 CFR Part 190 h s not already been corrected, the Special Report shall include request for a variance in accordance with the provisions of 40 CFR Pa t 190. Submittal of the report is considered a timely request, and a variance is granted unti staff action on the request is complete.

1

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

SURVEILLANCE RE UIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous efflu nts shall be determined in accordance with Specifications 4. 11. 1.2, 4. 11.2.2, an

4. 11.2.3, and in accordance with the methodology and parameters in the 0 CM.

4. 11.4. 2 Cumulative dose contributions from direct radiation from the reac or units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in Specification 3. 11.4a.

PALO VERDE - UNIT 1 3/4 11-18

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3/4. 12 RADIOLOGICAL ENVIRONMENTAL MONITORING

4. 12. 1 MONITORING PROGRAM LIHI G CONDITION FOR OPERATION 3.12.1 Th radiological environmental monitoring program shall be conducted as specified in Table 3. 12-1.

APPLICABILITY: t al 1 times.

ACTION:

a~ With the ra ological environmental monitoring program not being conducted as ecified in Table 3. 12-1, prepare and submit to the Commission, in he Annual Radiological Environmental Operating Report required by Spec ication 6. 9. 1. 7, a description of the reasons for not conducting the rogram as required and the plans for preventing a recurrence.

b. With the level of radi ctivl y as the result of plant effluents in an environmental samplin medium at a specified location exceeding the reporting levels of Ta le 3. 12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Spe ial Report that identifies the cause(s}

for exceeding the limit(s} and efines the corrective actions to be taken to reduce radioactive effl ents so that the potential annual dose" to A MEMBER OF THE PUBLIC i less than the calendar year limits of Specifications 3. 11. 1.2, 3. 11.2. and 3. 11.2.3. When more than one of the radionuclides in Table 3. -2 are detected in the sampling medium, this report shall be submitted if:

concentration 1) concentrati (2) +

reporting level (1) reporting leve (2)

When radionuclides other than those in Table 3. 2-2 are detected and are the result of plant effluents, this report all be submitted if the potential annual dose" to A MEMBER OF THE PUB C is equal to or greater than the calendar year limits of Specificat ons 3. 11. 1. 2,

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3. 11.2.2, and 3. 11.2.3. This report is not required the measured level of radioactivity was not the result of plant ef uents; however, in such an event, the condition shall be reported and d cribed in the Annual Radiological Environmental Operating Report.

C. With milk or fresh leafy vegetable samples unavailable from e or more of the sample locations required by Table 3. 12-1, identi locations for obtaining replacement samples and add them to the adio-logical environmental monitoring program within 30 days. The spe ific "The methodology and parameters used to estimate the potential annual dose to a MEMBER OF TME PUBLIC shall be indicated in this report.

PALO VERDE - UNIT 1 3/4 12-1 ZG~jlTRQILL.EG BV VSER

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ACTI : (Continued) locations from which samples were unavailable may then be deleted rom the monitoring program. Pursuant to Specification 6.9. 1.8,

> entify the cause of the unavailability of samples and identify th new location(s) for obtaining replacement samples in the next Semi nual Radioactive Effluent Release Report and also include in the r ort a revised figure(s) and table for the ODCM reflecting the new location(s).

d. The provis ns of Specifications 3.0.3 and 3.0.4 are not applicable.

.SURVEILLANCE RE UIREMENT 4.12.1 The radiological envir mental monitoring samples shall be collected pursuant to Table 3.12-1 from th specific locations given in the table and figure(s) in the ODCM, and shall b analyzed pursuant to the requirements of Table 3. 12-1, and the detection cap i lities required by Table 4. 12-1.

PALO VERDE " UNIT 1 CC) BY USKIR'

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TABLE 3.12-1

'ADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE P THWAY NUt<BER OF REPRESENTATIVE SAt1PLING AND TYPE AND FRgQUENCY AND/OR SAMPL SAMPLES AND SAMPLE LOCATIONS COLLECTION FREQUENCY OF ANALYSIS Airborne Radioiodine amples from 5 'locations: Continuous sampling Gross beta weekly;.d and partic- 3 ampl es at or near the collected weekly, I-131 weekly; gamma ulates SI BOUNDARIES (¹14A, 15, or more frequently isotopic analysis 21} different sectors if required by dust of composite (by of the highest calculated loading location) quarterly annual erage ground level 0/Q."

1 sample (¹4 from areas of special int rest, which is from the vic ity of a community having he highest calculated nnual average D/Q.

1 sample (¹6) from a co trol location 15-30 km (10-20 mi) distant and in the least prevalent wind direction.

Direct radiation 40 stations (¹6-45) with Qu terly Gamma dose two or more dosimeters for quarterly measuring dose rate continuously, placed as follows: an inner ring of stations at the site boundary and an outer ring in the 4-to-5 mi range from the site with a station in each sector of each ring, except the WNW sector, which is inaccessible (16 sectors x 2 rings minus 1 = 31 sta-tions). 7 additional stations are in local schools and population centers; 2 other stations are used as controls.

PALO VERDE " UNIT 1 3/4 12-3

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CONTROLLED B It'SER TABLE 3. 12" 1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM XPOSURE THWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAM E SAMPLES ANO SAMPLE LOCATIONS COLLECTION FREQUENCY OF ANALYSIS Waterborne Surface Water storage r'eservoir (¹60) Monthly composite of Gamma vaporation pond (¹59) weekly grab sample monthly; isotopic'nalysis tritium quarterly Ground 2 o ite wells (¹57, 58) quarterly grab ~

Tritium and gamma sample isotopic analysis quarterly Drinking (well) 3 wells om surrounding Composite sample of I-131 analysis on residences ¹46, 48, 49) weekly grab samples each composite when that would b affected over 2-week period the dose calculated by its discha e when I-131 analysi s for the consumption is performed, monthly of the water is composite of weekly greater than 1 mrem grab samples otherwise per year. h Composite for gross beta and gamma isotopic U%4aY~ analyses monthly.

Composite for tritium analysis quarterly.

Ingestion Nil k Samples from milking animals Se monthly for Gamma isotopic and in 3 locations within 5 km anim ls.on I-131 analysis distance having the highest pastu ; other- semi-monthly when dose potential. If there wise, m thly animals are on are none, 1 sample from pasture or monthly milking animals in each of . at other times 3 areas (¹50, 51, 53) between 5 and 8 km distant where doses are calculated to be greater than 1 mrem h

per year.

One sample from milking animals at a control location

(¹56), 15 to 30 km distant and in the least prevalent wind direction.

PALO VERDE - UNIT I 3/4 12-4 AMENDMENT NO. 27

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CONTROLLED BV USER TABlE 3. l2-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE THEY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAM E ... SAMPLES AND SAMPLE LOCATIONS. COLLECTION FREQUENCY OF ANALYSIS Food produc Samples (¹47, 52) of 3 Monthly during Gamma isotopic and different kinds of broad growing season I-l3l analysis.

leaf vegetation. grown near-st each of two different o fsite locations of highest pr icted annual average grou d-level D/g if milk sample g is not performed 1 sample ¹62} of each of Monthly during Gamma isotopic and the simila broad leaf growing season I-131 analysis.

vegetation g own 15-30 km distant in th least preva-lent wind direc ion if milk sampling is not p rformed

~+hen broad leaf vegetation samples are not available, reports from 4 existing supplemental airborne radioiodine sample locations will be substituted.

PALO VERDE - UNIT 1 3/4 12-5 AMENDMENT NO. 27

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TABLE 3. 12-1 (Continued)

TABLE NOTATIONS a

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Th number, media, frequency, and location of sampling may vary from site to site It is recognized that, at times, it may not be possible or practical ~

to ob in samples of the media of choice at the most desired location or time.

In thes instances suitable alternative media and locations may be chosen for the part ular pathway in question and submitted for acceptance. Actual loca-tions (dis ance and direction) from the site shall be provided in Table 7-1 and Figure 7-1 s the ODCM. Refer to Regulatory Guide 4. 1, "Programs for Monitoring

'Radioactivity in the Environs of Nuclear Power Plants."

b Regulatory Guide .13 provides guidance for thermoluminescence dosimetry (TLO) systems used for e vironmental monitoring. One or more instruments, such as a pressurized ion c mber, for measuring and recording dose rate continuously may be used in place f, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter may be considered to be one phosphor, and two or ore phosphors in a packet may be considered as two

'e or more dosimeters. Film adges s ld not be used for measuring direct radiation. e.it~ E' Can>sters for the collection o r in air are subject to channeling.

These devices should be careful 1 checked before operation in the field or several should be mounted in serie to prevent loss of iodine.

d Particulate sample filters shall be a lyzed for gross beta 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and t oron daughter decay. If gross beta activity in air or water is greater than 0 times the yearly mean of control samples for any medium, gamma'sotopic ana sis should be performed on the individual samples.

e Gamma isotopsc analysis means the identificatio and quantification of gamma-emitting radionuclides that may be attribu ble to the effluents from the facility.

fThe purpose of this sample is to obtain background in ormation. If it is not practical to establish control locations in accordance ith the distance and wind direction criteria, other sites that provide valid ckground data may be substituted.

g Groundwater samples should be taken when this source is tappe for drinking or irrigation purposes in areas where the hydraulic gradient o recharge properties are suitable for contamination.

h The dose shall be calculated for the maximum organ and age group, u 'ng the methodology and parameters in the ODCH.

PALO YERQE " UNIT 1 3/4 IZ-e

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03. 12-2 REPORTING LEVELS 'FOR RADIOACTIVITY CONCENTRATIONS IH ENVIROHMEHTAL SAMPLES Xl REPORTIHG LEVELS C7 m

MATER AIRBORNE PARTICULATE MILK FOOD PRODUCTS ANALYSIS Ci/Q,) OR GASES (pCi/ms) (pCi/2) (pCi/kg, wet)

~ H-3 20,000 Mn-54 1,000 Fe-59 400 Co-58 1,000 Co-60 300 Zn-65 300 Zr-Nb-95 400 I-131 0.9 100 Cs-134 30 10 60 1,000 Cs-137 50 20 70 2,000 Ba- La-140 200 300

For drinking water samples. This is 40 CFR Part 141 value. If no drinking thway exists, a value of 30,000 pCi/2 may be used.

- Ifno drinking pathway exists, a reporting level of 20 pCi/2 may be used.

1 TABLE 4. 12-1 DETECTION CAPABILITIES FOR EHVIROHl1EhfAL SAMPLE ANALYSIS LOMER LIHIT OF DETECTIOH (LLD)

ER AIRBORNE PARTICULATE HILK FOOD PRODUCTS ANALYSIS (pCs ) OR GAS (pCi/ma) (pCi/2) (pCi/kg,wet)

Gross beta 4 0. Ol H-3 2000" Mn-54 15 Fe-59 30 Co-58,-60 15 Zn-65 30 Zr-95 30 Nb-95 I-131 0. 07 60 Cs-134 0. 05 60 Cs-137 18 0. 06 18 80 Ba-140 60 60 .

La-140 15 15 Note: This list does not mean that only these nuclides are to be detected and reported. Other peaks that are measureable and identifiable, together with the above nuclides, shall also be identified and reported.

"If no drinking water pathway exists, a value of 3000 pCi/2 may be used.

""If no drinking water pathway exists, a value of 15 pCi/2 may be used.

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TABLE NOTATION uidance for detection capabilities for thermoluminescent dosimeters used environmental measurements is given in Regulatory Guide 4.13.

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Table 4.12-1 indicates acceptable detection capabilities for radioactive materi s in environmental samples. These detection capabilities are tabulate in terms of the lower limits of detection (LLDs). The LLD is defined, r purposes of this guide, as the smallest concentration of radioactive aterial in a sample that will yield a net count (above system backg und) that will be detected with 95/ probability with only 5/. probability f falsely concluding that a blank observation represents a "real" signal.

For. a particular me surement system (which may include radiochemical separation):

b LLD =

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Y exp(-Ut)

Mhere:

LLD is the "a priori" lower 1't of detection as defined above (as picocuries per unit mass or volume).

s is the standard deviation of th background counting rate or of tIIe counting rate of a blank sample s appropriate (as counts per minute)

E is the counting efficiency (as counts r disintegration)

V is the sample size (in units of mass or v ume)

2. 22 is the'umber of disintegrations per minu per picocurie Y is the fractional radiochemical yield (when app cable)

A, is the radioactive decay constant for the particula radionuclide ht for environmental samples is the elapsed time between ample collection (or end of the sample collection period) and t> e of counting PALO VERDE " UNIT 1 -9

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TABLE NOTATION In calculating the LLD for a radionuclide determined by gamma-ray ectrometry the background should include the typical contributions of o er radionuclides normally present in the samples (e.gss potassium-40 in ilk.'samples). Typical values of E, V, Y, and ht should be used in the 1cQlation.

ys It'shou,, be recognized that. the LLD is defined as an a priori (before the fact)tlimit representing the capability of a measurement system and

'not as an' osteriori (after the fact) limit for a particular measure-ment. Analy s shall be performed in such a manner that the stated LLDs wi11 be achene d under routine conditions. Occasionally background fluctuations, u voidable small sample sizes, the presence of interfering nuclides, or othe uncontrollable circumstances may render these LLDs unachievable. In ch cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

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4. 12. 2 LAND USE CENSUS LIM ING CONDITION FOR OPERATION

3. 12.2 land use census shall be conducted and shall identify within a distance 8 km (5 miles) the location in each of the 16 meteorological sectors of the near st milk animal, the nearest residence and the nearest garden" of greater than 0 m~ (500 ft~) producing broad leaf vegetation.

APPLICABILITY: At all times.

ACTION:

a. With a lan calculated use census 'ing a location(s) that yields a se or dose commitment greater than the values currently being calcula d in Specification 4.11.2.3, identify the new loca-tion(s) in the ext Semiannual Radioactive Effluent Release Report, pursuant to Spec ication 6.9. 1.8.

b. With a land use cen us identifying a location(s) that yields a calculated dose or d e commitment (via the same exposure pathway) 20'. greater than at a ocation from which samples are currently being obtained in accordance th Specification 3. 12. 1, add the new loca-tion(s) to the radiologic l environmental monitoring program within 30 days. The sampling loc ion(s), excluding the control station location, having the lowest lculated dose or dose commitment(s),

via the same exposure pathway, may be deleted from this monitoring program after (October 31) of t year in which this land use census was conducted. Pursuant to Specs ication 6.9. 1.8, identify the new location(s) in the next Semiannual adioactive Effluent Release Report and also include in the report a rev'sed figure(s) and table for the ODCM reflecting the new location(s).

c. The provisions of Specifications 3.0.3 a d 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS

4. 12.2 The land use census shall be conducted during th growing season at least once per 12 months using that information that will rovide the best results, such as by a door-to-door survey, aerial survey, o by consulting local agricul'tare, authorities. The results of the land use census hall be included in the Annual'adiological Environmental Operating Report purs nt to Specification 6.9. 1.7.

"Broad leaf vegetation sampling of at least three different kinds o vegetation may be performed at the SITE BOUNDARY in each o> two different direc 'on sectors with the highest predicted D/gs in lieu of the garden census. Specifi ations for broad leaf vegetation sampling in Table 3. 12-1 shall be followed, including analysis of control samples.

PALO VERDE - UNIT 1 3/4 12-11

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4. 12.3 IHTERLABORATORY COMPARISON PROGRAM LIMI G CONDITION FOR OPERATION 3.12.3 An ses shall be performed on radioactive materials supplied as part of an Interl oratory Comparison Program that has been approved by the Commission tha correspond to samples required by Table 3. 12-1.

APPLICABILITY: A al 1 times.

ACTION:

a~ Mith analyses ot being performed as required above, report the corrective acts ns taken to prevent a recurrence to the Commission in the Annual Ra ological Environmental Operating Report pursuant to Specification 6. . 1.7.

b. The provisions of Spe ifications 3.0.3 and 3.0.4 are not applicable.

4. 12.3 The Interlaboratory Comparison Pr ram shall be described in the 00CM.

A summary of the results obtained as part o the above required Interlaboratory Comparison Program and in accordance with the methodology and parameters in the ODCM shall be included in the Annual Radio gical Environmental Operating Report pursuant to Specification 6.9. 1.7.

0 PALO VERDE " UHIT 1 3/4 12-12

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In the event more than four sensors in a Reactor Vessel Level channel are inoperable, repairs may only be possible during the next refueling outage.

This is because the sensors are accessible only after the missile shield and reactor vessel head are removed. It is'ot feasible to repair a channel except during a refueling outage when the missile shield and reactor vessel head are removed to refuel the core. If both channels are inoperable, the channels shall be restored to OPERABLE status in the nearest refueling out-age. If only one channel is inoperable, it is intented that this channel be restored to OPERABLE status in a refueling outage as soon as reasonably possible.

3/4. 3. 3. 7 LOOSE-PART DETECTION INSTRUMENTATION The OPERABILITY of the loose-part detection instrumentation ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The allowable out-of-service times and surveillance requirements are co'nsistent with the recommendations of Regulatory Guide 1.133, "Loose-Part Detection Program for the Primary System of Light-Mater-Cooled Reactors," May 1981.

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3/4.3.3.8 MONITORING INSTRUMENTATION 4awLM 0 The i nstrumentati on i s to moni tor and contro, as app icable, the. releases of radioactive materials in gaseous effluent during actual or potential releases of gaseous effluents. The alarm/trip set-points for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes rovisions or mons orang an contro sng the concentrations of potentially explosive gas mixtures in the GASEOUS RADMASTE SYSTEM. The OPERA-BILITY and use of this instrumentation is consistent. with the requirements of General Qesign Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

There are two separate radioactive gaseous effluent monitoring systems:

the low range effluent monitors for normal plant radioactive gaseous effluents and the high range effluent monitors for post-accident plant radioactive gaseous effluents. The low range monitors operate at all times until the concentration of radioactivity in the effluent becomes too high during post-accident conditions.

The high range monitors only operate when the concentration of radioactivity in the effluent is above the setpoint in the low range monitors. II, PALO VEkQE - UNIT 1 B 3/4 3-5 AMEHDMENT NO. >4

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3/4. 11 RADIOACTIVE EFFLUENTS BASES 3 .11.1 SECONDARY SYSTEM LIOUID WASTE DISCHARGE TO ONSITE EVAPORATION PONDS 3/4.. 1. 1 CONCENTRATION T 's specification is provided to ensure that at any time during the life of the n clear station, the annual total body dose due to ground contamination of an UNREST CTED AREA, arising from transportation and deposition by wind of the accumulate activity discharged to the pond from the secondary system of the plant (if the pond ets dried up) on the UNRESTRICTED AREA, is within the guidelines of 10 CFR-Part 20 for the above-mentioned postulated event.

Restricting the concentrations of the secondary liquid wastes discharged to the onsite evapora ion ponds will .restrict the quantity of radioactive material that can get accumu ted in the ponds. This, in turn, provides assurance that in the event of an un ontrolled release of the pond's contents to an UNRESTRICTED AREA, the resulting to 1 body annual exposure from ground contamination to a MEMBER OF THE PUBLIC at he nearest exclusion area boundary will be within 0.5 rem.

This specification ap lies to the secondary system liquid waste discharges of radioactive materials fro all reactor units to the onsite evaporation ponds.

Since the chemical neutralize tank concentrations will bound concentrations in other secondary waste discha ges, surveillance requirements stipulate that sampling and analysis of other s ondary waste discharges need be performed only if the sampling and analysis f the contents of the chemical neutralizer tank shows that the neutralizer tan concentration exceeds the specified LLD.

The required detection capability s for radioactive materials in the secondary liquid waste samples are tabulated in t rms of the lower'imits of detection (LLDs). Detailed discussion of the LLD, nd other detecti.on limits can be found in HASL Procedures Manual, HASL-300 (revis d annually), Currie, L. A., "Limits for Qualitative Detection and Quantitative termination - Application-to Radio-chemistry," Anal. Chem. 40, 586-93 (1968), an Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atla ic Richfield Hanford Company Report ARH-SA-215 (June 1975).

3/4.11.1.2 DOSE This specification is provided to implement the equirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Pa t 50. The Limiting Condi-tion for Operation implements the guides set forth in Se tion II.A of Appendix I.

The ACTION statements provide the required operating flex ility and at the same time implement the guides set forth in Section IV:A of Appe dix I to assure that the releases of radioactive material in liquid effluents to RESTRICTED AREAS will kept be "as low as is reasonably achievable." Also, for resh water sites with drinking water supplies that can be potentially affected b plant operations, there is reasonable assurance that the operation of the facility ill not resul..'n excess of radionuclide concentrations in the finished drinking water that ar in the requirements of 40 CFR Part 141. The dose calculation methodolo and para-meters in the ODCM implement the requirements in Section III.A of App dix I that conformance with the guides of Appendix I be shown by calculational pro edures based on models and data, such that the actual exposure of a MEMBER OF T PUBLIC through appropriate pathways is unlikely to be substantially underestimate .

The equations specified in the ODCM for calculating the doses due to the ac al release rates of radioactive materials in liquid effluents are consistent wit PALO VERDE - UNIT 1 , B 3/4 11"1

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reactor at the site.

liquid For un'dwaste ion applies to the release of liquid effluents from each effluents from the shared system are propor so treatment systems, the its sharing that system.

3l4. 11. 1. LI UID HOLDUP TANKS The tanks referred to in this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks'ontents, the resulting concentrations would be less than the limits of ,

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10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

The limit of 60 curies is based on the analyses given in Section 2.4 of the PVNGS FSAR and on the amount of soluble (not gaseous) radioactivity in the Refueling Water Tank in .Table 2.4-26.

. 11.2 GASEOUS EFFLUENTS 3/4.11. 1 DOSE RATE This spec ication is provided to ensure that the dose at any time at and beyond the SITE 8 DARY from gaseous effluents from all units on the site will be within the annual se limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are t doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table Column 1. These limits provide reasonable assurance that radioactive mate al discharged in gaseous effluents will not result 'in the exposure of a MEMBER THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOU RY, to annual average concentrations exceeding the limits specified in Appends , Table II of 10 CFR Part 20 (10 CFR Part 20. 106(b)). For MEMBERS OF THE BLIC who may ~c times be within .

the SITE BOUNDARY, the occupancy of that MEMBER THE PUBLIC will usually be sufficiently low to compensate for any increase in atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of culations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy fact s, shall be given in the ODCM.'he specified release rate limits restrict, at times, the corresponding gamma and beta dose rates above background to a ME R OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 m s/year I

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RADIOACTIVE EFFLUENTS SES DOSE ATE (Continued) to the tal body or to less than or equal to 3000 mrems/year to the skin.

These rel ase rate limits also restrict, at all times, the corresponding thyroid do rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year.

This speci ication applies to the release of radioactive materials in gaseous effluent from all reactor units at the site.

The required de ection capabilities for radioactive materials in gaseous

'aste samples are tab lated in terms of the lower limits of detection (LLDs).

Detailed discussion of he LLD, and other detection limits can be found in HASL Procedures Manual, HASL- 0 (revised annually), Currie, L. A., "Limits for .

qualitative Detection and uantitative Determination Application to Radio-chemistry," Anal. Chem. 40, 86-93 (1968), and Hartwell, J. K., "Detection Limits for Radsoanalytical Co nting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (Jun 1975)'.

3/4. 11. 2. 2 DOSE " NOBLE GASES This specification is provided implement the requirements of Sections II.B, III.A and IV.A of Appen ix I, 10 CFR Part 50. The Limiting Condition for Operation implements the'des set forth in Section II.B of Appendix I. The ACTION statements provid the requ'ired operating flexibility and at the same time implement the guides s t forth in Section IV.A of Appendix I to assure that the releases of radioactive m erial in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is easonably achievable." The sur-veillance requirements implement the requiremen in Section .III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational proce-dures based on models and data 'such that the actua exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely o be substantially under-estimated. The dose calculation methodology and para ters established in the ODCM for calculating the doses due to the actual releas rates of radioactive noble gases in gaseous effluents are consistent with the e'thodology provided

- in Regulatory Guide 1. 109, "Calculation of Annual Doses to an from Routine Releases of Reactor Effluents for the Purpose of Evaluating ompliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Reg atory Guide l.

"Methods for Estimating Atmospheric Transport and Dispersion o Gaseous Effluents ill, in Routine Releases from Light-Water Cooled Reactors," Revision July 1977.

The ODCM equations provided for determining the air doses at and b ond the SITE BOUNDARY are based upon the historical average atmospheric con tions.

This specification applies to the release of radioactive material in gaseous effluents from each reactor unit at the site.

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RADIOACTIVE EFFLUENTS BASES 3 . 11. 2. 3 DOSE IODINE-131 IODINE-133 TRITIUM, AND RADIONUCLIDES IN PAR CULATE FORM T 's specification is provided to implement the requirements of Sections I.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation are the guides set forth in Section II.C of Appendix I.

The ACTION tatements provide 'the required operating flexibility and at the same time imp ement the guides set forth in Section IV.A of Appendix I to assure that the relea s of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be ke t, "as low as is reasonably achievable." The ODCM calculational methods specified n the surveillance requirements implement the requirements in Section III.A o ppendix I that conformance with the guides of Appendix I be shown by calculate nal procedures based on models and data, such that the actual exposure of a M BER OF THE PUBLIC through appropriate pathways is unli.kely to be substant> lly underestimated. The ODCM calculational method-ology and parameters for lculating the doses due to the actual release rates of the subject materials ar consistent with the methodology provided in Regulatory Guide 1. 109, "Cal lation of Annual Doses to Man from Routine Releases of Reactor Effluents r the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Re sion 1, October 1977 and'egulatory Guide 1. 111, "Methods for Estimating Atmospher Transport and Dispersion of Gaseous Effluents in. Routine Releases from Light-Wate -Cooled Reactors," Revision 1, July 1977. ~

These equationq also provide for det mining the actual doses based upon the historical average atmospheric conditi s. The release rate specifications for iodine-131, iodine-133, tritium, an radionuclides in particulate torm with half-lives greater than 8 days are depend t upon the existing radionuclide pathways to man, in the areas at and beyon the SITE BOUNDARY. The pathways

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that were examined in the development of the calculations were: (1) individual inhalati'on of airborne radionuclides, (2) depo ition of radionuclides onto green leafy vegetation with .subsequent consumption by an, (3) deposition onto grassy areas where milk animals and meat-producing anima graze with consumption of the milk and meat by man, and (4) deposition on the round with subsequent exposure of man.

Thi~pecifi.cation applies to the release of radio tive materials in gaseous effluents from each reactor unit at the site.

3/4. 11.2.4 GASEOUS RADWASTE TREATMENT The OPERABILITY of the GASEOUS RADWASTE SYSTEM and the YEN LATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for u whenever gaseous effluents require treatment prior to release to the environ ent. The requirement that the appropriate portions of these systems be used, en speci--

fied, provides reasonable assurance that the releases of radioactive m terials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR 50.36a, General Desig Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives gi n in Section II.D of Appends~;o" 10 CFR Part 50. The specified limits gover ng the use of appropl iate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II. C of Appendix I, 10 CFR Part 50, for gaseous, effluents.

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CONTROLLED BY USER RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT (Continued) ecification applies to the release of radioactive materials in gaseous effluen each reactor unit at the site.

The minimum analysis freq at intervals no greater than 9 days and a used for certain radioactive gaseous waste sampling

'm f 4/M (i.e. at least 4 times per month of 48 times a year) is le 4. 11-2 This

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will eliminate taking double samples when quarterly and week es are required at the same time.

3/4. 11. 2. EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. (Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits. These automatic control

-features include isolation of the source of hydrogen and/or oxygen, or injection of dilutants'o reduce the concentration below the flammability limits.) Main-taining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials vill be controlled tno0a 4 in conformance with the requirements of General Design Criterion 60 of Appendix A pc to 10 CgR ~Part 50.

3/4-ll- . GAS'STORAGE TANKS This specification considers postulated radioactive releases due to a waste gas system leak or failure, and.limits the quantity of radioactivity contained in each pressurized gas storage tank in the GASEOUS RAOMASTE SYSTEM to assure that a release would be substantially below the guidelines of 10 CFR part 100 for a postulated event.

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF TKE PUBLIC at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard:Review -Plan 11.3, Branch Technical Position ETSB 11-5, "postulated Radioactive Releases Due to"a Maste Gas System Leak or Failure,"

in NUREG-0800, July 1981.

1.3 SOLID RADIOACTIVE MASTE This cification addresses the requirements of General Design Criterion 60 o . endix A to 10 CFR Part 50. The process parameters included in establishing the ESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, /liquid/solidification agent/catalyst ratios, waste oil content, waste princsp chemical cons 'tuents, and mixing and times. 'uring 3/4. 11. 4 TOTAL DOSE This specification is provided to meet the dose li 'tions of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by R 18525-. The specification requires the prepar ation and submittal of a Special rt whenever the calculated doses from plant generated radioactive effluents P>

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RADIOACTIVE EFFLUENTS SES TOTAL OSE (Continued) direct ra iation exceed 25 mrems to the total body or any organ, except the thyroid, w ch shall be limited to less than or equal to 75 mrems. For sites containing u to four reactors, it is highly unlikely that the resultant dose to a MEMBER 0 THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual actors remain within twice the dose design objectives of Appendix I, and 1 direct radiation 'doses from the reactor units and outside storage tanks are p4 small. The Special Report will describe a course of action that should r suit in the limitation of the annual dose to a MEMBER OF THE PUBI IC to within e 40 CFR Part 190 limits. For the purposes of the Special Report, it may e assumed that the dose commitment to the MEMBER OF THE PUBLIC from other ur ium fuel cycle sources is negligible, with the exception that dose contri tions from other nuclear fuel cycle facilities at the same site or within a ra ius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is e imated to exceed the requirements of 40 CFR Part 190, the Special Report wi h a request for a variance (provided the release conditions resulting -in 'olation of 40 CFR Part 190 have not already been corrected), in accordance wit the provisions of 40 CFR Part 190. 11 and 10 CFR Part 20.405c, is considered be a timely request and fulfills the requirements of 40 CFR Part 190 until RC staff action is completed. The variance only relates -to the l.imits wf 0 CFR Part 190, and does not apply in any way to the other requirements for do limitation of 10 CFR Part 20, as addressed in Specifications 3. 11. 1. 1 and 11.2. l. An individual is not con-sidered a MEMBER OF THE PUBLIC during any p iod in which he/she is engaged in carrying out any operation that is part of th nuclear fuel cycle.

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3/4. 12 RADIOLOGICAL ENVIRONMENTAL MONITORING ASES 3/4.1 1 MONITORING PROGRAM DcL.~M The adiological environmental monitoring program required by this

'specificat on provides representative measurements of radiat',on and of radio-active mate 'als in those exposure pathways and for those radionuclides that lead to the h'est potential radiation exposures of'EMBERS OF THE PUBLIC resulting f>o'm e station-'operation. This monitoring program implementsSection IV.B.2 o Appendix I to 10 CFR Part 50 and thereby supplements the radiological effl nt monitoring program by verifying that the measurable concentrations of r dioactive materials and levels of radiation are not higher than expected on the asis of the effluent measurements and the modeling of the environmental expo re pathways. Guidance for this monitoring program is provided by the Radiolo cal Assessment Branch Technical Position on Environ-mental Monitoring. The i 'tially specified monitoring program will be effective for at least the first 3 ye rs of commercial operation. Following this period, program changes may initiated based on operational experience.

The required detection cap ilities for environmental sample analyses are tabulated in terms of the low limits of detection (LLDs). The LLDs requi red by Table 4. 12-1 are consi red optimum for routine environmental measurements in industrial laborator'. It should be recognized that the LLO-is-defined 'as an a priori (before he fact) limit representing the capa-htltty l y d t y t t t t lt th y t) limit for a particular measurement.

Detailed discussion of the LLD, and oth r detection limits, can be found in HASL Procedures Manual, HASL-300 (revised nually), Currie, L. A., "Limits ination - Application to Company

~ytidt ttq,"Al for qualitative Detection annqua~btative Oete Radiochemistry," Anal. Chem. 40, 586-93 (1968),

Alit l tdI Report ARH-SA-215 (June 1975).

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1 3/4. 12 RADIOLOGICAL ENVIRONMENTAL MONITORING SES 3/4.12. LAND USE CENSUS This pecification is provided to ensure that changes in the use of areas at and beyo d the SITE BOUNDARY are identified and that modifications to the radiological nvironmental monitoring program are made if required by the results of thl census. The best information from the door-to-door survey, aerial sur y or from consulting with local agricultural authorities shall 'rom be used. This ce sus satisfies the requirements of Section IV.B.3 of Appen-dix I to 10 CFR Pa 50. Restricting the census to gardens of greater than 50 m provides assur nce that significant exposure pathways via leafy vege-tables will be identi ed and monitored since a garden of this size is the minimum required to pro uce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Gu e 1.109 for consumption by a child. To determine this minimum garden size, e following assumptions were made: (1) 20K of the garden was used for growing road leaf vegetation (i.e., similar to lettuce t

and cabbage), and (2) a veget tion yield of 2 kg/m~.

3/4. 12.3 INTERLABORATORY COMPARI N PROGRAM The .requirement for participatio fn an approved Interlaboratory Comparison Program ss provided to ensure that hand endent checks on the precision and accu-racy of the measurements of radioactive t'erial in environmental sample matrices are performed as part of the qua ty'reassurance program for environ-mental monitoring in order to demonstrate t t 'the results are valid for the purposes of Section IV 8.2 of Appendix I to

~ CFR Part 50.

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(5) Procedures defining corrective actions for all off-control point chemistry conditions, and (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.

d. Backu Method for Determinin Subcoolin Mar in A program which will ensure the capability to accurately monitor the Reactor Coolant System subcooling margin.- This program shall include the following:

, (1) Training of personnel, and (2) Procedures for monitor ing.

e. Post-Accident Sam 1 in A program which'will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident 0 conditions. The program shall include the following:

(1) Training of personnel, (2) Procedures for sampling and analysis, (3) Provisions for maintenance of sampling and analysis equipment.

f. S ra Pond Monitorin A program which will identify and describe the parameters and activities used to control and monitor the Essential Spray Pond and XQMRY Piping. The program shall be conducted in accordance with station manual procedures.

6. 9 REPORTING RE UIREMENTS ROUTINE REPORTS 6.9. 1 In addition to the applicable reporting requirements of Title 10, Code

~ of Federal Regulations, the following reports shall be submitted to the Regional InoVO Administrator of the Regional Office of the NRC unless otherwise noted.

~yt HS STARTUP REPORT 6.9. 1. 1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel PALO VERDE " UNIT 1 6-16 AMENDMENT NO. 27

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g. Radioactive Effluent Contro s Pro ra 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:

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

2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table 11, Column 2,

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

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 to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1,

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

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

Radiolo ical Environmental Monitorin Pro ra A program shall be provided to monitor the radiation and radio-nuclides 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 expo-sure 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.

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ADMINISTRATIVE CONTROLS REPORTIHG RE UIREMENTS Continued supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The Startup Report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed.

ANNUAL REPORTS" 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted within the first calendar quarter of each year. The initial report shall be submitted within the first calendar quarter of the year following initial criticality.

6.9. 1.5 Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrems/yr and their associated man-rem exposure according to work and job functions,"" e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignments to various duty functions may be estimated based on pocket'dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20K of the individual total. dose need not be accounted for. In the aggregate, at least 80K of the total whole body dose received from external sources should be assigned to specific major work functions.

Annual reports shall also include the results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3. 4. 7. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior the the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one "A single submittal may be made for a multiple unit station. The submittal that are common to all units at the station.

jO should combine those sections

"This tabulation supplements the requirements of 520.407 of the 10 CFR Part 20.

PALO VERDE - UNIT 1 6-M AMEHDMEHT HO. 30 LQ

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CGi4TROLLED BY USER ADMINISTRATIVE CONTROLS ANNUAL REPORTS Continued analysis after the radioiodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentra-,

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

MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating Statistics and shutdown experience, including documentation of all challenges to the safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Mashington,. D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than

,the 15th of, each month following the calendar month covered by the report.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT", Xiaszaw N 6.9.1.7 utine Annual Radiological E'nvironmental Operating Reports covering the operatio of the unit during the previous calendar year shall be submitted prior to May 1 each year. The initial report shall be submitted prior to May 1 of the year llowing initial criticality.

The Annual Radiological vironmental Operating Reports shall include summaries, interpretations, and an ana sis of trends of the results of the radiological environmental surveillance ac ities for the report period, including a comparison with preoperational s dies, with operational controls as appropriate, and with previous environmental sur illance reports, and an assessment of the observed impacts of the plant operatio on the environment. The reports shall also include the results of land use cens es required by Specification 3.12.2.

The Annual Radiological Environmental Operatin eports shall include the results of analysis of all radiological environme 1 samples and of all environmental radiation measurements taken during th eriod pursuant to the locations specified in the Table and Figures in the ODC as well as summarized and tabulated results of these analyses and measurements s the format of the table in the Radiological Assessment Branch Technical Positio Revision 1, November 1979. In %he event that some individual results are no available for inclusion with the report, the report shall be submitted notin nd explaining the reasons for the missing results. The missing data sha be submitted as soon as possible in a supplementary report.

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INSERT 4 ANNUAL RADIOLOGICAL ENVIRONME TAL OPERATING REPORT

6.9.1.7 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, I

IV.B.3, and IV.C of Appendix to 10 CFR Part 50.

A single submi.ttal may be made for a multi-unit station.

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CONTROLLED BY USER ADMINISTRATIVE CONTROLS 11 sampling locations keyed to a table giving distances and directions from ine of one reactor; the results of licensee participation in,the Interlabora rison Program, required. by Specification 3.12.3; discussion of all devia io e sampling schedule of Table 3. 12-1; and discussion of all analyses in which the b Table 4.12-1 was not achievable.

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT" 'L~KE.M'V 6.9.1.8 outine Semiannual Radioactive Effluent Release Reports covering the operate n of the unit during the previous 6 months of operation shall be submitted wi in 60 days after January 1 and July 1 of each year. The period of the first re rt shall begin with the date of initial criticality.

The Semiannual Radi ctive Effluent Release Reports shall include a summary of .the quantities of dioactive liquid and gaseous effluents and solid waste released from the unit outlined in Regulatory Guide 1.21, "Measuring, Evalu-ating, and Reporting Radio tivity in Solid Mastes and Release of Radioactive Materials in Liquid and Gase s Effluents from Light-.Mater-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix thereof.

,The Semiannual Radioactive Effluent lease Report to be submitted within 60 days after January 1 of each year sh 1 include an annual summary of hourly meteorological data collected over the pr ious year. This annual summary may be either in the form of an hour-by-hour li ing on magnetic tape of wind speed, wind direction, atmospheric stability, nd precipitation (if measured),

or in the form of joint frequency distributions f wind speed, wind direction, and atmospheric stability."" This same report sha 1 include an assessment of the radiation doses due to the radioactive liquid an gaseous effluents released from the unit or station during the previous calendar ar. This same report shall also include an assessment of the radiation doses om radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to thei activities inside the SITE BOUNDARY (Figure 5.1-1) during the report period. 1 assumptions used in making these assessments, i.e., specific activity, expo ure time and location, shall be included in these reports. The meteorologica onditions concurrent with the time of release of radioactive materials in gas us effluents, as determined by. sampling frequency and measurement, shall e used for determining the, gaseous pathway doses. The assessment of radiation oses shall be performed in accordance with the methodology and parameters in t OFFSITE DOSE CALCULATION MANUAL.

ingle submittal

' may be made for a multiple unit station. The submittal shoul those sections that are common to all units at the station; however, for specify the un'eparate releases of ra radwaste systems, the submittal shall

've material from each unit.

""In lieu of submission with the first half year nual Radioactive Effluent Release Report, the licensee has the option o 'ng this summary of required meteorological data on site in a file that sha provided to the NRC upon request. zl PALO VERDE " UNIT 1 6-Q AMENDMENT NO. -7

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INSERT 5 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT **

6.9.1.8 The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous 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.1 of Appendix I to 10 CFR Part 50.

A single submittai may be made for a multiple unit station. The submittal should combine those sections that ace coamon to all units at the station> houever, for units uith separate raduaste systems, the submittai shall specify the release of radioactive materiai from each unit.

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CONTROL,LED BY USFR ADMINISTRATIVE CONTROLS S IANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)

The Se iannual Radioactive Effluent Release Report to be submitted 60 days after Ja uary 1 of each year shall also include an assessment of radiation doses to e likely most exposed MEMBER OF THE PUBLIC from reactor releases and other n rby uranium fuel cycle sources, including doses from primary effluent path ays and direct radiation, for the previous calendar year to show conforman with 40 CFR Part 190, Environmental Radiation Protection Standards for Nu lear Power Operation. Acceptable methods for calculating the dose contribut on from liquid and gaseous effluents are given in Regula-tory Guide 1.109, R . 1, October 1977.

The Semiannual Radioact've Effluent Release Reports shall include the following information for each cia of solid waste (as defined by 10 CFR Part 61) shipped offsite during the eport period:

a. Container volume, QU67

b. Total curie quantity (s cify whether determined by measurement or estimate),

c. Principal radionuclides (spe fy whether determined by measurement 0 d.

or estimate),

Source of waste and processing em oyed (e.g., dewatered compacted dry waste, evaporator bot ms),

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e. Type of container (e.g., LSA, Type A, pe B, Large quantity), and Solidification agent or absorbent (e.g., ment, urea formaldehyde).

The Semiannual RadioactiveEffluent Release Reports sha 1 include a list and description of unplanned releases from the site to UNRES ICTED AREAS of radio-active materials in gaseous and liquid effluents made duri the reporting period.

The Semiannual Radioactive Effluent Release Reports shall inclu any changes made during the reporting period to the PROCESS CONTROL PROGRAM a to the OFFSITE DOSE CALCULATION MANUAL, as well as a listing of new locati s for dose calculations and/or environmental monitoring identified by the nd use census pursuant to'pecification 3.12.2.

SPECIAL REPORTS

6. 9. 2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.

6.9.3 Violations of the requirements of the fire protection program described

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ability to achieve and maintain safe shutdown in the event of a fire shall be

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2t PALO VERDE - UNIT 1 6-X AMMENDMENT NO. 27

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CONTROLLED BY USER ADMINISTRATIVE CONTROLS RECORO RETENTION (Continued)

Records of quality assurance activities required by the QA Manual not listed in Section 6. 10. 1.

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

k. Records of PRB meetings and of NSG activities.

l. Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.9 including the date at which the ser-vice life commences and associated installation and maintenance records.

m. Records of audits performed under the requirements of Specifications 6.5.3.5 and 6.8.4.

n. Records of analyses required by the radiological environmental moni-

'toring program that would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and gA records showing that these procedures were followed.

o. Meteorological data, summarized and reported in a format consistent with the recommendations of Regulatory Guides 1.21 and 1.23.

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p. Records of secondary water sampling and water quality.

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6. 11 RAOIATION PROTECTION PROGRAM < -~ ~e 6.11.1 Procedures for personnel radiation protection shall be prepared con-sistent with the requirements of 10 CFR Part 20 and shall be approved, main-tained, and adhered to for all operations involving personnel radiation exposure.

6.12 MIGH RAOIATION AREA 6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Expo-sure Permit (REP)": Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the fol 1 owi ng:

"Radiation Protection personnel or personnel escorted by Radiation Protection personnel shall be exempt from the REP issuance requirement during the perform-ance of their assigned radiation protection duties, provided they are otherwise tollowing plant radiation protection procedures for entry into high radiation areas.

PALO VEROE " UNIT 1 6-22 AMENOMENT NO. 27

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ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued)

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device which 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 level in the area has been established and personnel have been made knowledgeable of them.

C. A radiation protection qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Radiation Protection Supervisor or his designated alternate in the REP.

6 .12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be main-tained under the administrative control- of the Shift Supervisor on duty and/or radiation protection supervision. Doors shall remain locked except during periods of access by personnel under an approved REP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months a dose in excess of 1000 mrems", that are located within large areas, such as PMR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas; then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the REP, direct or remote (such as use of closed circuit TY cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP) Xws<~~ 4

6. 13. 1 The be approved by the Commission prior to implementation.

6.13.2 Licensee-initiated changes PCP:

Shall be submitted to the Commission in the e Radioactive Effluent Release Report for the period in which the chan as made. This submittal shall contain:

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~Measurement made at 18 inches from source of radioactivity.

PALO VERDE " UNIT 1 6-23

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INSERT 6 6 13 PROCESS CONTROL PROGRAM Changes to the PCP:

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.q. This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analysts 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.

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

INSERT 7 t 6 14 OFFSITE DOSE CALCULATION MANUAL Changes a.

to the ODCM:

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

documentation shall contain:

1) Sufficient information to support the change together This with the appropriate analyses or'valuations justifying the change(s) and

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

Shall become effective after review and acceptance by the PRB and the approval of the Plant 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 Semiannual 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.

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ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (PCP Continued)

1) ficiently detailed information to totally suport the rationale for hange without benefit of additional or supplemental information, d

2) A determination that t hange did not reduce the overall conformance of the solidifie ste Product to existing criteria for solid wastes.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) iw~ettw P 6.14.1 Th DCM shall be approved by the Commission prior to implementation.

6.14.2 Licensee- tiated changes to the ODCM:

Shall be subm~ d to the Commission in the Semiannual Radioactive Effluent Release ort for the period in which the change(s) was made ef'fective. This ubmittal shall contain:

1) Sufficiently detailed s ormation to totally support the rationale for the change w out benefit of additional or supple-mental information. Informat> submitted should consist of a package of those pages of the OD to be changed with each page numbered and provided with an approv and date box, together with appropriate analyses or evaluations 'ustifying the change(s);

and

2) A determination that the change will not reduce th ccuracy or reliability of dose calculations or setpoint determin ons.

6.15 MAJOR CHANGES TO RADIOACTIVE LI UID GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.15. 1 Licensee-initiated major changes to the radioactive waste systems (l.iquid, gaseous, and solid):

Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed. by the PRB. The discussion of each change shall contain:

1) A summary of the evaluation that led to the determination that the change could be made- in accordance with 10 CFR 50.59.

2) Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; 1 "Licensees as may chose part of the annual to submit the information called for in this specification FSAR update.

PALO VERDE - UNIT 1 6-24 AMENDMENT ND. 77

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