Text

Amend 98 to License DPR-54,revising Tech Specs by Reducing Limits of Detection for Liquid Radioactive Effluents & Changing Requirements to Address Hardware Changes in Effluent Sys
	ML20148J846
Person / Time
Site:	Rancho Seco
Issue date:	03/17/1988
From:	Knighton G; Office of Nuclear Reactor Regulation
To:	;
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ML20148J816	List: ML20148J811; ML20148J846; ML20148J861;
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	NUDOCS 8803300407
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joh UNITED STATES p

p, NUCLEAR REGULATORY COMMISSION g

E WASHINGTON, D. C. 20555

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SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-31?

RANCHO SEC0 NUCLEAR GENERATING STATION AMEMCMENT TO FACILITY OPERATING LICENSE Amendment No. 98 License No. DPR-54 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendrent by Sacramento Municipal Utility District (the licensee) dated June 30, 1987, as supplemented October 3 and December 23, 1987 and January 11, 1988, complies with the standards and requirerents of the Atonic Energy Act of 1954, as amended (the Act), and the Comission's regulatior.s set forth in 10 CFR Chapter I; B.

The facility will operate in confonnity with the application, the provisions of the Act, and the regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

I i

8803300407 080317 ADOCK 05000312 PDR PDR P

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendr.cnt, and paragraph 2.C.(2) of Facility Operating License No. OPR-54 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 98, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This amendment to the Technical ;;ecification shall become effective within 30 days of the issuance date or prior to reactor criticality following the 1986/87 outage, whichever is first. The implementation delay is provided to allcw time for modification of affected procedures and promulgation of these changes to personnel.

FOR THE NUCLEAR REGULATORY COMMISSION

,1 George. Knighton,4'irector Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: March 17,1988

March 17. 1988 ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO. DPR-54 DOCKET NO. 50-312 Replace the following pages of the Appendix "A" Technical specifications with the attached pages.

The revised pages are identifiad by Amendment number and contain vertical lines indicating the area of change.

Remove Insed iia iia iii iii if iv vi vi vii vii vila viii vii' ix ix x

x xii xii 1-6 1-6 1-7 1-7 1-3 1-9 1-10 3-3 3-0 3-9 3-9 3-60 3-60 3-60a 3-61 3-61 3-62 3-62 3-63 3-63 3-63a 3-64 3-64 3-65 3-65 3-66 3-66 3-E7 3-67 3-68 3-68 3-69 3-69 3-70 3-70 3-71 3-71 3-72 3-72 3-72a 3-73 3-73 3-74 3-74 3-75 3-75 3-76 3-76 3-77 3-77 3-78 3-78 3-79 3-79 l

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-... - ~,

' ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO. DPR-54 DOCKET NO. 50-312 Remove Insert 3-81 3-81 3-82 3-82 3-83 3-83

?-84 3-84 3-85 3-85 3-86 3-86 3-87 3-87 3-88 3-88 3-90 3-90 3-91 3-91 3-92 3-92 4-7b 4-7b 4-9 4-9 4-9a 4-63 4-63 4-64 4-64 4-64a 4-65 4-65 4-66 4-66 4-67 4-67 4-68 4-68 4-69 4-69 4-70 4-70 4-71 4-71 4-71a 4-71b 4-72 4-72 4-72a 4-72b 4-72c 4-72d 4-72e 4-73 4-73 4-73a 4-74 4-74 4-75 4-75 4-76 4-76 4-76a 4-76b 4-77 4-77 4-78 4-78 4-79 4-79 j

4-80 4-80 4-81 4-81 1

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-3 ATTACMMENT TO LICENSE AMENDMENT No.

FACILITLOPERATING LICENSE NO. DPR-54 DOCKET NO. 50-312 Remove Insert 4-82 4-82 4-83 4-83 4-84 4-84 4-85 4-85 4-85a

<t-85b 4-86 4-86 4-89 4-89 5-1 5-1 5-la 5-lb 5-Ic 5-1d 6-5 6-5 6-10 6-10 6-11 6-11 6-12a 6-12a 6-12b 6-12b 6-12c 6-12c 6-12d 6-12d 6-12e 6-12e 6-12f 6-12f 6-129 6-12g 6-14 6-14 6-17 6-17 6-18 6-18 6-19 6-19 l

l l

l

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RAfD10 SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLEOFCONTEffTS(Continued)

Section Pace 1.16 RESTRICTED AREA 1-7 1.17 SITE BOUNDARY 1-7 1.18 DOSE E0VIVALENT I-131 1-7 1.19 MEW ER(S) 0F THE PUBLIC 1-7 1.20 DEWATERING 1_7 1.21 MAXIMUM EXPOSED (HYPOTHETICAL) INDIVIDUAL 18 1.22 RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAH HANUAL I-8 1.23 LIOUID EFFLUENT RADWASTE TREATHENT SYSTEH 1-8 1.24 VENTIl.Aif0N EXHAUST TREATHENT SYSTEMS 19 1.25 PURGE - PURGING 1_g 1.26 VENTING 19 1.27

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1-9 2

SAFETY LIMITS NO LIMITItG SAFETY SYSTM SETTINGS 2-1 2.1 SAFETY LIMITS. REACTOR CORE 2-1 2.2 SAFETY LIMITS. REACTOR SYST M PRESSURE 2-4 2.3 LIMITING SAFETY SYSTEM SETTINGS. PROTECTIVE INSTRUMENTATION 2-5 3

LIMITING C0f0ITIONS FOR OPERATION 3-0 3.0 GENERAL LIMITING C0f0ITIONS FOR OPERATION 3-0 3.1 REACTOR C00UWT SYSTEM 3-1 3.1.1 Ooerational Camonents 3-1 3.1.2 Pressurization. Heatuo. and Cooldown Limitations 3-3 3.1.3 Mininun Conditions for Criticality 3-6 3.1.4 Reactor Coolant Systen Activity 3-8 3.1.5 Chemistry 3-10 Amendment No. 28,53,$/,98 iia

RANCHO SEC0 UNIT 1 TECHNICAL SPECIFICATIONS TA8LE OF CONTENTS (Continued)

Section PLqe Letage 3-12 k

3.1.6 3.1.7 Moderator Temoerature Coefficient of Radioactivity 3-15 3.1.8 Low Power Physics Testina Restrictions 3-15b 3.1.9 Control Rod Ooeration 3-16 3.2 HIGH PRESSURE IR.lECTION. CHEMICAL ADDITION AND LOW TEMPERATURE OVERPRESSURE PROTECTION (LTOP) SYSTEMS 3-17 3.3 EMERGENCY CORE COOLING. REACTOR BUILDING EMERGE?{C.Y COOLING. AND REACTOR BUILDING SPRAY SYSTEMS 3-19 3.4 STENi AND POWER CONVERSION SYSTEM 3-23 3.5 INSTRtNENTATION SYSTEMS 3-25 3.5.1 QRer3tional Safety Instrmentation 3-25 3.5.2 Control Rod Grouo and Power Distribution Limits 3-31 3.5.3 Safety Features Actuation System Setooints 3-34 3.5.4 Incore Instrunentation 3-36 3.5.5 Accident Monitorina Instrtinentation 3-38d 3.5.6 Ernercency Feedwater Initiation and Control Setooints 3-389 3.5.7 Emercency Shutdown Instrmentation 3-38i 3.6 REACTOR BUILDING 3-39 3.7 AUXILIARY ELECTRICAL SYSTEMS 3-41 3.8 RJEL LOADING AND REFUELING 3-44 3.9 SPENT FUEL P0OL 3-46A 3.10 SEC0f0ARY SYSTEM ACTIVITY 3-47 3.11 fLEACTOR BUILDING POLAR CRANE AND AUXILIARY HOIST 3-49 3.12 SHOCK SUPPRESSORS (SNUB 8ERS) 3-51 3.13 AIR FILTER SYSTESM 3-52 3.14 FIRE SUPPRESSION 3-53 3.14.1 Instrtmentation 3-53 Amendment No. 28,39,80,82,84,93,9/,98 iii

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued)

Section Etat 3.14.2 Water Syst e 3-53 3.14.3 Sorav and Sorinkler Systens 3-56 CO System 3-56 3.14.4 2

3.14.5 Fire Hose Stations 3-57 3.14.6 Fire Barrier Penetration Fire Seals 3-58 3.15 RADIOACTIVE LIOUID EFFLUENT HONITORING INSTRUMENTATION 3-60 l

3.16 RADIOACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION 3-63 3.17 L10UID EFFLUENTS 3-70 3.17.1 Concentration 3-70

,v.3.17.2 Qqig 3-71 3.17.3 Licuid Holduo Tanks 3-72 3.17.4 Liauid Effluent Radwaste Treatment 3-72al 3.18 GASEQUS EFFLUENTS 3-73 3.18.1 Dose Rate 3-73 3.18.2 Dose-Noble Gases 3-74 3.18.3 Dose-Iodine-131. Iodine-133. Tritium. and Radioactive Materials in Particulate Form 3-75 3.18.4 Gaseous Radwaste Treatment 3-78 3.18.5 Gas Storace Tanks 3-79 3.19 DELETED 3.20 DELETED 3.21 SOLIO RADIOACTIVE WASTES 3-80 3.22 RADIOLOGICAL ENVIRONMENTAL MONITORING 3-81 3.23 LAND USE CENSUS 3-87 3.24 EXPLOSIVE GAS HIXTURE 3-89 3.25 FUEL CYCLE DOSE 3-90 3.26 INTERLABORATORY COMPARISON PROGRAM 3-92 Ar.endment No. 32,23,98 iv

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued)

Sits _ tis.a P.Asut 4.11 REACTOR BUILDING PURGE EXHAUST FILTERING SYSTEM 4-42 4.12 AUXILIARY AND SPENT FUEL BUILDING FILTER SYSTEMS 4-43 4.13 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH 4-44 ENERGY LINES OUTSIDE OF CONTAINHENT 4.14 SHOCK SUPPRESSORS (SNUBBERS) 4-47 4.15 RADIOACTIVE MATERIALS SOURCES 4-48 4.16 Reserved 4-49 4.17 STEAM GENERATORS 4-51 4.17.1 Steam Generator Samole Selection and Insoection 4-51 4.17.2 Steam Generator Tube Samole Selection and Insoection 4-51 4.17.3 Insoection Freauencies 4-52 4.17.4 Acceotance Criteria 4-53 4.17.5 Reoorts 4-54 4.17.6 OTSG Auxiliary Feedwater Header Surveillance 4-54 4.17.7 Inspection Acceptance Criteria and Corrective Actions 4-55 4.17.8 Reports 4-55 4.18 EJEE SUPPRESSION SYSTEM SURVEILLANCE 4-58 4.19 MCI 0 ACTIVE LIOUID EFFLUENT HONITORING INSTRUMENTATION 4-63 l

l 4.20 RADIOACTIVE GASEOUS EFFLUENT HONITORING INSTRUMEMTATION 4-65 4.21 LIOUID EFFLUENTS 4-69 4.21.2 Qgijtt 4-72 l

4.21.2 Dose calculations 4-72 4.21.3 Liauid Holduo Tanks 4-73 4.21.4 Liauid Effluent Radwaste Treatment 4-73a ll VI Amendment No. 7ll 5),$$,M,98

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RMCHO SECO lNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued) 4.22 GASEOUS EFFLUENTS 4-74 4.22.1 Dose Rate 4-74 4.22.2 Dose-Noble Gases 4-77 4.22.3 Dose-Iodine-131. Iodine-133. Tri tium. e.nd Radioactive Ma_terials in Particulate Form 4-79 4.22.4 Gaseous Radwaste Treatment 4-79 4.22.5 Gas Storace Tanks 4-80 4.23 Deleted 4 4.24 Oflelad 4-80 4.25 SOLID RADIOACTIVE HASTES 4-81 4.26 RADIOLOGICAL ENVIR0fNENTAL K)NITORIPG 4-83 4.27 LAfD USE CENSUS 4-86 4.28 EPLOSIVE CAS MIXTURE 4-67 4.29 FUEL CYCLE DOSE 4-89 4.30 INTERLABORATORY COPARISON PROGRM SURVEILLANCE REOUIRDENT 4-90 4.31 fDCLEAR SERVICE ELECTRICAL BUILDING ENERGENCY HEATIPG VENTILATION Am AIR C0f0ITIONING 4-91 4.32 TDI DIESEL GENERATOR CONTROL R004 ESSEhTIAL VENTILATION SYSTEM 4-92 4.34 METER 0 LOGICAL MONITORING INSTRLNENTATION 4-93 4-35 HYDA0 GEN RECOSINERS 4-95 5

DESIGN FEATURES 5-1 5.1 11IE 5-1 5.1.1 Exclusion Area 5-1 5.1.2 Low Pooulation Zone 5-1 5.1.3 Site Boundary for Gaseous and Licuid Effluents.10 CFR 50 5-1 Aco. I Guidelines 5.1.4 Site Boundarv for Liouid Effluents.10 CFR 20 Comoliance 5-1

/In6ndment No, )8, ps, %,p, f(,9; vii U,98

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATION $

TABLE OF CONTENTS (Continued)

Section PAgg 5.2 CONTAINHENT 5-2 5.2.'l Relctor Building 5-2 5.2.2 Reactor Buildina Isolation System 5-3 5.3 REACTOR 5-4 5.3.1 Reactor Core 5-4 5.3.2 Reactor Coolant System 5-4 5.4 NEH AND SPENT FUEL STORAGE FACILITIES 5-6 5.4.1 New Fuel Insoection and Temocrary Storaae Rack 5-6 5.4.2 New and Scent Fuel Storace Racks and Failed 5-6 Fuel Storace Container Rack 5.4.3 New and Soent Fuel Temocrary Storace 5-6 5.4.4 Soent Fuel Pool and Storace Rack Desian 5-6 1

kr.er.dment No. 98 viia

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued)

Section Elsa 6

ADMINISTRATIVE CONTROLS 6-1 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION 6-1 6.3 FACILITY STAFF OUALIFICATIONS 6-3 6.4 TRAINING 6-3 6.5 REVIEW AND AUDIT 6-3 6.5.1 Plant Review Committee 6-3 6.5.2 Manacement Safety Review Commitigg 6-6 6.5.3 Technical Review and Contrtl 6-8 6.5.4 Audits 6-9 6.6 REPORTABLE OCCURRENCE ACTION 6-10 6.7 1AEETY LIMIT VIOLATION 6-11 6.8 PROCEDURES 6-11 6.9 EfPORTING REOUIREMENTS 6-12 6.10 RECORD RETENTION 6-13 6.11 RADIATION PROTECTION PROGRAM 6-14 6.12 RESPIRATORY PROTECTION PROGRAM - Deleted 6.13 HIGH RADIATION AREA 6-15 6.14 ENVIRONMENTAL QUALIFICATION 6-16 6.15 PROCESS CONTROL PROGRAM (PCP) 6-17 6.16 0FFSITE DOSE CALCULATION AND RADIOLOGICAL HONITORING PROGRAM MANUALS 6-18 6.17 MAJOR CHANGES TO RADIOACTIVE HASTE TREATMENT SYSTEMS (LIOUID. GASEOUS. AND SOLID) 6-19 6.18 POSTACCIDENT SAMPLING 6-22 Amendment No. 28,53,20,93.98 viii

i RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIST OF TABLES Section EiLqe 1.2-1 OPERATIONAL K) DES 1-2c 1.9-1 FREQUENCY NOTATION 1-10 l

2.3-1 REACTOR PROTECTION SYSTEM TRIP SETTING LIMITS 2-9 3.0-1 APPLICABILITY OF SPECIFICATIONS 3.0.3 AND 3.0.4 3-0a 3.3-1 PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES 3-22a 3.5.1-1 INSTRtNENTS OPERATING CONDITIONS 3-27 3.5.5-1 ACCIDENT MONITORING INSTRlNENTATION OPERABILITY REQUIREMENTS 3-38e 3.5.7-1 EMERGENCY SHUTDOWN INSTRLNENTATION 3-38j 3.6-1 SAFETY FEATURES CONTAlfEENT ISOLATION VALVES 3-40 3.7-1 VOLTAGE PROTECTION SYSTEM RELAY TRIP VALUES 3-41a 3.7-2 VOLTAGE PROTECTION SYSTEM LIMITING CONDITIONS 4-42k 3.12-1 SAFETY RELATED HYRAULIC SNUBBERS 3-51a-e 3.14-1 FIRE DETECTION INSTRlNENTS FOR SAFETY SYSTEMS 3-55 3.14-2 WATER SUPPRESSION ZONES 3-56b,c 3.14-3 CARBON DIOXIDE SUPPRESSION ZONES 3-56d,e 3-14-4 FIRE HOSE STATIONS 3-57a,b 3.15-1 RADI0fCTIVE LIQUID EFFLUENT MONITORING INSTRlNENTATION 3-61 3.16-1 RADI0 ACTIVE GASES EFFLUENT MJNITORING INSTRLNENTATION 3-64 3.22-1 RADIOLOGICAL ENVIR0fNENTAL MONITORING PROGRNi 3-83 3.22-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS 3-86 IN ENVIR0fNENTAL SNfLES 3.29-1 METER 0 LOGICAL H3NITORING INSTRlNENTATION 3-95 4.0-1 APPLICMILITY OF SPECIFICATIONS 4.0.2 AND 4.0.3 4-0a 4.1-1 INSTRlNENT SURVEILLANCE REQUIRENENTS 4-3 l

4.1-2 MINIHN EQUIR4EW TEST FREQUENC/

4-8 4.1-3 MINIHN SNiPLING FREQUENCY 4-9 4.2-1 CAPSULE ASSEN LY WITHDRAWAL SCHEDULE AT DAVIS-BESSE 1 4-12b Amendment No. 26,53,66,68,76,77,86, ix 85,87,88,96,91,98

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RANCHO SECO UNZT 1 TECHNICAL SPECIFICATIONS LIST OF TABLES (Continued)

Ich em 4.6-1 DIESEL GENERATOR TEST SCHEDULE 4-34j 4.6-2 ADDITIO ML RELIABILITY ACTIONS 4-34k 4.14-1 DESIGNATED SAFETY RELATED HYDRAULIC SNUBBERS FUNCTIONALLY 4-47d,e TESTED ONLY AS REQUIRED BY THE SNUBBER SEAL REPLACEMENT PROGRAM 4.17-1 HINIMUH NUMBER OF STEAH GENERATORS TO BE INSPECTED 4-56 DURING INSERVICE INSPECTION 4.17-2A STEAM GENERATOR TUBE INSPECTION 4-57 4.17-28 STEAM GENERATOR TUBE INSPECTION (SPECIAL LIMITED AREA) 4-57a 4.17-3 OTSG AUXILIARY FEEDHATER HEATER SURVEILLANCE 4-57b,c 4.19-1 RADIOACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION 4-64 SURVEILLANCE REQUIREHENTS 4.20-1 RADIOACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION 4-66 SURVEILLANCE REQUIREMENTS 4.21-1 RADI0 ACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAM 4-70 4.21-2 RADIOACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAM 4-72b 4.22-1 RADIOACTIVE GASEOUS HASTE SAMPLING AND ANALYSIS PROGRAM 4-75 4.26-1 HAXIHUM VALUES FOR THE LCHER LIMITS OF DETECTION (LLD) 4-84 4.28-1 EXPLOSIVE GAS HIXTURE INSTRUMENTATION SURVEILLANCE 4-BB REQUIREMENTS l

6.2-1 HINIMUM SHIFT CREH COMPOSITION 6-2 Amendment No. 28,53,88,96,9/,98 x

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIST OF FIGURES (Continued)

Fiaure 3.5.2-7 Core Imbalance vs. Power Level, O to 40 EFPD 3.5.2-8 Core Imbalance vs. Power Level, after 30 EFPD 3.5.2-9 Core Imbalance vs. Power Level, after 300 EFPD with APSRs Withdrawr.

3.5.2-10 Deleted 3.5.2-11 Deleted 3.5.2-12 Deleted 3.5.4-1 Incore Instrumentation Specification Axial Imbalance Indication 3.5.4-2 Incore Instrumentation Specification Radial Flux Tilt Indication 3.5.4-3 Incore Instrumentation Specification 3.i8-1 General Layout of Site 4.13-1 Main Steam Inservice Inspection 4.13-2 Main Feedwater Inservice Inspection 4.13-3 Main Steam Dump Inservice Inspection 5.1-1 Exclusion Area 5.1-2 Low Population Zone 5.1-3 Site Boundary for Gaseous and Liquid Effluents,10 CFR 50 Appendix I Guidelines 5.1-4 Site Boundary for Liquid Effluents,10 CFR 20 Conformance 6.2-1 SHUD Corporate Support of Nuclear Safety to Rancho Seco 6.2-2 Nuclear Organization Chart Amendment No. 39,79,79,y),p),97,79,98 xii

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Definitions 1.11 FIRE SUPRESSION SYSTEMS 1.11.1 The FIRE SUPRESSION HATER SYSTEM shall consist of water sources, pumps and distribution piping with associated sectionalizing control of isolation valves.

Such valves include yard hydrant valves and the first valve ahead of the water flow alarm device on each sprinkler header, hose standpipe or spray system riser which protect nuclear safety components.

1.11.2 The FIRE SUPRESSION CARBON DIOXIDE SYSTEM shall consist of a CO2 source and distribution piping with sectionalizing control valves which protect nuclear safety components.

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

a.

A test schedule for n systems, subsystems, trains or designated components obtained by dividing the specified test interval into n equal subintervals.

b.

The testing of one system, subsystem, train or designated components during each subinterval.

1.13 PROCESS CONTROL PROGRAM PROCESS CONTROL PROGRAM (PCP) - The PROCESS CONTROL PROGRAM shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATION /0EHATERING of radioactive wastes from liquid systems is assured.

1.14 SOLIDIFICATION SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed),

monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).

Amendment No. IS,23,53,9S l-6

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e RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Definitions 1.15 0FFSITE DOSE CALCULATION MANUAL (00CH)

The OFFSITE DOSE CALCULATION MANUAL (OOCH) shall be a manual containing the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints.

1.16 RESTRICTED AREA That portion of the site property, the access to which is controlled by security fencing, equipment and personnel.

1.17 SITE BOUNDARY Site Boundaries are defined by Figures 5.1-1 through 5.1-4.

l 1.18 DOSE EOUIVALENT I-131 The DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose via the inhalation pathway as the quantity and isotopic mixture of I-131, I-132, I-133. I-134 and I-135 actually present.

The thyroid dose conversion factors used for this calculation shall be those listed in Regulatory Guide 1.109, "Calculation of Annual Doses to Han from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I."

1.19 MEMBER (S) 0F THE PUBLIC HEMBER(S) 0F THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant.

This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions.

This category shall D21 include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.

1.20 DEWATERING The process which removes the slurry water from ion exchange resin or filter media that has been transferred to a disposal container in a manner which provides reasonable assurance that State, Federal and disposal site free standing liquid requirements are met.

Amendment No. 53,93,98 1-7

c.

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Definitions 1.21 MAXIMUM EXPOSED (HYPOTHETICAL) INDIVIDUAL The MAXIMUM EXPOSED INDIVIDUAL is characterized as "maximum" with regard to food consumption, occupancy, and other usage or exposure pathway parameters in the vicinity of Rancho Seco that would represent an individual with habits greater than usually expected for the average of the population.in general.

1.22 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) HANUAL The RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM (REMP) MANUAL shall be a manual containing the description of the Rancho Seco radiological environmental monitoring program.

The REMP MANUAL shall contain a description of the environmental samples to be collected, the sample locations, sampling frequencies, and sample analysis criteria.

1.23 LIOUID EFFLUENT RADWASTE TREATHENT SYSTEM The LIQUID EFFLUENT RADRASTE TREATMENT SYSTEM is the system designed and installed to reduce the quantity of radioactive materials in liquid effluents by collecting liquid effluent and providing processing for the purpose of reducing the total radioactivity prior to its release to the environment.

Amendment No. 98 1-8 i

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Definitions 1.24 VENTILATION EXHAUST TREATHENT SYSTEM The VENTILATION EXHAUST TREATHENT SYSTEMS are systems 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 lodines or particulates 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 VENTILATION EXHAUST TREATHENT SYSTEMS components.

1.25 PURGE - PURGING PURGE or PURGING is 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 required to purify the confinement.

1.26 VENTING VENTING is 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, dces not imply a VENTING process.

1.27

[

E-BAR shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of average beta and gamma energies per disintegration (in HEV) for isotopes with half lives greater than 20 minutes, making up at least 95% of the total activity in the coolant (excluding iodines).

l Amendment No. 96 1-9

TABLE 1.9-1 FREQUENCY NOTATION NOTATI0d FREOUENCY S

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

H At least once per 7 days.

H At least once per 31 days.

Q At least once per 92 days.

SY At least once per 184 days.

A At least once per 12 months R

At least once per 18 months.

BA At least once per 24 months S/U Prior to each reactor startup.

P Completed prior to each release.

NA Not applicable.

Amendment No. 98 l-10

o RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.1.4 REACTOR COOLANT SYSTEM ACTIVITY Soecification 3.1.4.1 The total fission product activity of the reactor coolant due to nuclideswithhalfliveslongerthan20minutesshallnotexceed43/El microcuries per gm whenever the reactor is critical.

E is the average (mean) beta and gamma energies per disintegration, in Hev, weighted in proportion to the measured activity of the rad;onuclides in reactor coolant samples.

Bases The above specification is based on limiting the consequences of a postulated accident involving the double-ended rupture of a steam generator tube.

The rupture of a steam generator tube enables reactor coolant and its associated activity to enter the secondary system where volatile isotopes could be discharged to the atmosphere through condenser air-ejectors and through steam safety valves (which may lif t momentarily).

Since the major portion of the activity entering the secondary system is due to noble gases, the t,ulk of the activity would be discharged to the atmosphere.

The activity release continues until the operator stops the leakage by reducing the reactor coolant system pressure below the set point of the < team safety valves and isolates the faulty steam generator. The operator can identify a faulty steam generator by using the off-gas monitors on the condenser air ejector lines; thus he can isolate the faulty steam generator within 34 minutes after the tube break occurred.

During that 34 minute period, a maximum of 2740 ft3 of hot reactor coolant will have leaked into the secondary system; this is 3

equivalent to a cold volume of 1980 ft.

The controlling dose for the steam generator tube rupture accident is the whole-body dose resulting from immersion in the cloud of released activity.

To insure that the public is adequately protected, the specific activity of the reactor coolant will be limited to a value which will insure that the whole-body annual dose at the site boundary will not exceed 0.5 rem, the limit in 10 CFR Part 20 for whole body dose in an unrestricted area.

Although only volatile isotopes will be released from the secondary system, the following whole-body dose calculation conservatively assumes that all of the radioactivity which enters the secondary system with the reactor coolant is released to the atmosphere.

Both the beta and gamma radiation from these isotopes contribute to the whole-body dose. The gamma dose is dependent on the finite size and configuration of the cloud.

However, the analysis employs the simple model of a semi-infinite cloud, which gives an upper limit to the potential gamma dose. The semi-infinite cloud model is applicable to the beta dose because of the short range of beta radiation in air.

It is further assumed that meteorological conditions during the course of the accident correspond to Pasquill Type F and 0.6 meter per second wind speed, resulting in a X/Q value of 8.51 x 10-4 sec/m3 Amendment No. 87,37,98 3-8

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation The combined gamma and beta whole body dose from a semi-infinite cloud is given by:

Dose (Rem) = 0.246 5 A V X/Q p Amax (pc/gm) 0.5 (Dose) max 0.246iVX/Qp 0.246x[x77.6x8.51x10-4 x 0.713 Amax (pc/gm) - 43/5 Hhere A - Reactor coolant activity (pCi/gm - mci /Kgm) l V - Volume of hot reactor coolant leaked into secondary system (2740 ft3 - 77.6 m3)

X/0 - Atmospheric dispersion coefficient at site boundary for a two hour period (8.51 x 10-4 sec/m3) 5 - Average beta and gamma energies per disintegration (HeV) p - Density of hot reactor coolant (0.713 gm/cc)

Calculations required to determine 5 will consist of the following:

A.

Quantitative measurement of the specific activity (in units of pc/gm) of radionuclides with half lives longer than 20 l

minutes, which make up at least 95 percent of the total activity in reactor coolant samples.

B.

A determination of the average beta and gamma decay energies per disintegration for each nuclide, measured in (A) above, by utilizing known decay energies and decay schemes (e.g.,

Table of Isotopes, Sixth Edition, March 1968).

C.

Acalculationof5bytheaveragebetaandgammaenergyfor each radionuclide in proportion to its specific activity, as measured in (A) above.

Amendment No. 87,98 3-9

0;'

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.15 RADI0 ACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION l

The radioactive liquid effluent monitoring instrumentation char.nels shown in Table 3.15-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.17.1 are not exceeded.

The alarm / trip setpoints of these channels shall be determined in accordance with the methodology contained in the OFFSITE DOSE CALCULATION MANUAL (00CH).

Aeolicability During releases via the retention basin effluent discharge.

l Action a.

With a radioactive liquid effluent monitoring instrumentation thannel alarm / trip setpoint less conservative than a value which will ensure that the limits of Specificatior, 3.17.1 are met, immediately suspend the release of radioactive liquid effiuents monitored by the affected channel, or declare the channel inoperable, or change the secpoint so it is acceptably conservative, b.

Hith less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.15-1.

l Bases During normal operations, all radioactive contaminated water from primary system leaks and drains (except demineralized reactor coolant as noted below) is processed in a liquid radwaste system and recycled into the Reactor Coolant Makeup System or otherwise reused in the controlled areas of the plant.

Secondary system water is normally released from the plant.

If the secondary system water contains radioactive material it is first processed through the 'A' orB' Regenerant Hold-Up Tanks (RHUTs) and then transferred to the North or South Retention Basin.

The water in a Retention Basin is released off-site as a batch release.

These releases are monitored by the Retention Basin Effluent Discharge. During periods of primary to secondary leakage, or when the sumps are contaminated, administrative contr)ls require the liquid effluent in turbine building sumps shall be diverted to the 'A' and 'B' Regenerant Hold-Up Tanks.

Demineralized reactor coolant can be transferred from the Demineralized Reactor Coolant Storage Tank (DRCST) to the 'A' and 'B' Regenerant Holdup Tanks for sampling, processing, and eventual discharge offsite as required by operational constraints.

Under normal conditions, the once through steam generators have no blow down.

If a blow down is required during periods of primary to secondary leakage, all water will be retained and processed in the radwaste system or diverted to the 'A' and 'B' Regenerant Hold-Up Tanks.

Amendment No. 53,98 3-60

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.15 (Continued)

Bases (Continued)

Radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of radioactive liquid effluents.

The alarm / trip setpoints for these instruments shall be calculated in accordance with the methodology contained in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of specification 3.17.1.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3-60a Amendment No. 98

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.15-1 RADI0 ACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION Minimum Number of Channels Instrument Ooerable Action 1.

Gross Radioactivity Honitors Providing Automatic Termination of Release a.

Retention Basin 1

Hith the monitor inoperable, Effluent Discharge effluent releases may be resumed Monitor provided that prior to initiating a release from the retention basin:

1.

At least two independent samples are analyzed in accordance with Specification 4.21.1.

2.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

Exert best efforts to return the monitor to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.2.3 why the inoperable monitor was not restored in a timely manner.

i Amendment No. 53,98 3-61

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.1S-1 (Continued)

RADIOACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION Minimum Number of Channels Instrument Ooerable Action 2.

Flow Heasurement Devices a.

Regenerant Hold-Up 1

Hith the flow measurement device Tank Discharge Line inoperable, releases to the retention Total Flow basins may continue provided the total flow is estimated once every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by a tank level device.

b.

Haste Water Flow Rate 1 Hith the flow measurement device and Totalizer inoperable, effluent releases via this pathway may continue provided the total flow is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during retention basin releases by a level device in the discharge stream.

3-62 Amendment No. J3,98

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 1

3.16 RADI0 ACTIVE GASEQUS EFFLUENr HONITORING INSTRUMENTATICH The radioactive gaseous effluent monitoring instrumentatior. channels shown in Table 3.16-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.18.la are not exceeded.

The alarm / trip setpoints of these channels shall be determined in accordance with the methodology contained in the ODCH. Continuous simples of the gaseous effluent for radiciodines and radioactive particulate caterial shall be taken as indicated in Table 3.16-1.

&policability At all times.

l AI_ tion a.

With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than a value which will ensure that the limits of Specification 3.18.la are met, immedistely suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With less than tht minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.16-1.

Exert best efforts to return the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report submitted pursuant to Specification 6.9.2.3 why the inoperability was not corrected in a timely manner.

lbuuti The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases radioactive of gaseous effluents.

The alarm / trip setpoints for these instruments shall be calculated in accordance with the methodology contained in the 00CH to ensure that the alarm / trip will occur prior to exceeding the limits of Specification 3.18.la.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

The Auxiliary Building Stack is the effluent release point for the Haste Gas System.

The Auxiliary Building Stack Noble Gas Activity monitor will perform the necessary Haste Gas System release termination.

The monitor alarms and terminates a Haste Gas Decay Tank release automatically if the activity exceeds the setpoint limits.

Amendment No. 53,98 3-63

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS 3.16 (Continued Limiting Conditions for Operation Bases (Continued)

The condenser air ejector exhaust has an individual noble gas monitor.

This system exhausts into the Auxiliary Building ventilation system.

Therefore, the Auxiliary Building Stack is the effluent release point and will alarm u;;r, release of environmentally significant radioactive gases.

Fuel Storage Building exhaust is directed to the Auxiliary Building Stack where the exhaust is filtered and monitored for any activity prior to release to the atmosphere.

Amendment No. 98 3-63a

RANCHO SECO UNfT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.16-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Number of Channels Instrument Ooerable Action 1.

Reactor Building Purce Vent a.

Noble Gas Activity I

Hith the monitor channel alarm / trip Honitor providing setpoint less conservative alarm and automatic than the setpoint calculated as

' termination of described in the 00CH, immediately release.

suspend the release or declare the channel inoperable.

With the monitor inoperable, effluent releases via this pathway may continue provided grab samples are taken at 1 cast once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed in accordance with Table 4.22-1 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

Iodine Sampler 1

Hith the collection device inoperable, effluent releases via this pathway may continue provided continuous samples are taken within one hour after the monitor is declared inoperable and these samples are analyzed in accordance with Table 4.22-1 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . **

c.

Particulate Sampler i

Hith the collection device inoperable, effluent releases via this pathway may continue provided continuous samples are taken within one hour after the monitor is declared inoperable and these samples are analyzed in accordance with Table 4.22-1 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . **

See Table 3.5.5-1 for additional actions required for this monitor as an accident monitor.

Interruption of continuous sampling is allowed for periods not to exceed one hour.

Anendment No. 53,73,98 3-64

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operatien Table 3.16-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Hinimum Number of Channels Instrument Ooerable Action 1.

Reactor Building Purge Vent (continued) d.

System Effluent Flow 1

Hith the flow rate device Rate Device inoperable, effluent releases may continue provided the flowrateusedisthemaximu design flow rate.

e.

Sampler flow Rate 1

Hith the flow rate device Measurement Device inoperable, effluent releases via this pathway may continue provided the flow rate is estimated and recorded at least onco per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Amendment No. 33,98 3-65

o RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.16-1 (Continued)

RADI0 ACTIVE GASEQUS EFFLUENT HONITORING INSTRUMENTATION Minimum Number of Channels Instrument Ocerable Action 2.

Auxiliary Building Stack a.

Noble G&! Activity 1

Hith the monitor alarm / trip Monitor providing setpoint less conservative than the alarm and automatic setpoint calculated as described in termination of Waste the 00CM immediately suspend the Gas Header release

release or declare the channel inoperable.

With the monitor inoperable, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed in accordance with Table 4.22-1 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With the monitor inoperable, the contents of the Haste Gas System tank (s) may be released to the environment provided that prior to initiating the release:

a.

At least two independent samples of the tank's contents are analyzed, and See Table 3.5.5-1 for additional action required for this monitor as an accident monitor.

Amendment No. 53,73,98 3-66

o RANCHO SECO UN!T 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3,16-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION Hinimum Number of Channels Instrument Ooerable Action 2.

Auxiliary Building Stack (continued) b.

At least two technically l

qualified members of the facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this

pathway, b.

Iodine Sampler i

Hith the collection device inoperable, effluent releases via this pathway may continue provided continuous samplet are taken within one hour after th;; monitor is declared inoperable and these samples are analyzed in accordance with Table 4.22-1 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

Particulate Sampler 1

Hith the ecliection device inoperable, effluent releases via this pathway may continue provided continuous samples are taken within one hour after the monitor is declared inoperable and these samples are analyzed in accordance with Table 4.22-1 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . **

d.

System Effluent flow 1

Hith the flow rate device Rate Device inoperable, effluent releases via this pathway may continue provided the flow rate used is the maximum design flow rate.

l e.

Sampler Flow Rate 1

hith the flow rate device inoperable, Heasuring Devices effluant releases via this pathway may continue provided the flow rate is estimated and recorded at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Interruption of continuous sampling is allowed for periods not to exceeo one hour.

3-67 Amendment No. 53,98

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.16-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIQN Hinimum Number of Channels Instrument Ooerable as11gn 3.

Auxiliary Building l

Grade Level Vent a.

Noble Gas Activity I

Hith the monitor channel alarm /

Honitor

trip setpoint less conservative than the setpoint calculated as described in the 00CH, immediately suspend the release or declare the channel inoperable.

With the monitor inoperable, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed in accordance with Table 4.22-1 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

Iodine Sampler i

Hith the collection device inoperable, effluent releases via this pathway may centinue provided continuous samples are taken within one hour after the monitor is declared inoperable and these samples are analyzed in accordance with Table 4.22-1 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . **

See Table 3.5.5-1 for additional actions required for this monitor as an accident monitor.

Interruption of continuous sampling is allowcd for periods not to exceed one hour.

Amendment No. 53,73,98 3-68

U 2

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.16-1 (continued)

RADIOACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION Minimum Number of Channels Instrument Ooerable 6t!Lon 3.

Auxiliary Building Grade Level Vent (continued) c.

Particulate Sampler 1

Hith the collection device inoperable, effluent releases via this pathway may continue provided continuous samples are takPn within one hour after the monitor is declared inoperable and these samples are analyzed in accordance with Table 4.22-1 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .**

d.

System Effluent Flow 1 Hith the flow rate device Rate Device inoperable, effluent releases may continue provided the flow rate used is the maximum design flow rate.

l e.

Sampler Flow Rate 1

Hith the flow rate device Measurement Device inoperable, effluent releases via this pithway may continue provided the flow rate is estimated and recorded at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

l Interruption of continuous sampling is allowed for periods not to exceed one hour.

-t Amendment No. 33,73,98 3-69

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.17 LIQUID EFFLUENTS 3.17.1 Concentration The concentration of radioactive material released in liquid effluents at any time beyond the Site Boundary For Liquid Effluents (see Figure 5.1-4) snall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall be limited to 2x10-4 pCi/mi total attivity.

ADolicability At all times Action With the concentration of radioactive material released from the site exceeding Specification 3.17.1, immediately restore concentration within the specification limits and report the event in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.2.3:

31111 This Specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to areas beyond the Site Boundary For Liquid Effluent (see figure 5.1-4) will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within the limits of 10 CFR Part 20.106 to HEMBER(S) 0F THE PUBLIC.

The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its HPC in air l (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

Amendment No. 53,$7,98 3-70

i o

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Tne dose or dose commitment to a MAXIMUM EXPOSED (HYPOTHETICAL) l INDIVIOUAL from radioactive materials in liquid effluents released beyond the Site Boundary For Liquid Effluents (see Figure 5.1.3) l shall be limited to:

a.

Less than or equal to 1.5 mrem to the total body and to less than or equal to 5.0 mrem to any organ during any calendar quarter; and, b.

Less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ during any calendar year.

Acolicability At all times Action a.

With the calculated dose or dose commitment from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report pursuant to Specification 6.9.5.

This i Report will identify the cause(s) for exceeding the limit (s) and define the corrective actions to be taken to reduce the releases of radioactive material in liquid effluents and the l

proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

E1111 This specification is provided to implement the requirements of Sections II. A, III. A and IV. A of Appendix I,10 CFR Part 50.

The Limiting Condition for Operatien implements the guides set forth in Section II. A of Appendix 1.

The l

ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." The dose calculation methodology in the l

OOCH implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the OOCH for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"

Revision 1, October 1977 and Regulatory Guide 1.113. "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

There is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in finished drinking water that are in excess of the requirements of 40 CFR 141.

Amendment No. 53,98 3-71 L

a e

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.17.3 Licuid Holduo Tanks The quantity of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 Curies l excluding tritium and dissolved or entrained noble gases:

a.

"A" and "B" Regenerant Holdup Tanks b.

Borated Hater Storage Tank c.

Demineralized Reactor Coolant Storage Tank d.

Miscellaneous Hater Holdup Tank e.

Outside Temporary Tanks Acolicability At all times Action With the quantity of radioactive material in any of the listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, and initiate actions to reduce the tank contents to within the limit.

Reduce the tank contents to within the limit within the next 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report.

f1112.1 Restricting the quantity of radioactive material contained in the specified outdoor tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting l

concentration at the nearest potable water supply and the nearest surface water supply in an unrestricted area would be less than the limits of 10 CFR 20, Appendix B, Table II, Column 2.

The limit applies to nth tank individually.

l Tanks included in this specification are those outdoor tanks that are nct 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 or the LIQUID EFFLUENT RADHASTE TREATHENT SYSTEM.

Amendment No. 53,98 3-72 l

RANCHO SECO UNIT 1 TECHNICAL SPFCIFICATIONS Limiting Conditions for Operation 3.17.4 Liould Effluent Radwaste Treatment The LIQUID EFFLUENT RA0 HASTE TREATHENT SYSTEM shall be OPERABLE.

The appropriate portions of the system shall be used to reduce the quantity of radioactive materials in liquid effluents prior to their discharge when projected doses due to the liquid effluent beyond the Site Boundary for Liquid Effluents (see Figure 5.1-3) when averaged over 31 days, would exceed 0.25 mrem to the total body _or 0.83 mrem to any organ.

Aeolicability At all times.

Action a.

With the LIQUID EFFLUENT RA0 HASTE TREATHENT SYSTEM inoperable for more than 31 days or with radioactive 11guld waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.5 a Special Report which includes the following information:

1.

Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability.

2.

Action (s) taken to restore the inoperable equipment to OPERABLE statJs, and 3.

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

flaiti The OPERABILITY of the LIQUID EFFLUENT RADHASTE TREATHENT SYSTEM ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used, when specified, provides reasonable assurance that the releases of radioactive materials in liquid effluents are maintained "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the LIQUID EFFLUENT RADWASTE TREATHENT SYSTEM are the dose design objectives set forth in Section II.A of Appendix I,10 CFR Part 50, for liquid effluents.

Amendment No. 98 3-72a

O RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operaticr.

3.18 GASEOUS EFFLUENTS 3.18.1 Dose Rate The dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the Exclusion Area Boundary (see Figure 5.1-1) shall be limited to the following values:

The dose rate limit for noble gases shall be less than or eaual a.

to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin; and, b.

The dose rate limit for Iodine-131, Iodine-133, tritium, and for all radioactive materials in particulate form with half lives greater than 8 days shall be less than or equal to 1500 mrem /yr to any organ.

Acolicability At all times Action With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the limit (s) given in Specification 3.18.1 and report the event in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.2.3.

BAlti This specification is provided to ensure that the dose rate from gaseous effluents due to immersion or inhalation at any time at the Exclusion Area Boundary (Figure 5.1-1) will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentration of 10 CFR Part 20, Appendix B. Table II, Column 1.

These limits provide reasonable assurance that radioactive material discharguf in gaseous effluents will not result in the exposure of an individual in an unrestricted area to annual average concentrations exceeding the dose rate equivalent, on which the limits specified in Appendix B Table II of 10 CFR Part 20 (10 CFR Part 20.106 (b)(1)) were derived.

For individuals who may at times be within the Exclusion Area Boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the Exclusion Area Boundary to less than or equal to 500 mrem /yr to the total body or to less than or equal These release rate limits also restrict, at all to 3000 mrem /yr to the skin.

times, the corresponding thyroid dose rate above background to a person of any age group via the inhalation pathway to less than or equal to 1500 mrem /yr.

Amendment No. 53,98 3-73

O e

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.18.2 Dose-Noble Gases The air dose due to noble gases released in gaseous effluents to areas at or beyond the Site Boundary For Gaseous Effluents (see Figure 5.1-3) shall be limited to the following:

a.

During any calendar quarter, to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad fer beta radiation; and, b.

During any calendar year, to less than or equal to 10 mrad for gamma radiation and to less than or equal to 20 mrad for beta radiation.

Acolicability At all times Action Hith the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above.'imits, prepare and submit to the Commission within 30 days a Special Report pursuant to Specification 6.9.5.

This Report will identify the cause(s) for exceeding the limit (s) and define the corrective action (s) taken to reduce the release of radioactive noble gases in gaseous l

effluents, and the corrective action (s) to be taken to assure that subsequent releases will be in compliance with the abovelimits, fbuli This specification is provided to implement the requirements of Sections II.8, III.A, and IV.A of Appendix I, 10 CFR Part 50.

The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I.

The ACTION statements provide the required cporating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievt.ble".

The Surveillance Requirements implement the requirempnts in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated.

The dose calculations established in the OOCH for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109.

"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"

Revision 1, October 1977 and Regulatory Guide 1.111. "Hethods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors", Revision 1 July 1977.

Tne ODCH equations provided for determining that the air doses at the Site Boundary for Gaseous Effluents (Figure 5.1-3) are based upon the historical average atmospheric conditions.

Amendment No. 53,98 3-74

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.18.3 Dose-Iodine-131. Iodine-133. Tritium and Radioactive Materials in PEticulate Form.

The dose or dose commitment to a MAXIMUM EXPOSED (HYPOTHETICAL)

I!4DIVIDUAL from Iodine-131 Iodine-133, tritium, and radioactive materials in particulate form with half-lives greater than eight days in gaseous effluents released to areas at or beyond the Site Boundary for Gaseous Effluents (see Figure 5.1-3) shall be limited to the following:

a.

During any calendar quarter, to less than or equal to 7.5 mrem to any organ; and, b.

During any calendar year, to less than or equal to 15 mrem to any organ.

Aeolicability At all times Action With the calculated dose or dose commitment from the release of Iodine-131, Iodine-133, tritium, and radioactive materials in particulate form with half-lives greater than eight days in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report pursuant to Specification 6.9.5.

This Report will identify tre cause(s) far exceeding the limit and defines the corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent release will be in compliance with the above annual limits.

Bases This specification is provided to implement the requirements of Sections II.C.

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

The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implemet.i the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCH calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with th$ guides of Appendix I be shown by calculational procedures based on mos'els and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.

For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmosphedc dispersion factor above that for the restricted area boundary.

Amendment No. 53,98 3-75

o RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.18.3 (continued)

Batti (continued)

Th; ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliante with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.111. "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Hater-Cooled Reactors", Revision 1, July 1977.

These equations also provide for estimating doses based upon the historical average atmospheric conditions.

For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric dispersion factor above that for the restricted area boundary.

The release rate specifications for radioiodines and radioactive materials in particulate form are dependent on the existing radionuclide pathways to man in areas at or beyond the Site Boundary for Gasecus Effluents (Figure 5.1-3).

The pathways which were examined in the development of these calculations are:

(1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.

l Amendment No. 53,98 3-76

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS i

LIMITING CONDITIONS FOR OPERATION This page has been intentionally left blank.

l l

3-77 Amendment No. 53,98

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.18.4 Gaseous Radwaste Treatment The Haste Gas System and the VENTILATION EXHAUST TREATHENT SYSTEM shall be OPERABLE.

The appropriate portions of these systems shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected air doses due to gaseous effluent releases (see Figure 5.1-3), averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 5.1-3), when averaged over 31 days, would exceed 0.3 mrem to any organ.

Aeolicability When Gaseous Radwaste Treatment System and/or Ventilation Exhaust Treatment Systerr, are not being used.

Action a.

With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days a Special Report pursuant to Specification 6.9.5 which includes l

the following information:

1.

Explanation of why gaseous radwaste was being discharged without treatment, and identification of the equipment or subsystems not OPERABLE and the reason for inoperability.

2.

Action (s) taken to restore the inoperable equipment to OPERABLE status.

3.

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

Bases The OPERABILITY of the Haste Gas System and the VENTILATION EXHAUST TREATHENT l

SYSTEM ensures that the systems is available for use whenever gaseous effluents require treatment prior to release to the environment.

The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents are maintained "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the systems are the dose design objectives set forth in Sections II.B and II.C of Appendix I, l

10 CFR Part 50, for gaseous effluents.

Amendment No. 53,98 3-78

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.18.5 Gas Storace Tanks l

The quantity of radioactivity contained in each waste gas decay tank shall be limited to less than or equal to 135,000 curies of noble i

gases (considered as Xe-133).

Acolicability At all times Action a.

When the reactor coolant system activity reaches the limit of Specification 3.1.4, sample the on line waste gas decay tank daily to ensure that the 135,000 curie equivalent Xe-133 limit is not exceeded.

b.

With the quantity of radioactive material in any waste gas decay 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, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.2.3.

Bh.121 Restricting the quantity of radioactivity contained in each waste gas decay tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to an individual at the exclusion area boundary (See Figure 5.1-1) will not exceed 500 mrem.

This is l

consistent with Standard Review Plan 15.7.1, "Haste Gas System Failure."

Potential atmospheric releases from a waste gas decay tank are evaluated assuming design coolant activities (see page 140-25 Vol. VI FSAR).

Based on primary coolant activity as shown in Table 14D-7, the decay tank is assumed to hold the activity associated with the off-gas from one reactor coolant system degassing with no credit taken for decay.

Calculation of the limiting decay tank activity based on the coolant activity limit of Technical Specification 3.1.4 yields a maximum decay tank inventory of 98,414 Ci (Ref. FSAR Table 140-33).

In order for the decay tank inventory to reach the limiting condition for operation, coolant activity would have to exceed the Technical Specification 3.1.4 limit on coolant activity and this would require a reactor shutdown, thus preventing a further increase in gaseous activity.

Therefore, it is conservative to require'that the online waste gas decay tank be sampled _ daily upon reaching the reactor coolant system limiting activity l

value (43/E) to ensure the 135,000 curies equivalent Xe-133 is not exceeded.

Once the coolant is below the limiting activity, there is no requiremer.t to sample waste gas decay tanks except for discharging.

Amendment No. 53,98 3-79

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.22 RADIOLOGICAL ENVIRONMENTAL MONITORING The Radiological Environmental Monitoring Program shall be conducted I as specified in Table 3.22-1.

Aeolicability At all times Action a.

With the Radiological Environmental Monitoring Program not being i

conducted as specified in Table 3.22-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Specification 6.9.2.2, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

(Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, or seasonal unavailability.)

l b.

With the level of radioactivity in an environmental sampling medium exceeding the reporting level of Table 3.22-2 when averaged over any l calendar quarter, in addition to complying with the requirements of specification 3.25a, prepare and submit to the Commission within 30 days after the level of radioactivity has been determined, a Special Report pursuant to Specification 6.9.5 which includes an evaluation l of any release conditions, environmental factors or other aspects wh'ch caused the reporting limits to be exceeded.

This report will define corrective actions to reduce emissions such that potential exposures will meet Specifications 3.17.2, 3.18.2, and 3.18.3.

When more than one of the radionuclides in Table 3.22-2 are detected in the sampling medium, thi.s report shall be submitted if:

Concentration (1)

+

Concentration GD_. +

21.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 3.22-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifications 3.17.2, 3.18.2, and 3.18.3.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c.

With milk or fresh leafy vegetation samples unavailable from any of I

the sample locations required by Table 3.22-1, identify the cause of the unavailability of samples and the locations for obtaining replacement samples in the next Annual Radiological Environmental Operating Report. The locations from which samples were unavailable may then be deleted from Table 3.22-1 provided the locations fron which the replacement samples were obtained are added to the Radiological Environmental Monitoring Program as replacement locations, if available.

Amendment No. 53,98 3-81

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operatier 3.22 (continued)

HA12.1 The Radiological Environmental Monitoring Program required by this

[

specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of. individuals resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and ODCH modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979.

The specified monitoring program is in effect at this time.

Program changes may be initiated based on operational experience, and changes in regional population or agricultural practices. The sample locations have been listed in the RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM (REMP) MANUAL to retain flexibility for making changes as needed.

The detection capabilities required in Table 4.26-1 are state-of-the-art for routine environmental measurements in industrial laboratories. The LLD's for drinking water meet the requirement of 40 CFR 141.

3-82 Amendment No. 33,98

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.22-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Minimum Sampling and Exposure Pathway Number of Collection Type and Frequency and/or Samole Samoles*

Frecuency of Analysis 1.

AIRBORNE A. Radioiodine 8

Continuous oper-Radiolodine canis-and Parti-ation of sampler ter. Analyze at culates with sample least once weekly l

collection as for I-131.

required by dust loading but at Particulate least once per sampler. Analyze

week, for Gross Beta radioact ity at l

1eas: 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months tulioving filter change.

Perform gamma isotopic analysis on each sample where gross beta activity is greater than 10 times the yearly mean of control samples for the same sample period.

Perform gamma iso-topic analysis on composite (by location) for particulate filters sample at least once per quarter.

2.

DIRECT At least 40 At least once Gamma dose. At RADIATION locations with 2 per quarter.

least once per dosimeters at each quarter.

location.

Sample locations are shown in the REMP HANUAL.

Amendment No. 53,98 3-83

4.

4 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.22-1 (Continued) t RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM Minimum Sampling and Exposure Pathway Number of Collection Type and Frequency and/or Samole Samoles*

Frecuency of Analysis 3.

WATERBORNE a.

Surface 1

Composite Gamma isotopic sample collected and tritium monthly analysis of each composite.

3 Grab sample Gamma isotopic and collected tritium analysis of

monthly, each sample, b.

Run'off 1

Grab sample Gamma isotopic and collected tritium analysis of fortnightly.

each sample.

c.

Ground 2

At least once Gamma isotopic, per quarter, and tritium analysis of each sample.

d.

Hud and 2

At least once Gamma Isotopic Silt semi-annually, analysis of One pint sample each sample.

of the top 3" of material 2 ft, from shoreline.

1-l i

Sample locations are shown in the REMP MANUAL.

I i

Amendment No. 53,98 3-84

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.22-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Minimum Sampling and Exposure Pathway Number of Collection Type and Frequency and/or Samole Samoles*

Frecuency of Analysis 4.

INGESTION a.

Milk 4

At least weekly Gamma isotopic when animals analysis and are on pasture; I-131 analysis of at least once each sample, per month at other times, b.

Fish and 3

At least Gamma isotopic Inverte-quarterly. One analysis on edible brates sample of each portion of each species as sample.

listed in the REMP HANUAL.

1 c.

Food 4

At time of har-Gamma isotcpic vest. One sam-analysis on pie of each of edible portion the several of each sample.

classes of food products as shown in the REMP HANUAL.

0 ample locations are identified in the REMP HANUAL.

l 4

Amendment No. 11,98 3-85

[

RANCHO SECO UNIT 1 TICitNICAL SPECIFICATIONS O

Liniting Conditions for Operation S

Table 3.22-2

,5 R[PORTIMJIV{L$_[QR_RA0[QAXTJIVITY (QN{EN1RALION$_INJNVIRONNEN1_A(SAMPLES Reporting Levels u

Water Airborne Particylate Fish Milk Food Products Analysis (pCi/1) or Gases (oCi/si')

(pCi/kg, wet)

(pCi/1)

(pCi/kg, wet) 4 H-3 2x 10 (a) 4 Mn-54 1a 103 3a 10 4

Fe-59 4x 102 1m 10 4

Co-58 1 x 103 3a 10 4

Co-60 3x 102 1 = 10 4

Zn-65 3a 102 2m 10 Zr-Nb-95 4x 102 (b) y h

I-131 2

0.9 3

1x 102 Cs-134 30 10 1a 103 60 1x 103 Cs-137 50 20 2x 103 70 2x 103 Ba-La-140 2x 102 (b) 300 (b)

Gross 1, eta 40 2

(a) For drinking water samples, this is 40 CFR Part 141 value.

(b) Total for parent and daughter.

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.23 LAND USE CENSUS A land use census shall be conducted annually and shall identify the location of th6 nearest milk animal, the nearest residence and the nearest garden' of greater than 500 square feet producing fresh leafy vegetation in each of the 16 meteorological sectors within a l

distance of five miles.

The Land Use Census shall also include information relevant to the liquid effluent pathway and gaseous effluent pathway such that the OFFSITE DOSE CALCULATION MANUAL (ODCM) and the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL can be kept current with the existing environmental and societal uses surrounding Rancho Seco.

ADolicability At all times Action a.

With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Specifications 4.21.2, and 4.22.3, identify the new locations in the next Annual Radiological Environmental l

Operating Report, b.

With a land use census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposcre pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.22, add the new location (s) to the Radiological Environmental Honitoring Program within 30 days or submit 3 Special Report to the Commission pursuant to Specification 6.9.5 that identifies the cause(s) for exceeding these requirements and the proposed corrective actions for precluding recurrence.

The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s) (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

Identify the new location (s) in the next Annual Radiological Environmental Operating Report and also l

include in the report a revised figure (s) and table for the REMP manual reflecting the new location (s).

Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest 0/0 in lieu of the garden census.

l An.endment No. 53,98 3-87

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS 3.23 (Continued)

Bases This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the Radiological Environmental Monitoring Program and the ODCH are made if required by the results of this census.

This census satisfies the requirements of Section IV.B.3 cf Apper. dix I to 10 CFR Part 50.

Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetation will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.

To determine this minimum garden size, the following assumptions were used: (1) that 20 percent of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage); and (2) a vegetation yield of 2 kg/ square meter.

In addition, by gathering information on the liquid effluent pathway and the gaseous effluent pathway, the census provides assurance that proper radiological environmental monitoring and radioactive effluent controls are in place for the adequate protection of the health and safety of the general public.

Amendment No. 53,98 3-8S

RANCHO SECO Ut4IT 1 TECHt4ICAL SPECIFICATIONS Limiting Conditions for Operation 3.25 FUEL CYCLE DOSE The dose or dose commitment to any real HEMBER OF THE PUBLIC due to releases of radioactive material in gaseous and liquid effluents and to direct radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which is limited to less than or equal to 75 mrem) in a calendar year.

Aeolicability At all times Action a.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.17.2.a. 3.17.2.b, 3.18.2.a. 3.18.2.b, 3.18.3.a or 3.18.3.b or exceeding the reporting levels of Table 3.22-2, calculations shall be made including direct radi6 tion contributions (including outside storage tanks, etc.) to determine whether the above limits of Specification 3.25 have been exceeded, b.

If the above limits have been exceeded, prepare and submit to the Commission within 30 days, a Special Report pursuant to Specification 6.9.5 that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report) as defined in 10 CFR Part 20.405(c), shall include an analysis that estimates the radiation exposure (dose) to a HEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, in a calendar year that includes the release (s) covered by this report.

It shal' also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

c.

If the estimated dose (s) extced the above limits, and if the release condition resulting in the violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provision of 40 CFR Part 190. Submittal of the report is consider 6d a timely request, and a variance is granted until staff action on the request is complete.

B1111 This specification is provided to meet the dose limitations of 40 CFR 190 that have been incorporated into 10 CFR 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the numerical guides for design objective doses of Appendix I or exceeds the reporting levels for the Raciological Environmental Monitoring Program. For the Rancho Seco site it is unlikely that the resultant dose to a HEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the plant remains within twice the numerical guides for design objectives of 10 CFR 50 Appendix I and if direct radiation (outside storage tanks, etc.) is kept small. The Special Amendment No. 53,98 3-90

o RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.25 (Continued)

H1111 (Continued)

Report will describe a course of action which should result in the limitation of the dose to a HEH8ER CF THE PUBLIC for a calendar year to within the 40 CFR 190 limits.

For the purposes of the Special Report, it may be assumed that the dose commitment to the HEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions fran other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered.

If the dose to any HEMBER OF THE PUBLIC is evaluated to exceed the requirements of 40 CFR 190 the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 P'.ve not already been corrected), in accordance with the provisions of 40 CFR 190 is considered to be a timely request and fulfills the requirements of 40 CFR 19C until NRC staff action is completed. An individual is not considered a HEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation which is part of the uranium fuel cycle.

3-9I Amendment No. 33,$1,98

RANCHO 5 C0 UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.26 INTERLABORATORY COMPARISON PROCRAM The contractor performing the analysis cf radiological environmental monitoring samples for radioactive materials shall participate in an l

Interlaboratory Comparison Program approved by the Commission.

Acclicability At all times Action Hith analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.2.2.

2 Bases The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR 50.

i

(

F i

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Amendment No. 53,98 3-92

RANCHO SECO tmIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards D

Table 4.1-1 (Continued)

INSTRUMI M MENTS ef, Channel Description Check Test Calibrate Remarks

42. Reactor 8vtiding drain accussistion tank level m

E R

43.

Incore neutron detectors M(1) m M

(1) Check functioning, including functioning of computer readout and/or recorder readout.

44

a. Process radiation mon'.toring system W

Q R

O

b. Area radiation monitoring system W

M Q

c.

Chierine Detector V(1)

M(1)

R(1)

(1) Only required if the total m

quantity of gaseous chlorino in the RESTRICTED AREA

d. Containment Area Monitors W

~

m R

45.

Emergency plant radiation g

Instruments M(1) m W

(1) Battery check h

46.

Environmental air monitors M(1) m P.

(1) Check functioning

47. Strong motten acceleremeter Q(1) m K

(1) Battery check

48. Deleted 49.

Pressuriser Water Level M

M R

50. Assillary Feedwater Flow Rate M

M R

51. Spent Fue' Pool Level w(1) m R

(1) Dally during refueling when moving fuel or control rods.

52. EMOV Power Position Indicator (Primary Detector)

M M

R

53. EMOV Position Indicator (Ba;%up Detector)

M m

R T/C or Acoustic

54. EMOV elect valve Position Indicator M

M R

55. Safety Valve Position In-dicator (Primary Detector)

M M

R T/C

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.1-3 HINIMUM SAMPLING FREQUENCY Item Check Frequency

~ Reactor coolant

a. Badio-chemical analysis (l)

H 1.

E determination (3)l4)(6)

Semiannually l

b. Gross activity (1) (3) 3/ week

c. Tritium radioactivity H

d. Chemistry (Cl and 0 )

3/ week 2

e. Boron concentration 2/ week

f. Fluccide H

2.

Borated water Boron concentration (5)

H and after each storage tank makeup water sample 3.

Core flooding tank Boron concentration (3)

H and after each water sample makeup 4.

Spent fuel storage Boron concentration H and after each water sample makeup 5.

Secondary coolant

a. Gross activity (3)

Weekly

b. Iodine analysis (2)(3)

Weekly 6.

Concentrated boric Boron concentration (5) 2/ week and after l

acid tank each makeup 7.

Spray' additive NaOH concentration (3)

Q and after tank each makeup each makeup 8.

Cooling Tower Gross activity (3)

H water E

f Amendment No. 12,98 4-9

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.1-3 HINIMUM S'*:PLING FREQUENCY Table NotatiRD (1)Hhen radioactivity level is greater than 20 percent of the limits of Technical Specification 3.1.4, the sampling frequency shall be increased to a 1

minimum of once each day.

(2)Hhen gross activity increases by a factor of two above normal, an iodine analysis will be made and performed thereafter when the gross activity increases by ten percent.

(3)Not performed during cold shutdown.

(4)E determination will he started when a gross activity analysis indicates greater than 10pCi/gm.

E will be redetermined each 10pCi/gm increase in gross activity. A radio chemical analysis for this purpose shall consist of a quantitative measurement of 95% of radionuclides in reactor coolant with half lives of >20 minutes, t

(5)Not required during periods when systems are shutdown for maintenance.

(6) Sample to be taken after a minimum of 2 EFPO and 20 days of power operation have elapsed since the reactor was last subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or longer.

i i

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Amendment No. 12,98 4-9a

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.19 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION l

Surveillance Rcauirements The maximum setpoint shill be determined in accordance with methodology as described in the Offsite Dose Calculation Manual (ODCH) and shall be recorded on the release permits.

Each radioactive liquid ef fluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the INSTRUMENT CHANNEL CHECK, SOURCE CHECK, INSTRUMENT CHANNEL CALIBRATION, AND CHANNEL TEST at the frequencies shown in Table 4.19-1.

Records shall be maintained in accordance with the Process Standards of all radioactive liquid effluent monitoring instrumentation alarm / trip setpoints.

Maxbnum setpoints and setpoint calculations shall be available for review to ensure that tha limits of Specification 3.17.1 are met.

fifuLt1 The radioactive liquid effluent monitoring in;trumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential release of radioactive liquid effluents.

The alarm / trip setpoints for these instruments shall be calculated in accordance with the methodology contained in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of Specification 3.17.1.

Tla OPERABILITY and use of this instrumentation is consistent witn the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

Amendment No. 53,98 4-63

. ~.

!l -

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.19-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Ins truiiunt Channel Source Channel Channel Instrument Chath Check Calibration 1g11 1.

Gross Radioactivity

' Monitors Providing Alarm and Automatic Isolation a.

Retention Basin O(l)

P R(2)

Q(3)

Effluent Discharge Monitor 2.

Flow Monitors a.

Regenerant Hold-up 0(4)

NA R

Q Tank Discharge Line Total Flow b.

Haste Water Flow 0(4)

NA R

Q Rate and Totalizer Amendment No. 53,98 4-64

RANCHO SFC0 UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.19-1 (Continued)

TABLE NOTATION (1) During releases via this pathway, a check shall be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

(2) The instrument Channel Calibration for radioactivity measurement instrumentation sts11 be performed using one or more reference standards.

(3)

The Channel Test shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:

a.

Instrument indicates measured levels above the alarm / trip setpoint.

b.

Circuit failure.

c.

Instrument indicates a downscale failure.

d.

Instrument controls do not set in operate mode.

(4) The Instrument Channel Check shall consist of verifying indication of flow during periods of release. The Instrument Channel Check shall be made at least once daily on any day on which batch releases are made.

Amendment No. 53,98 4-64a L

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.20 RADI0 ACTIVE GASEQUS EFFLUENT HONITORING INSTRUNENTATION Surveillance Reauirements The maximum setpoints shall be determined by procedures implementing the rathodology described in the OFFSITE DOSE CALCULATION MANUAL (ODCH) and shall be recorded on release permits.

Each radioactive gaseous effluent monitoring instrumentction channel shall be demonstrated OPERABLE by performance of the INSTRUMENT CHANNEL CHECK, SOURCE CHECK, INSTRUMENT CHANNEL CALIBRATION, AND CHANNEL TEST at the frequencies shown in Table 4.20-1.

Records shall be maintained in accordance with the Process Standards of all l

radioactive gaseous effluent monitoring instrumentation alarm / trip setpoints.

Maximum setpoints and setpoint calculations shall be available for review to ensure that the limits of Specification 3.18.1 are met.

l Bases The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of radioactive gaseous effluents.

The alarm / trip setpoints for these instruments shall be calculated in accordance with the methodology contained in the ODCH to ensure that the alarm / trip will occur prior to exceeding the limits of Specification 3.18.1.

The OPERABILITY and use of this instrumentation is consistent with the requirements and General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

The flow rates in the Auxiliary Building Stack and Auxiliary Building Grade Leve! Vent are constant as they use single speed fans.

The Reactor Building Purge Vent has a constant release rate. However, releases from the Reactor Building may be at three different flowrates, winter, summer or minipurge.

Administrative controls assure that the correct flowrate is used.

The flow rates of the ventilation systems are periodically determined by surveillance procedures.

The flow rate devices must be removed from the ventilation systems for the channel test, and in addition transported to the manufacturer for calibration.

The frequencies have been set as shown in Table 4.20-1.

Amendment No. 33,98 4-65

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.20-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS Instrument Instrument Channel Source Channel Channel Instrument ChjLG Chftd Calibration Tnt 1.

Reactor Building Purge Vent a.

Noble Gas Activity Monitor D

M(4)

R(3) g(1)l b.

Iodine Sampler H

NA NA NA c.

Particulate Sampler H

NA NA NA d.

System Effluent Flow Rate Device D

NA R

Q(6) l e.

Sampler Monitor Flow Rate Measurement Device D

NA R

Q l

2.

Auxiliary Building Stack a.

Noble Gas Activity Monitor O(5)

M R(3)

Q(7) l b.

Iodine Sampler H

NA NA NA c.

Particulate Sampler H

NA NA NA d.

System Effluent Flow Rate Device D

NA R

Q(6)l e.

Sampler Monitor Flow Rate Measurement Device D

NA R

Q l

Amendment No.53,73,57,98 66

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.20-1 (Continued)

Instrument Instrument Channel Source Channel Channel Instrument Check Check Calibration Igil 3.

Auxiliary Building l

Grade Level Vent a.

Noble Gas D

H R(3) g(2) l Activity Monitor b.

Iodine Sampler H

NA NA NA c.

Particulate H

NA NA NA Sampler d.

System Effluent D

NA R

Q l

Flow Rate Device e.

Sampler Honitor D

NA R

Q l

Flow Rate Measurement Device i

Amendment No. 53,73,87,98 4-67

~ -.

P RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.20-1 (Continued)

TABLE NOTATION (1)

The CHANNEL TEST shall also demonstrate that automatic termination of the purge and control room alarm annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

4.

Instrument controls not set in operate mode.

(2)

The CHANNEL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Circuit failure.

3.

Iristrument indicates a downscale failure.

4 Instrument controls not set in operate mode.

(3) The INSTRUMENT CHANNEL CALIBRATION shall be performed using one or more reference standards.

(4) A check shall be performed prior to each release.

(5) A check shall be performed prior to each release via a Haste Gas Decay Tank (s).

(6) To be performed when device is accessible and conditions do not pose a personnel safety hazard (i.e., potential main steam safety actuation).

(7)

The CHANNEL TEST shall also demonstrate that the Waste Gas System automatically isolates and that control room annunciation occurs if any of the following conditions exist:

1.

Instrument indictes measured levels above the alarm / trip setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

4.

Instrument controls not set in operate mode.

Amendment No. 53,73,87,98 4-68

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.21 LIQUID EFFLUENTS 4.21.1 Concentration Surveillance Reauirements The concentration of radioactive material at any time in liquid effluents released from the site shall be continuously monitored in accordance with Table 3.15-1.

The liquid effluent continuous monitor having provisions for automatic termination of liquid releases, as listed in Table 3.15-1, shall be used to limit the concentration of radioactive material released at any time from the site to areas beyond the site boundary to the limits given in Specification l

3.17.1.

The radioactivity content of each batch of liquid effluent to be discharged shall be determined prior to release by sampling and analysis in accordance with Table 4.21-1.

The results of pre-release analyses shall be used with the calculational methods in the OFFSITE DOSE CALCULATION MANUAL (00CM) to assure that the concentration at the point of release is limited to the limits of Specification 3.17.1.

l Bases This Specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to areas beyond the site boundary for liquid effluent will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2.

This limitation l

provides additional assurance thht the levels of radioactive materials in bodies of water outside the site will result in exposures within the limits of 10 CFR Part 20.106 to HEMBER(S) 0F THE PUBLIC.

The concentration limit for l

dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its HPC in air (submersion) was converted to l

an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

There are no continuous releases of radioactive material in liquid effluents from the plant. All radioactive liquid effluent releases from the plant are by batch method.

Amendment No. 53,98 4-69

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.21-1 RADI0 ACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAM Sampling Minimum Analysis Type of Activity Lower Limit Liquid Release Frequency Frequency Analysis Of Detection Type (LLD)

(UCi/ml)(a)

A. Batch Waste Re-Each Batch Each Batch Principal 2E-8 lease Tanks (b,d)

Gamma Emitting P

P Nuclides (c)

I-131 6E-8 Dissolved and IE-5 Entrained Gases (Gamma Emitters)

H-3 1E-5 Amendment No. 53,98 4-70

O RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.21-1 (Continued)

RADI0 ACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAM Table Notation a.

(1) The lower limit of detection (LLD) for a radionuclide presented in this table is the smallest concentration, expressed in microcuries per milliliter, which is required to be detected, if present, in order to achieve compliance with the limits of Specification 3.17.1 (10CFR20, Appendix

, Table II, Column 2).

(2)

The LLO of a radioanalysis system is that value which will indicate the presence or absence of radioactivity in a sample when the probability of a false positive and of a false negative determination is stated.

The probabilities of false positive and false negative are taken as equal at 0.05.

The equation for LLO in microcuries per milliliter is given by the equation:

LLD - 2.71 + 3.29(Br)0.5 3.70E4(YEVT) v:here 2.71 - factor to account for Poisson distribution at very low background count rates.

When background is estimated from a blank which Ias been cotnted fcr a specific period, the following applies:

B - estimated background (counts) t

-b g

tb b - blank background (counts) tb - blank count time (seconds) ts - sample count time (seconds) t r-1+

3 tb Aciendcient No. 53,98 4-71

c RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.21-1 (Continued)

RADIOACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAM Table Notation 3.70E4 - disintegrations /second/ microcurie Y - yield of radiochemical process, i.e., the product of all factors such as emission fraction, chemical yield, etc.

E - counting efficiency (count / disintegrations)

V - sample volume (milliliters)

T - [1-exo(-Xts)lexo(-Xtel X

where X - decay constant (seconds -I) tc - time from midpoint of collection to start of counting (3)

When spectroscopy is used to analyze the sample, the fcilowing LLD equation is used:

LLD -

2.71 + 4.65(B)0.5 3.70E4 (YEVT)

Where B is the counts in the Region Of Interest.

(4)

The LLD is defined as an a priori (before the fact) limit and not as an a posteriori (after the fact) limit.

Amendment No. 98 4-71a

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.21-1 (Continued)

RADIOACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAM Table Notation b.

Prior to discharge from the 'A' or '8" RHUT, samples are collected and analyzed for accountability of activity in the Retention Basins. Prior to sampling the RHUTs, each batch will be isolated, and then thoroughly mixed, to assure representative sampling. A batch release is the discharge of liquid wastes of discrete volume from the north or south Retention Basin. Samples will also be collected from the Retention Basin and analyzed prior to discharge.

c.

The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Hn-54, Fe-59, Co-58, Co-60, 2n-65. Ho-99, Cs-134, Cs-136, Cs-137, C3-141, Ce-144, and Ba-140.

Other peaks which are measureable and identifiable, together with the listed nuclides, shall also be identified and reported.

Nuclides which are not observed for the analysis shall be reported as "less than" the instrument's LLD, and shall not be reported as being present.

The "less than" values shall not be used in the ODCH evaluations. However, if the nuclide is measured and identified at a value less than the Table 4.21-1 LLD value, it shall be reported and entered into the ODCM evaluations.

d.

Miscellaneous Water Evaporator release is via the gaseous pathway.

Amendment No. 98 4-71b

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.zi.?

,loitui Dose Calculations Cumulative dose contributions and cumulative dose projections a:sociated with the release of liquid RADIOACTIVE EFFLUENTS from the site (see Figure 5.1-3) shall be determined in accordance with the sampling and analyses specified in Tables 4.21-1 and 4.21-2 and the methodology described in the Offsite Dose Calculation Manual (ODCH) at the following frequencies:

a.

Prior to the initiation of a release of liquid RADI0 ACTIVE EFFLUENT and, a dose calculation update shall be made; and, b.

Monthly, based on gamma-emitter and tritium analyses of liquid RADIOACTIVE EFFLUENT releases during the previous calendar month and the results of analyses performed on composite samples shall be added to the monthly dose calculation.

A dose tracking system and administrative dose limits shall be established and maintained. Operating parameters shall be adjusted in accordance with methodology described in the ODCH such that the dose values at any time, when projected to the end of the applicable time period, do not exceed the doses specified in Technical Specification 3.17.2.

BlifUi This specification is r.ovided to implement the requirements of Sections II.A, III. A, and IV. A of Appendix I,10 CFR Part 50.

The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I.

Specification 4.21.2 provides the required operating flexibility and, at the I

same time, implements the guides set forth in Section IV.A of Appendix I which assures, by definition, that the releases of radioactive material in liquid effluents will be kept "as low as reasonably achievable." The dose calculations methodology in the ODCM implements the requirements in Section III.A of Appendix I that conformance with the guides of Appendix 1 be shown by calculational procedures based on models and data such that the actual Amendment No. 53,98 4-72

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards exposure of an individual through appropriate pathways is unlikely to be J

substantially underestimated.

The equations specified in the 00CM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Dose to Man from Routine Releases of Reactor Effluent for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, and Regulatory Guide 1.13, "Estimating Aquatic Msper sion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

The results from composite samples during the period 1981 through 1984 indicates that Cs-137, Cs-134, Co-58 ar Co-60 constitute 80 percent of the historical mix of gamma emitting radionuclides in plant liquid effluents.

Another 13 percent consists of I-131. When the thyroid is separated as a limiting organ, 97.8 percent of the total body dose and 97.6 percent of the limiting organ dose are due to Cs-134 and Cs-137.

Essentially 100 percent of the thyroid dose is due to I-131.

The activity analysis of Cs-134, Cs-137 and I-131 at the Lower Limits of Detection specified in Table 4.21-1 are based on an estimated annual plant radioactivs effluent outflow of 20 million galloa.s per year with a minimum average dilution flowrate of 8,500 gallons per minute.

These Lower Limits of Detection equate to an offsite dose commitment of approximately 50 percent of the guidelines specif.ied in 10CFR50, Appendix I and provide an adequate basis for determining the presence or absence of dose due to other radionuclides in plant liquid effluents, when no other indications are revealed during sample analysis.

The Lower Limits of Detection specified in Table 4.21-2 equate to an offsite dose commitment of approximately 10 percent of the 10CFR50, Appendix I guidelines.

The dose tracking system ensures that the dose limits prescribed in Technical Specification 3.17.2 will not be exceeded at the 95 percent confidence level. The methodology presented in the ODCH provides for adjustment of operational and analysis parameters to factor in variables such as annual radiological liquid effluent release volume, discharge canal flow rate, and current cumulative dose.

The dose tracking system provides for prompt updating of cumulative dose and contains feedback mechanisms to assure that the 10 CFR 50, Appendix I design objectives are not exceeded.

There is also reasonable assurance that the operation of the facility will not result in radionuclide concentrations in finished drinking water that are in excess of the requirement of 40CFR141.

4-723 Amendment No. 53,98

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.21-2 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Sampling Minimum Analysis Type of Activity Lower Limit Liquid Release Frequency frequency Analysis (c)

Of Detection Type (LLD)

(UCi/ml)(a)

A.5atchHasteRe-Each Batch Composite (d)

Principal 4E-9 lease Tanks (b) p.

H Gama Emitting Nuclides (c)

H-3 lE-5 Gross Alpha lE-7 Sr-89, Sr-90 3E-8 Amendment No. 98 4-72b

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.21-2 (Continued)

RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Table Notation a.

(1) The lower limit of detection (LLD) for a radionuclide presented in this table is the smallest concentration, expressed in microcuries per milliliter, which is required to be detected, if present, in order to achieve compliance with the limits Of Specification 3.17.2 (10CFR50, Appendix I).

(2) The LLD of a radioanalysis system is that value which will indicate the presence or absence of radioactivity in a sample when the probability of a false positive and of a false negative cetermination is stated.

The probabilities of false positive and false negative are taken as equal at 0.05.

The equation for LLD in microcuries per milliliter is given by the equation:

LLD - 2.71 + 3.29(Br)0.5 3.70E4(YEVT) where 2.71 - factor to account for Poisson distribution at very low background count rates.

When background is estimated from a blank which has been counted for a specific period, the following applies:

B - estimated background (counts)

-b t,

tb b - blank background (counts) tb - blank count time (seconds) ts - sample count time (seconds) r-1+t 3 tb Amendment No. 98 4 72c

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.21-2 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Table Notation 3.70E4 - disintegrations /second/ microcurie Y - yield of radiochemical process, i.e., the product of all factors such as emission fraction, chemical yield, etc.

E = counting efficiency (count / disintegrations)

V - sample volume (milliliters)

T - fl-exo(-1:s)1exo(-Atcl X

where A = decay constant (seconds -1) tc - time from midpoint of collection to start of counting (3)

When spectroscopy is used to analyze the sample, the following LLD equation is used:

LLD -

2.71 + 4,65(B)0.5 3.70E4 (YEVT)

Where B is the counts in the Region Of Interest.

(4)

The LLD is defined as a priori (before the fact) limit and not as an a posteriori (af ter the fact) limit.

Amendment No. 98 4-72d 4

y r-m u - --

1

- - -------.------i -

a RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.21-2 (Continued)

RADI0 ACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAM b.

A batch release is the discharge of liquid wa>tes of discrete volume from the north or south retention basin.

Prior to sampling the RHUTs, each batch will be isolated, and then thoroughly mixed, to assure representative sampling.

Samples will also be collected from the Retention 3asins and analysed prior to discharge.

c.

The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:

Hn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-136, Cs-137, Ce-141, Ce-144, and Ba-140. Other peaks which are measureable and identifiable, together with the listed nuclides, shall also be identified and reported. Nuclides which are not observed for the analysis shall be reported as "less than" the instrument's LLD, and shall not be reported as being present.

The "less than" values shall not be used in the ODCM evaluations. However, if the nuclide is measured and identified at a value less than the Table 4.21-2 LLD value, it shall be reported and entered into the ODCH evaluations.

d.

A composite sample is one in which the quantity of liquid samples is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

Amenduent No. 98 4-720

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.21.3 Liauid Holduo Tanks

Surveillance Reauirements The quantity of radioactive material contained in each tank listed in Specification 3.17.3 shall be determined to be within the specified limit by analyzing a representative sample of the tank's contents at least weekly when radioactive materials are being added to the tank.

Bases Restricting the quantity of radioactive material contained in the specified outdoor tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the concentration at the nearest pctable water supply and the surface water supply in an unrestricted area would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2.

' Tanks included in this specification are those outdoor 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 or the LIQUID EFFLUENT RADHASTE TREATHENT SYSTEM.

Amendment No. 98 4-73

O e

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.21.4 Liauid Effluent Radwaste Treatmpnl Surveillance Reauirements Doses due to liquid releases to unrestricted areas shall be projected at least once per 31 days in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (0DCH) when LIQUID EFFLUENT RADHASTE TREATMENT SYSTEMS are not being fully utilized.

The installed LIQUID EFFLUENT RADWASTE TREATHENT SYSTEM shall be considered OPERABLE by meeting Specifications 3.17.1 and 3.17.2.

B3 Jill The OPERABILITY of the LIQUID EFFLUENT RADWASTE TREATHENT SYSTEM ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment.

The requirement that the appropriate portions of this system be used when specified provides assurance that the release of radioactive materials in liquid effluents will be kept "as low as is reasonable achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as the dose design objectives set forth in Section II.A of Appendix I,10 CFR Part 50, for liquid effluents.

~

Amendment No. 98

~

L RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.22 GASEOUS EFFLUENTS 4.22.1 Dose Ralft Surveillance Recuirements l

The noble gas effluent continuous monitors, as listed in Table 3.16-1, shall ur.e monitor setpoints to limit the dose rate in unrestricted areas to the limits in Specification 3.18.1.

l In the event a noble gas effluent exceeds the setpoint of its monitor, an 1ssessment of compliance with Specification 3.18.la shall be made in accordance with the methodology described in the ODCH.

The release rate of radioactive materials, other than noble gase:, in gaseous effluents shall be determined by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 4.22-1.

The dose rate due to Iodine-131, Iodine-133, tritium, and all radioactive material in particulate form with half-lives greater than 8 days released in gaseous effluents, shall be determined to be within the limits in Specification 3.18.1 by using the results of the sampling and analysis program specified in Table 4.22-1, and in accordance with the methodology described in the ODCM.

Bases This specification is provided to ensure that the dose rate at any time at the Exclusion Area Boundary (Figure 5.1-1) from gaseous effluents will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas.

The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1.

These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)(1)).

For individuals who may at times be within the Exclusion Area Boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary.

The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the Exclusion Area Boundary to less than or equal to 500 mrem / year to the total body or to less than or equal to 3,000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to any person via the inhalation pathway to less than or equal to 1,500 mrem / year at the Exclusion Area Boundary.

Amendment No. 53,98 4-74

p' s

RANCHO SECO UN8T 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.22-1 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Sampling Minimum Analysis Type of Activity Lower Limit Gaseous Release frequency frequency Analysis of Detection Type (LLD) (a)

(uCi/ml)

A. Haste Gas P

P l

Storage Tank Each Tank Each Tank Principal Gama 1 x 10-4 Grab Emitters (f)

Sample B. Reactor Building P

P Purge Vent Each Purge Each Purge (b,e,1) Principal Gamma 1 x 10-4 Grab Emitters (f)

Sample (b,e,1)

H-3 1 x 10-6 C. Auxiliary M(b,c.e)

M(b)

Principal Gama 1 x 10-4 l

Building Stack Grab Emitters (f)

Sample H-3 1 x 10-6 D. Auxiliary H(b)

M(b)

Principal Gama 1 x 10-4 Building Grade Grab Emitters (f)

Level Vent Sample H-3 1 x 10-6 E. All Release Continuous H(d)

I-131 1 x 10-12 l

Types as listed Charcoal in A,B,C,0 above Sample l

Continuous H(d)

Particulate Principal Gama 1 x 10-11 Sample Emitters (f)

(I-131. Others)

Continuous M

Gross Alpha (h) 1 x 10-11 Composite Particulate Sample Sr-89, Sr-90(g) 1 x 10-11 Continuous Noble Gas Noble Gases 1 x 10-4 Honitor Gross Beta and l

Gama as Xe-133 s

Amendment No. 57,98 4-75

a RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.22-1 (Continued)

RADI0 ACTIVE GASEOUS HASTE SAMPLING AND ANALYSIS PROGRAM Table Notation a.

(1)

The lower limit of detection (LLD) for a radionuclide presentad in this table is the smallest concentration, expressed in microcuries per unit volume, which is required to be detected, if present, in oraer to achieve compliance with the limits of Specifications 3.18.1, 3.18.2 and 3.18.3.

(2) The LLD of a radioanalysis system is that value which will indicate the presence or absence of radioactivity in a sample when the probability of a false positive and of a false negative determination is stated.

The probabilities of false positive and false negative are taken as equal at 0.05.

The equation for LLD in microcuries per cubic centimeter is given by the equation:

LLD - 2.71 + 3.29(Br)0.5 3.70E4(YEVT) where 2.71 - factor to account for Poisson distribution at very low backyround count rates.

When background is estimated from a blank which has been counted for a specific period, the following applies:

B - estimated background (counts) t

-b 3

tb b - blank background (counts) tb - blank count time (seconds) ts - sample count time (seconds) r-1+t 3 tb Amendment No. 53,98 4-76

i RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Tacle 4.22-1 (Continued)

RADI0 ACTIVE GASE0l's WASTE SAMPLING AND ANALYSIS PROGRAM Table Notation 3.70E4 - disintegrations /second/ microcurie Y - yield of radiochemical process, i.e., the product of all factors such as emission fraction, chemical yield, etc.

E - counting efficiency (count / disintegrations)

V - sample volume (cubic centimeters) where A - decay constant (seconds -l) te - time from midpoint of collection to start of counting (3) When spectroscopy is used to analyze the sample, the following LLD equation is used:

LLO -

2.71 + 4.65(B)0.5 3.70E4 (YEVT)

Where B is the counts in the Region Of Interest.

(4) The LLO is defined as an a priori (before the fact) limit and not as an a posteriori (after the fact) limit.

b.

Analysis shall also be performed when gross beta or gamma activity anaylsis of reactor coolant indicates greater than 10 pCi/ml.

The analysis shall be repeated after each additional increase of 10 pCi/ml in the reactor coolant gross beta or gamma activity analysis, c.

Tritium grab samples shall be taken at least once per seven days from the ventilation exhaust from the auxiliary building stack during refueling and anytime fuel is in the spent fuel pool and the pool temperature exceeds 110'F.

Below Il0*F there is essentially no evaporation from this source.

Amendment No. 53,98 4-76a

o RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.22-1 (Continued)

RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Table Notation d.

Samples shall be changed at least weekly and analyses shall be completed l within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Sampling and analysis shall also be performed whea reactor coolant indicates 10pCi/mi gross beta gamma activity and every 10pCi/ml increases thereafter. When samples collected for less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs maybe increased by a factor of 10.

e.

Tritium grab samples shall be taken at least daily during refueling activities.

f.

Principal gamma emitters for which the LLD applies are: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-135m, and Xe-138 for gaseous samples and Hn-54, Fe-59, Co-58, Co-60, Zn-65, Ho-99, (or Tc99m), Cs-134 Cs-137, Ce-141, and Ce-144 for particulate samples.

This list does not mean on!y these nuclides will be detected and reported. Other peaks that are measurable and identifiable shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.2.3.

Nuclides which are below the LLO for the analysis shall be reported as "less than" the nuclide's LLD and shall not be reported as being present at the LLO level for that nuclide. However, if the nuclide is measured and identified at a value less than its predetermined LLD value, it shall be reported and entered into the ODCH evaluations, g.

Gross beta analysis performed on a monthly basis for each environmental release particulate sample.

If any one of these samples indicates greater than 1.0 E-11 pCi/cc gross beta activity then a Sr-89, Sr-90 analysis will be performed on tt.ose samples exceeding this value.

h.

Gross alpha performed on a monthly basis for each environmental release particulate sample. This fulfills the requirements of performing a monthly composite.

i.

After purging seven reactor building volumes, a technical evaluation, prior to reinitiation of a purge following an out of service period, may be conducted in lieu of sampling and analysis.

Amendment No. 53,98 4-76b

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.22.2 Dose-Noble Gases Dose Calculations Cumulative air dose contributions for the calendar quarter and calendar year shall be determined in accordance with the methodology described in the OFFSITE DOSE CALCULATIONAL MAh3AL (ODCM) at least monthly.

E1111 This specification is provided to implement the requirements of Sections II.B. III.A. and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I.

The ACTION statements in Specification 3.18.2 provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents are maintained "as low as reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix !

be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unliKely to be substantially underestimated.

The dose calculations established in the ODCH for calculating the doses due to the actual release rates of radioactive noble gases in gaseous l

effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111. "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1 July 1977.

The ODCM equations provided for determining the air doses at the Site Boundary for Gaseous Effluents (Figure 5.1-3) and are based upon the historical average atmospheric conditions.

Amendment No. 53,98 4-77

O RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.22.3 Dose-Iodine-131. Iodine-133. Tritium. and Radioactive Materials in Particulate Form.

Dose Calculations Cumulative dose contributions for the calendar quarter and calendar year period shall be determined in accordance with the methodology described in the (ODCM) 0FFSITE DOSE CALCULATION MANUAL at least monthly.

Bases This specification is provided to implement the requirements of Sections II.C, III.A, and IV.A of Appendix I, 10 CFR Part 50.

The Limiting Conditions for Operation in Specification 3.18.3 are the guides set forth in Section II.C of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." The ODCH calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such t.iat the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.

The ODCH calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodolog" provided in Regulatory Guide 1.109, "Calculating of Annual Do'es to Han fcom Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111. "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.

These equations also provide for estimating doses based upon the historical l

average atmospheric conditions.

The release rate specifications for radioiodines, and radioactive material in particulate form are dependent on l

the existing radionuclide pathways to man at or beyond the Site Boundary for Gaseoes Effluents (Figure 5.1-3).

The pathways which are examined in the development of these calculations are:

(1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.

Amendment No. 53,98 4-78

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.22.4 Gaseous Radwaste Treatment Surveillance Reauirement Doses due to gaseous releases to areas at and beyond the Site Boundary For Gaseous Effluents (see Figure 5.1-3) shall be projected at least once per 31 days in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (00CH) when Gaseous Radwaste Treatment Systems are not being fully utilized.

The installed VENTILATION EXHAUST TREATHENT SYSTEM and Haste Gas System shall be considered OPERABLE by meeting Specifications 3.18.1, 3.18.2 and 3.18.3.

Bases The operability of the Haste Gas System and the VENTILATION EXHAUST TREATHENT SYSTEMS ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment.

The requirement that the appropriate portions of systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.0 of Appendix I to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the systems were specified as the dose design objectives set forth in Sectiens II.B and II.C of Appendix I, '1 10 CFR Part 50, for gaseous effluents.

Amendment No. 53,98 4-79

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.22.5 G3.5 St? race Tanks Surveillance Reauirements The Quantity of radioactive material contained in each waste gas decay tank shall be determined to be within the limit in Specification 3.18.5 at least l

daily when radioactive materials are being added to the tank and the Reactor Coolant System activity exceeds the limits of Specification 3.1.4.

Bases Restricting the quantity of radioactivity contained in each waste gas decay tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the exclusion area boundary (see figure 5.1-1) will not exceed 500 mrem.

This is consistent with Standard Review Plan 15.7.1, "Haste Gas System Failure."

Calculations have shown that the reactor coolant activity must exceed the limits of Specification 3.1.4 before the waste gas decay tank activity approaches the limits of Specification 3.18.5.

l Amendment No. 53,$7,98 4 80

o RANCHO SECO UNTT I TECHNICAL SPECIFICATIONS Surveillance Standards 4.25 SOLID RADIOACTIVE WASTES Surveillance Recuirements 4.25.1 The solid radwaste systems shall be demonstrated OPERABLE at least once per 92 days by:

a.

Operating the solid radwaste system at least once in the previous 92 days in accordance with the PROCESS CONTROL PROGRAM, or b.

Verification of the existence of a valid contract for SOLIDIFICATION /DERATERING to be performed by a contractor in accordance with an approved PROCESS CONTROL PROGRAM.

4.25.2 The PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION of each new mix by testing of at lease one representative test specimen from at least every tenth batch of each type of wet radioactive waste being solidified (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions).

a.

If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shal1 be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION.

SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION param"ters determined by the PROCESS CONTROL PROGRAM.

b.

If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing Of representative test specimens from each consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.15, to assure SOLIDIFICATION of subsequent batches of waste.

The Process Control Program shall be used to verify the Dewatering of each type of resin and filter media processed to assure established free standing liquid requirements are met.

Haifti The OPERABILITY of the solid radwaste system ensures that the system will be available for use whenever solid radwastes require processing and packaging prior to being shipped offsite.

This specification implements the requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste / liquid / solidification agent / catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.

Amendment No. 53,98 4-81

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards THIS PAGE INTENTIONALLY LEFT BLANK.

4-02 Amendment No. 53,98

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standares 4.26 RADIOLOGICAL ENVIRONMENTAL HONITORING Surveillance Reauirements The radiological environmental monitoring samples shall be collected per Table 3.22-1 from the locations shown in the RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM (REMP) MANUAL and shall be analyzed to the requirements of Tables 3.22-1 and 4.26-1.

Bases The Radiological Environmental Monitoring Program required by this l

specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation.

This monitoring program thereby implementsSection IV.B.2 of Appendix I to 10CFR50 and supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and ODCH modeling of the environmental exposure l

pathways.

Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environtaental Monitoring, Revision 1, November 1979.

The specified monitoring progran, is in effect at the present time.

Program changes may be initiated based on operational experience and changes in regional population or agricultural practices. The sample locations have been listed in the REHP MANUAL to retain flexibility for j making changes as needed.

The detection capabilities required by Table 4.26-1 are state-of-the-art for routine environmental measurements in industrial laboratories.

The LLD's for drinking water meet the requirements of 40 CFR 141.

Amendment No. 33,98 4-83 L

I g

RANCHO SECO UNIT 1 9

T[CHNICAL $P[CIFICATIONS u

Surveillance Standards I

Table 4.26-1 m

MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a. d

's

.O l

Water AirborneParticulgte Fish Milk Food Products Mud and Silt w

j Analysis (pCi/1) w or Gases (pCi/m )

(pCi/kg, wet)

(pCi/1)

(pCi/kg, wet)

(pCi/kg, wet) i e~

l gross beta 4(b)

Ia 10-2 3H 2000 (1000(b))

l l

54Mn 15 130 59Fe 30 260 58Co 15 130 150 l

60Co 15 130 150 l

65Zn 30 260 l

i 95Zr-Nb 15 (e) l 133I 1 (b) 7x 10-2 1

60 i

13dCs 15 (10(b))

1 x 10-2(c) 130 15 60 150 l

I37Cs 18 (10(b))

1 x 10-2(c) 150 18 80 180 140Ba-La 15 (e) 15 (e) r l

k l

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.26-1 (Continued)

MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a, d Table Notation a.

(1)

The lower limit of detection (LLO) for a radionuclide presented in this table is the smallest concentration, expressed in picocuries per unit sample, which is required to be detected, if present, in order to achieve compliance with the applicable regulation, given stated operating conditions and calculation methology.

(2) The LLD of a radioanalysis system is that value which will indicate the presence or absence of radioactivity in a sample when the probability of a false positive and of a false negative determination is stated.

The probabilities of false positiva and false negative are taken as equal at 0.05.

The equation for LLO in picocuries per unit sample is given by the equation:

LLD - 2.71 + 3.29(Br)0.5 3.70E4(YEVT) 2.71 - factor to account for Poisson distribution at very low cackground count rates.

When background is estimated from a blank which has been counted for a specific period, the following applies:

B - estimated background (counts)

-b t,

tb b = blank background (counts) tb - blank count time (seconds) ts - sample count time (seconds) r - 1 + t, tb Amendment No. $3,87,98 4-85

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.26-1 (Continued)

MAXIMUM VALUES FOR THE LOHER LIMITS OF DETECTION (LLD)a, d Table Notation 3.70E4 - disintegrations /second/ microcurie Y - yield of radiochemical process E - counting efficiency (count / disintegrations)

V - sample volume (liters) or mass (kilograms)

T - [1-exo(-Xts)lexo(-Xtcl A

where X - decay constant (seconds -I) tc - time from midpoint of collection to start of counting (3) When spectroscopy is used to analyze the sample, the following LLD equation is useo:

LLD -

2.71 e t,65(B)0.5 3.70E4 (YEVT)

Where B is the counts in the Region Of Interest.

(4) Analyses shall be performed in such a manner that the 3tated LLD's will be achieved under routine conditions. Occasionally, background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLD's unachievable.

In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

(5) The LLD is defined as a a priori (before the fact) limit and not as an a posteriori (after the fact) limit.

Amendment No. 9G 4-85a

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.26-1 (Continued)

HAXIMUM VALUES FOR THE LOHER LIMITS OF DETECTION (LLD)a, d TAhle Notation b.

LLO for drinking water.

c.

LLD shown 13 for composite analysis.

For individual samples, 5x10-2 Ci/m3 is the LLD.

p d.

Other peaks which are measurable and identifiable, together with the nuclides in Table 4.26-1, shall be identified and reported.

e.

Tctal for parent and daughter.

l a

i Amendment No. 53,87,98 4-85b

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.27 LAND USE CENSUS Surveillance Recuirements The land use census shall be conducted annually by using methods that will provide the best results, such as door-to-door survey, aerial survey, or by consulting local agriculture authorities.

The land use census or portions thereof, shall be conducted during the appropriate time of the year to provide the best results.

Reoorts The results of the land use census shall be included in the Annual Radiological Environmental Operating Report.

111111 This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM HANUAL and 00CH are made if required by the results of this census.

This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored, since a garden of this size is the minimum requ red to produce the quantity (26 kg/ year) of leafy vegetable assumed in Regulatory Guide 1.109 for consumption by a child.

To determine this minimum garden size, the following assumptions were used:

(1) that 20 percent of the garden was used for growing broad-leaf vegetation (i.e.,similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/ square meter.

In addition, by gathering information on the liquid effluent pathway and the t

gaseous effluent pathway, the census will assure that proper radiological

)

environmental monitoring and radioactive effluent controls are in place for the adequate protection of the health and safety of the general public.

Amendment No. 53,98 4-86

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Survaillance Standards 4.29 FUEL CYCLE DOSE Surveillance Reauirements Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.21.2, 4.22.2, and 4.22.3 and in accordance with the OFFSITE DOSE CALCULATION MANUAL (00CH).

Cumulative dose contributions from direct radiation (including outside storage tanks, etc.) shall be determined in accordance with the OFFSITE DOSE CALCULATION HANUAL (00CH).

This requirement is applicable only under conditions set forth in the Action Statement of Specification 3.25.

Recorts Special reports shall be submitted as required under Specificatio.13.25.

B3JLt1 This specification is provided to meet the dose limitations of 40 CFR 190 that have been incorporated into 10 CFR 20 by 46 FR 18525.

The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the numerical guides for design objective doses of Appendix I or exceeds the reporting levels for the Radiological Environmental Monitoring Program. For the Rancho Seco site, it is unlikely that the resultant dose to a HEMBER OF ThE PUBLIC will exceed the dose limits of 40 CFR 190 if the plant remains within twice the numerical guides for design objectives of 10 CFR 50, Appendix I and if direct radiation (outside storage tanks, etc.) is kept small. The Special Report will describe a course of action which should result in the limitation of the dose to a HEMBER OF THE PUBLIC for 12 consecutive months to within the 40 CFR 190 limits.

For the purposes of the Special Report, it may be assumed that the dose commitment to the HEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible.

If the dose to any MEMBER OF THE PUBLIC is evaluated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. An l

individual is not considered a HEHBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation which is part of the uranium fuel cycle.

I l

Amendment No. 53,98 4-89 l

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Design Features 5.

DESIGN FEATURES 5.1 1111 The Rancho Seco reactor is located on the 2,480 acres owned by Sacramento Municipal Utility District, 26 miles north-northeast of Stockton and 25 miles southeast of the City of Sacramento, California.

The minimum distance to the boundary of the exclusion area, as defined in 10 CFR 100.3, shall be 2,100 feet.

5.1.1 Exclusion Area The EXCLUSION AREA shall be shown in Figure 5.1-1.

5.1.2 Low Poculation Zone The LOW POPULATION ZONE shall be shown in Figure 5.1-2.

5.1.3 Site Boundarv For Gaseous and Liauid Effluents The SITE BOUNDARY FOR GASEOUS AND LIQUID EFFLUENTS for meeting 10 CFR 50, Appendix I guidelines shall be shown in Figure 5.1-3.

5.1.4 Site Boundary For Liauid Effluents The SITE BOUNDARY FOR LIQUID EFFLUENTS for 10 CFR 20 com;11ance shall be shown in Figure 5.1-4.

5-1 Amendment No. $7,98

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4 Amendment No. 98 5-1d
o RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls,
RESPONS!81LITIES (Continued) 9 All events requiring a Licensee Event Report as defined by 10CFR50.73 and NUREG 1022 to determine adequacy of corrective action and to detect any degrading trend..
h.
Special investigations and reports thereon as requested by the AGM, Nuclear Power Production.
1.
The Plant Security Plan and changes thereto.
j.'
The Emergency Plan and changes thereto.
k.
Review of changes to the PROCESS CONTROL PROGRAM. the 0FFS;TE DOSE CALCULATION MANUAL and the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL.
(See Specifications 6.15 and 6.16.)
1.
Major changes to the Radioactive Waste Treatment Systems (Liquid, Gaseous and Solid), and all information required by Specification 6.17.
Review of any accidental, unplanned, or uncontrolled release of m.
radioactive material to the environs including the preparation and forwarding af reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence, and the forwarding of these reports to the Nuclear Plant Manager and to the HSRC.
AUTHORITY 6.5.1.7 The Plant Review Comittee shall:
a.
Recommend in writing to the AGM, Nuclear Power Production approval or disapproval of items considered under 6.5.1.6(a) through (m) above.
l
'b.
Render determinations in writing with regard to whether or not each ites considered under 6.5.1.6(a) through (e), and (1) above l
constitutes an unreviewed safety question.
c, Provide immediate written notification to the Chairman of the Management Safety Review Comittee of disagreement between the PRC and the AGM, Nuclear Power Production; however, the AGM, Nuclear Power Production shall have responsibility for resolution of such disagreements pursuant to 6.5.1.1 above.
RECORDS 6.5.1.8 Records of the PRC activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each PRC meeting, including appropriate documentation of reviews encompassed by Specification 6.5.1.6e and g, shall be prepared, approved, and forwarded to the AGM, Nuclear Power Production and to the Chairman, Management Safety Review Comittee within fourteen (14) days following each meeting.
Amendment No. H,$7,63,H,98' 6-5
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATICNS Admiriistrative Controls AUDITS 6.5.4 Audits of facility activities shall be perfomed under the cognizance of the Director, Quality. Assurance, Nuclear.
These-audits shall encompass:
a.
The confomance of facility operation to all provisions contained within the Techr.ical Specifications and applicable license conditions at least once per year.
b.
The perfomance, training and qualifications of the District's entire facility technical staff at least once per year.
c.
The result of all actions taken to correct deficiencies occuring in facility equipment, structures, systems or methods of operation that affect nuclear safety at least once per six months for those changes not previously audited.
d.
The performance of all activities required by the Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per two (2) years.
e.
The Facility Emergency Plan and implementing procedures at least once per two (2) years.
f.
The Facility Security Plan and implementing procedures at least once per two (2) years.
g.
Any other area of facility operation considered appropriate by the Chief Executive Officer, Nuclear.
h.
Compliance with fire protection requirements and implementing procedures at least once per two (2) years.
i.
An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection fim.
J.
An inspection and audit of the fire protection and loss prevention program shall be perfomed by an outside qualified fire consultant at intervals no greater than three (3) years.
k.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
1.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months, m.
The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes from liquid systems at least once per 24 months.
n.
The performance of activities required by the Quality Assurance Program for Effluent Control and Environmental Monitoring.
6-10 Amendment No. JS,53,H,98
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The provisions of 10 CFR 50.36 (c) (1) (i) and 10 CFR 50.72 shall be complied with, b.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour.
The Director, Nuclear Operations and Haf ntenance, the AG4, Nuclear Power Production, and the Chairman of the HSRC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
c.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the PRC.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence, d.
The Safety Limit Violation Report shall be submitted to the Commission, the HSRC, and the AG4, Nuclear Power Production, within 14 days of the violation.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures recomended in Appendix "A" of Regulatory Guide 1.33, Novembar 1972.
b.
Refueling operations, c.
Surveillance and test activities of safety related equipment.
d.
Security Plan implementation.
e.
Emergency Plan implementation.
f.
Fire Protection Procedures implementation.
g.
PROCESS CONTROL PROGRAM implementation.
h.
OFFSITE DOSE CALCULATION MANUAL implementation.
i.
RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM MANUAL implementation, j.
Quality Assurance Program for the Effluent Control and Environmental Monitoring using the guidance of Regulatory Guide 4.15, Revision 1, February 1979.
6.8.2 Each procedure of 6.8.1 above and changes thereto shall be reviewed and approved as set forth in Specification 6.5.
Amendment No. 18,H,53,87,#,98 6-11
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.9.2 Radioloaical Reoorts l
6.9.2.1 Annual Radioloaical Reoorts Annual reports covering the activities of the unit, as described below, for the previous calendar year shall be submitted as follows:
6.9.2.1.1 Annual Occucational Radiation Exoosure Reoort The Annual Occupational Radiation Exposure Report shall be submitted to the Commission within the first calendar quarter of each calendar year in compliance with 10CFR20.407.
6.9.2.1.2 Annual Exoosure Recort The Annual Exposure Report shall be submitted to the Commission within the first calendar quarter of each calendar year in accordance with the guidance contained in Regulatory Guide 1.16.
6.9.2.2 Annual Radioloaical Environmental Ooeratina Reoort 6.9.2.2.1 Routine Annual Radiological Environmental Operating Reports l
covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.
l 6.9.2.2.2 The Annual Radiological Environmental Operating Reports shall include summaries and statistical evaluation of the results of the radiological environmental surveillance activities for the recut period, including a comparison with operational controls (as appropriate).
The reports shall also include the results of the Land Use Census required by Specification 3.23.
In the event a radionuclide concentration should be confirmed in excess of the reporting level in Table 3.22-2 by environmental measurements, the report shall describe a planned course of corrective action.
Amendment No. 17,33,98 6-12a
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.9.2.2.2 (Continued)
The Annual Radiological Environmental Operatir.9 Reports shall l
include summarized and tabulated results of al) radiological environmental samples taken during the report period.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data srM1 be submitted as soon as possible in a supplementary report.
1 The reports shall also include the following:
a summary description of the Radiological Environmental Monitoring Program; including a map of all sampling locations keyed to a table giving distances and directions from one reactor, and the results of licensee participation in the Interlab Comparison Program.
The annual report shall also include information related to Specification 4.29, Uranium fuel Cycle Dose.
6.9.2.3 Semiannual Radioactive Effluent Release Keoort Routine Semiannual Radioactive Effluent Release Reports covering the l
operation of the unit during the previous six months of operation shall be submitted within 60 days after January 1 and July 1 of each year.
6.9.2.3.1 The Semiannual Radioactive Effluent Release Reports shall l
include i summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit with data summarized on a quarterly basis.
The Semiannual Radioactive Effluent Release Report shall include a summary of meteorological data collected over the report period.
In lieu of submitting all meteorological data with the after July I report, the information will be retained in a file onsite and shall be submitted to the NRC upon request.
Amendment No. 53,$7,96,98 6-12b
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.9.2.3.1 Continued)
The Semiannual Radioactive Effluent Release Reports shall l
include an assessment of the radiation doses from radioactive gaseous and liquid effluents to individuals due to their activities outside the site boundary (Figures 5.1-3 and 5.1-4) l during the report period.
The Semiannual Radioactive Effluent Release Reports shall l
include the following information for all unplanned releases to unrestricted areas of radioactive materials in gaseous and liquid effluents:
a.
A description of the event and equipment involved.
b.
Cause(s) for the unplanned release.
c.
Actions taken to prevent recurrence, d.
Consequences of the unplanned release.
The radioactive effluent release reports shall include an assessment of radiation doses from the radioactivo liquid and gaseous effluents released from the unit during each calendar quarter. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCH).
The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP), RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM MANUAL and 0FFSITE DOSE CALCULATION MANUAL (00CH) pursuant to Specifications 6.15 and 6.16 as well as any major changes to Liquid, Gaseous or Solid Radwater Treatment Systems pursuant to Specification 6.17.
ihe Semiannual Radioactive Effluent Release Report shall include tacI n for comparison with Specifications 3.17.2, 3.18.2, and 3.16.3 The July-December report shall include c summary table for cc@arison with the annual values in Specifications 3.17.2, 3.18.2, 3 d 3.18.3.
The Semiannual Dadioactive Effluent Release Report shall also include events W.ribed in Specifications 3.17.1, 3.17.3, 3.18.1 and 3.20.
Amendment No. 17,4,53,63.96,98 6-12c
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.9.2.3.1 Continued)
The Semiannual Radioactive Effluent Release Report shall include the following information for each type of solid waste shipped offsite during the report period:
a.
Container volume, b.
Total curie quantity (determined by measurement or estimate),
c.
Principal radionuclides (determined by measurement or estimate),
d.
Type of waste (e.g., spent resin, compacted dry waste evaporator bottoms),
Type of container (e.g., LSA, Type A Type B, High e.
Integrity), and f.
Solidification agent (e.g., cement).
MONTHLY REPORT 6.9.3 Routine reports of operating statistics, including narrative summary of operating and shutdown experience, of lif ts of the Primary System Safety Valves or EHOVs, of major safety related maintenance, and tabulations of facility changes, tests or experiments required pursuant.to 10 CFR 50.59(b), shall be submitted on a monthly basis to the Document Control Branch U.S. Nuclear Regulatory Comission, Washington, D. C.
20555,wIthacopytotheResidentInspectorand Regional Office, postmarked no later than the 15th day of each month following the calendar month covered by the report.
LICENSEE EVENT REPORT 6.9.4 The LICENSEE EVENT REPORTS of Specification 6.9.4.1 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC as Licensee Event Reports. Supplemental reports may be required to fully describe final resolution of occurrence.
In case of corrected or supplemental reports, a License Event Report shall be completed and reference shall be made to the original report date, pursuant to the requirements of 10 CFR 50.73.
Amendment No. 17,M,53,H,96,98 6-12d
t RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls LICENSEE EVENT REPORT 6.9.4.1 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within thirty (30) days of occurrence of the event.
The written report shall include, as a minimum, a completed copy of a licensee event report form, pursuant to 10 CFR 50.73 and the guidance of NUREG-1022.
a.
(i) The completion of any nuclear plant shutdown required by the plant's Technical Specification; or (ii) any operation or condition prohibited by the plant's Technical Specifications; or (iii)
Any deviation from the pl ut's Technical Specifications authorized pursuant to 10 CFR 50.54(x).
b.
Any event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded, or that resulted in the nuclear power plant being:
(i)
In an unanalyzed condition that significantly compromised plant safety; (ii) In a condition that was outside the design basis of the plant; or (iii)
In a condition not covered by the plant's operating and emergency procedures, any natural phenomenon or other external condition that posed an c.
actual threat to the safety of the nuclear power plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the nuclear power plant.
d.
Any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS). However, actuation of an ESF, including the RPS, that resulted from and was part of the preplanned sequence during testing or reactor operation need not be reported, any event or condition that alone could have prevented the e.
fulfillment of the safety function of structures or systems that are needed to:
1.
Shut down the reactor and maintain it in a safe shutdown condition; knendment No. 17,53,63,98 6-12e
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls LICENSEE EVENT REPORT 2,
Remove residual heat; 3.
Control the release of radioactive material; or 4.
Hitigate the consequences of an accident.
f.
Events covered in paragraph 6.9.4.1.e of this section may include one or more procedural errors, equipment failures, and/or discovery of design, analysis, fabrication, construction, and/or procedural inadequacier.
However, individual component failures need not be reported pursuant to this paragraph if redundant equipment in the same system was operable and available to perform the required safety function.
g.
Any event where a single cause or condition caused at least one independent train or channel to become inoperable in multiple systems or two independent trains or channels to become inoperable in a single system designed to:
1.
Shut down the reactor and maintain it in a safe shutdown condition; 2.
Remove residual heat:
3.
Control the release of radioactive material; or 4.
Hitigate the consequences of an accident.
h.
1.
Any airborne radioactivity release that exceeded 2 times the applicable conet.ations of the limits specified in Appendix B, Table.
af 10 CFR 20 in unrestricted areas, when averaged over a time period of one hour.
2.
Any liquid effluent release that exceeded 2 times the limiting combined Maximum Permissible Concentration (MPC)
(see Note 1 of Appendix B to 10 CFR 20) at the point of entry into the receiving water (i.e., unrestricted area) for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one hour.
i.
Any event that posed an actual threat to the safety of the nuclear power plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the nuclear power plant including fires, toxic gas releases, or radioactive releases, j.
Failure of the pressurizer EMOVs or Primary System Safety Valves.
Amendnent No. U,49,53,H.H,98 6-12f
RANCHO SECO UN!T 1 TECHN! CAL SPEC 1FICAT10NS Administrative Controls Soecial Recorts (Continued)
J.
Gaseous and Liquid Radwaste Treatment 30 days (3.18.4 and 3.17.4)
K.
Radiological Environmental Monitoring Program 30 days (3.22)
L.
Deleted l
H.
Solid Radioactive Hastes 30 days (3.21) l N.
Fuel Cycle Oose 30 days (3.25)
,0.
Land Use Census 30 days (3.23) l P.
Steam Generator Tube Inspection 30 days (4.17.5)
Amendment No. jI,98 6-12g
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c.
Records of facility radiation and contamination surveys, d.
Records of radiation exposure for all individuals entering radiation control areas.
e.
Records of gaseous and liquid radioactive mcterial released to the environs.
f.
Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
g.
Records of training and qualification for current members of the plant operating staff, b.
Records of in-service inspections performed pursuant to these Technical Specifications.
i.
Records of Quality Assurance activities required by the QA Hanual.
j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k, Records of meetings of the PRC and the MSRC.
1.
Records for Environmental Qualification which are covered under the provisions of paragraph 6.14.
m.
Records for the Radiological Environmental Monitoring Program, l
n.
Records of the maintenante of all hydraulic snubbers listed in Table 3.12-1.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved maintained and adhered to for all operations involving personnel radiation exposure.
6.12 - Deleted Amendment No. 25 6/dd/ ddd I6/2480.
6-14 Amendment No. 53 77.98
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.15 PROCESS CONTROL PROGRAM (PCP) 6.15.1 Function The PROCESS CONTROL PROGRAM shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured, and that DEWATERING of resin or filter media meets the free standing liquid requirements.
6.15.2 Chanaes A.
The PCP shall be approved by the Commission prior to implementation.
B.
Licensee initiated changes to the PCP shall:
l.
Be submitted to the Commission by inclusion in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was/were made and shall contain:
a.
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; b.
A determination that the change did not reduce the overall conformance of the solidified or dewatered l
waste product to existing criteria for solid wastes; and c.
Documentation of the fact that the change has been reviewed and found acceptable by the Plant Review i
Committee.
4 2.
Become effective upon review and acceptance by the PRC, unless otherwise acted upon by the Commission through written notification to the Licensee.
Amendment No. 53,98 6-17
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.16 0FFSITE DOSE CALCULATION AND RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM MANUALS 6.16.1 Function 6.16.1.1 The OFFSITE DOSE CALCULATION MANUAL (00CH) shall describe the methodology and parameters to be used in the calculation of offsite doses due to the release of radioactive material in gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCO's contained in these Technical Specifications. Methodologies and calculational procedures acceptable to the Commission are contained in various Regulatory Guides as noted in the bases of applicable LCO's.
6.16.1.2 The RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) MANUAL shall be a manual containing the description of the Rancho Seco Radiological Environmental Monitoring Program.
The REMP manual shall contain a description of the environmental samples to be collected, the sample locations, sampling frequer.cies, and sample analysis criteria.
6.16.2 Any changes to the OOCH or REMP HANUAL shall be made as follows:
A.
Licensee-initiated changes:
1.
Shall be submitted to the Commission by inclusion in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was/were made and shall contain:
a.
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information. Information submitted should consist of a package of those pages of the OOCH and the REMP MANUAL to be changed with l
each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);
b.
A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and c.
Documentation of the fact that the change has been reviewed and found acceptable by both the PRC and MSRC.
2.
Shall become effective upon a date specified and agreed to by both the PRC and MSRC following their review and acceptance of the change.
Amendment No. 33,87.98 6-18
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.17 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATHENT SYSTEMS (LIOU10, GASEOUS,-
AND SOLIO) 6.17.1 Function The radioactive waste treatment system (liquid, gaseous, and solid) are those systems described in the facility Final Safety Analysis Report or Hazards Summary Report, and amendments thereto, which are used to maintain that control over radioactive. materials in gaseous and liquid effluents and in solid waste packaged for offsite shipment required to meet the LCOs set forth in these Specifications.
6.17.2 Major changes to the radioactive waste systems (liquid, gaseous, and solid) shall be made by the following method.
For the purpose of this specification, "major changes' is defined in Specification 6.17.3.
Licensee-initiated changes:
1.
The Commission chall be informed of all c0anges by the inclusion of a suitable discussion of each change in the annual USAR update for the period in which the changes were made.
The discussion of each change shall contain:
a.
A summary of the evaluation that led to the determination that the change could bc made (in accordance wi.th 10 CFR 50.59);
b.
Sufficient infonnation to support the reason for the change without benefit of additional or supplemental information; c.
A description of the equipment, components, and processes involved, and the interfaces with other plant systems; d.
An evaluation of the change with regard to the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste if different from chose previously predicted in the license application and amendments thereto; e.
An evaluation of the change with regard to the expected maximum exposures to a HEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population if different from those previously estimated in the license application and amendments thereto; Amendment No. 53,87,#6,98 6-19
e s
March 17, 1988 ATTACHMENT TO LICENSE AMENDMENT NO.
EACILITY OPERATING LICENSE NO. DPR-54 DOCKET NO. 50-312 Replace the following pages of the Appendix "B" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert i
i 20 20 21 21
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS APPENDIX B PEL 1.0 DEFINITIONS 1
2.0 ENVIRONMENTAL PROTECTION CONDITIONS 4
2.1 Deleted 2.2 Deleted 2.3 Deleted 2.4 Deleted 2.5 Deleted 2.6 Deleted 20 l
3.0 NON-RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE PROGRAMS 25 3.1 Erosion 25 3.2 Drif t Contaminants 25 3.3 Deleted 3.4 Noise 26 3.5 Fogging 27 3.6 Deleted 4.0 RADIOLOGICAL ENVIRONMENTAL HONITORING 31 4.1 Deleted 4.2 Deleted 4.3 Deleted 4.4 Deleted 4.5 Deleted 4.6 Deleted 4.7 Deleted 4.8 Deleted 4.9 Deleted 4.10 Deleted 5.0 ADMINISTRATIVE CONTROLS 42 42 5.1 Responsibility 42 5.2 Organization 5.3 Review and Audit 42 5.4 Action to be taken in Event of Violation of an Environmental Protection Limit 43 44 5.5 Procedures 44 5.6 Plant Reporting Requirements 46 5.7 Records Retention 5.8 Deleted i
Amendment No. 45,53,98
O w
THIS PAGE HAS BEEN DELETED Amendment No. 36,33,98 -.
e e
THIS PAGE HAS BEEN DELETED Amendment No. 36,53,98 -

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