Text

Amend 69 to License DPR-72,requiring That Releases of Radioactive Matls to Unrestricted Areas During Normal Operations Be Kept ALARA
	ML20093D006
Person / Time
Site:	Crystal River
Issue date:	06/27/1984
From:	Rivenbark G; Office of Nuclear Reactor Regulation
To:	; City of Alachua, FL, City of Bushnell, FL, City of Gainesville, FL, City of Kissimmee, FL, City of Leesburg, FL, City of New Smyrna Beach, FL, City of New Smyrna Beach, FL, Utilities Commission, City of Ocala, FL, City of Orlando, FL, City of Tallahassee, FL, Florida Power Corp, Orlando Utilities Commission, Sebring Utilities Commission, Seminole Electric Cooperative
Shared Package
ML20093D011	List: ML20093D006; ML20093D013; ML20093D015;
References
	DPR-72-A-069, TAC 08985 NUDOCS 8407160067
	Download: ML20093D006 (117)
	v • d • e

{{#Wiki_filter:) f,\\ UNITED STATES NUCLEAR REGULATORY COMMISSION j,n o,; vvAssincion. o. c. :csss FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINE5VILLE CITY OF KISSIMMEE CITY OF LEE 5 BURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES EDMT53TOlmb CITY OF ORLANDO SEBRING UTILITIES COMMISSION SEMINOLE ELEGIRIC COOPERATIVE, INC. CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. DPR-72 1. The Nuclear Regulatory Comission (the Comission) has found that: A. The application for amendment by Florida Power Corporation, et al (the licensees) dated January 17, 1983, as supplemented or November 1 and December 16, 1983, and March 22, 1984, coaplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in confonnity with t.he application. the provisions of the Act, and the rules and 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 i in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the common 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. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-72 is here'y o l amended to read as follows: M[kD 0 e

' Technical Scecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 69, are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with tne Technical Specifications., 3. This license amendment becomes effective on July 1, 1984. FOR THE NUCLEAR REGULATORY COMMISSION Wek G org . Riven ark, Acting Chief Operating Reactors Branch No. 4 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: June 27, 1984 l l l -,-~-.

0 0 ATTACHMENT TO LICENSE AMENDMENT NO. gg FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 1. Replace the following existing pages of the Appendix "A" Technical Specifications with the enclosed pages and add the enclosed new pages (as indicated). The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness. .Pa19 3/4 3-42 thru.-54 (new) I 3/4 7-48 thru -54 (new) Ia (new) 3/411-1 thru -15 (new) IV 3/412-1 thru -12 (new) IVa(new) 83/4 3-6 (new) VII B3/4 7-7 (new) VIIA (new) S/47-8(new) VIIIa (new) B3/411-1 thru -4 (new) XII B3/412-1 (new) XIIA (new) 5-1 XIIIa (new) 5-3a(new) XIV 6-6 XVI 6-6a(new) 1-6 thru l-8 6-10 thru 6,12a I 1-9(new) 6-14 1-10 (new) 6-14a thru 6-14c (new) 3/4 3-23 6-15 thru 6-17 3/4 3-23a (new) 6-17a(new) 3/4 3-24 6-19 3/4 3-25 6-20 3/4 3-25a (new) 6-21(new) 2. Remove Appendix B, Part I, in its entirety from the Technical Specifications. Ensure that Appendix B, Part II, (Environmental Protection Plan (Non-Radiological)) remains in the Appendix B section of the Technical Specifications. -, - ~ _, _ - s

INDEX DEFINITIONS SECTICM PSCE 1.0 DEFINITIONS DEFINED TERMS 1-1 THERMAL POWER 1-1 RATED THERMAL POWER 1-1 OPERATIONAL MODE I t-1 ACTION 1-1 OPERABLE - OPERABILITY 1-1 REPORTABLE OCCURRENCE l-2 CONTAINMENT INTEGRITY 1-2 ) CHANNEL CALIBRATION 1-2 CHANNEL CHECK 1-2 CHANNEL FUNCTIONAL TEST 1-3 CORE ALTERATION 1-3 q SHUTDOWN MARGIN l-3 IDENTIFIED LEAKAGE l-3 UNIDENTIFIED LEAKAGE l-4 PRESSURE BOUNDARY LEAKAGE l-4 CONTROLLED LEAKAGE l-4 QUADRANT POWER TILT 1-4 DOSE EQUIVALENT I-131 3 1-4 E-AVERAGE DISINTEGRATION ENERGY l-4 STAGGERED TEST BASIS 1-5 FREQUENCY NOTATION 1-5 AXIAL POWER IMBALANCE l-5 REACTOR PROTECTION SYSTEM RESPONSE TIME l-5 ENGINEERED SAFETY FEATURE RESPONSE TIME l-6 PHYSICS TESTS 1-6 SOURCE CHECK 1-6 PROCESS CONTROL PROGRAM (PCP) 1-6 SOLIDIFICATION 1-6 OFFSITE DOSE CALCULATION MANUAL l-6 f 4 CRYSTAL RIVER - UNIT 3 I Amendment No. 2#, 69

INDEX DEFINITIONS set TION FAG _E 1.0 DEFINITIONS (Continued) WASTE GAS SYSTEM 1-6 VENTILATION EXHAUST TREATMENT SYSTEM 17 PURGE-PURGING 17 VENTING 17 INDEPENDENT VERIFICATION 1-7 LIQUID RADWASTE TREATMENT SYSTEM 1-7 MEMBER (S) OF THE PUBLIC 18 SITE BOUNDARY 18 UNRESTRICTED AREA 1-8 j OPERATIONAL MODES (TABLE 1.1) 19 FREQUENCY NOTATION (TABLE 1.2) 1-10 l l l CRYSTAL RIVER - UNIT 3 la Amendment No. 69 l

'l p INDEX l I! sacEw u=Ts me us: : : cr t re:r- ---:.a SECTION PAGE 2.1 SAFETY LIMITS Reactor Core.............................................. 2-1 Reactor Coolant Sys tem Pressure........................... 2-1 2.2 LIMITINGSAFETYSYSTEMSETTINGS' Reactor Protection System Setpoints...................... 2-4 = l 1 BASES SECTION PAGE j 2.1 SAFETY LIMITS i Re a c t o r Co re.............................................. B 2-1 Reactor Coolant System Pressure........................... B 2-3 j 2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor Protection System Setpoints....................... B 2-4 1 CRYSTAL RIVER - UNIT 3 II

LIMITING CONDITIONS FOR OPERATION _AND SURVEILLANCE REOUIREMENTS SEC-'F" r w.nc. 3n.n A c es t < 3 n t i m........................................... 3/4 0-1 3/4.1 REACTIVITY' CONTROL SYSTEMS 3/4.1.1 BORATI0d CONTROL Shutdown Ma rgin - Ope ra ti ng.......................... 3/4 1-1 Shutdown Ma rgi n.. Shutdown.....................~...... 3/4 1-2a Baron Dil ut ion ~.~.'... ',T. s....'...... l....... TI..'.rt.7....; 3/41h3 Modera t:r Tempera ture Coefficient......... '............ 3/4 1-4 ~ Minimum Temperature for Cri ticality.................. 3/4'l-5 i 3/4.1.2 BORATION SYSTEMS Fl ow P a ths - S h ut down................................3/4 1-6 Fl ow Paths - Operati ng............................... 3/41-7 Makeun Pumo - Shutdown....... g..................... 3/4 1 -9 Makeuo Pumos - 0oerating............................. 3/4 1-10 Decay Heat Remova l Pumo - Shutdown................... 3/4 1-11 Bori c Aci d Pumo - Shutdown........................... 3/4 1-12 Bori c Aci d Pumos - Operatin g......................... 3/4 1-13 5 crated Wa ter Sources - Shutdown..................... 3/4 1-14 i Bera ted Wa ter Sources - 0cerating.................... 3/4 1-16 2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Grouc Height - Safety and Regulating Rod Grouns...... 3/4 1-18 Group Height - Axial Power Shacing Rod Groun......... 3/4 1-20 Pos ition Indi cator Channel s.......................... 3/4 1-21 Rod Droo Time........................................ 3/4 1-23 Sa fe ty Rod In s erti on L imi t........................... 3/4 1-24 Regulating Rod Insertion Limits...................... 3/4 1-25 Rod Program.......................................... 3/4 1-33 Axial Power Shacino Rod Insertion Limits.............. 3/a 1-37 9 CRYSTAL RIVER - UNIT 3 III Amendment No. 18, 32, 34 I t ~.... y,. .m.-.-_-_,-_g,.,_c

INDEX LU.tITING CCNDITIONS FOR OPERATION AND SURVEILLANQE R SEC fiON P6GE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL POWER IMBALANCE 3/4 2-1 3/4.2.2 NUCLEAR HEAT FLUX HOT CHANNEL FACTOR - F Q 3/4 2A 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - Fji g 3/4 2-6 3/4.2.4 QUADRANT POWER TILT 3/4 2-8 3/4.2.3 DNB PARAMETERS 3/4 2-12 4 f 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4 3-9 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3 22 Incore Detectors 3/4 L26 Seismic Instrumentation 3/4 3-23 Meteorological Instrumentation i 3/4 3-31 Remote Shutdown Instrumentation 3/4 3 34 Post-accident Instrumentation 3/4 3 37 4 Fire Detection Instrumentation 3/4 k40 i Radioactive Liquid Effluent Monitoring Instrumentation 3/4 k42 Radioactive Caseous Effluent Monitoring Instrumentation 3/4 k47 Waste Gas Decay Tank - Explosive Gas Monitoring Instrumentation 3/4 3 33 CRYSTAL RIVER - UNIT 3 IV Amendment No, JJ, 38,69

INDEX LIMITING CONDITIONS FOR OPERATION AND SUove" ' *MCE REQUIR SECnON PAGai 3/4.4 REACTOR COOLANT SYSTEu 3/4.4.1 REACTOR COOLANT LOOP 5 3/c L1 3/4.4.2 RELIEF VALVES - SHUTDOWN 3/4 4-3 3/4.4.3 RELIEF VALVES - OPERATING. 3/4 4-4 Code Safety Valves 3/4 4-4 Power-Operated Relief Valve 3/4 4-4a I l CRYSTAL RIVER - UNIT 3 Iva Amendment No. 69

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOJJIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE 3/4 7-13 LIMITATION 3/4.7.3 CLOSED CYCLE COOLING WATER SYSTEM Nuclear Services Closed Cycle Cooling System 3/4 7-14 Decay Heat Closed Cycle Cooling Water System 3/4 7-15 3/4.7.4 SEA WATER SYSTEM Nuclear Services Sea Water System 3/4 7-16 l

Decay Heat Sea Water System 3/4 7-17 3/4.7.5 ULTIMATE HEAT SINK i 3/4 7-18 3/4.7.6 FLOOD PROTECTION 3/4 7-19 ] 3/4.7.7 CONTROL ROOM EMERGENCY YENTILATION SYSTEM 3/4 7-20 3/4.7.8 AUXILIARY BUILDING VENTILATION EXHAUST SYSTEM3/4 7-23 3/4.7.9 HYDRAULIC SNUBBERS 3/4 7-25 3/4.7.10 SEALED SOURCE CONTAMINATION 3/4 7-35 3/4.7.11 F1RE SUPPRESSION SYSTEMS Water System 3/4 7-38 Deluge and Sprinkler Systems 3/4 7 41 Halon System 3/4 7-44 Fire Hose Stations 3/4 7-43 3/4.7.12 PENETRATION FIRE BARRIERS 1 3/4 7-47 3/4.7.13 RADIOACTIVE WASTE SYSTEMS Waste Gas Decay Tanks 3/4 7-48 Liquid Radwaste Treatment System 3/4 7-49 Waste Gas System 3/4 7-51 Waste Solidification System 3/4 7 53 Waste Gas Decay Tank - Explosive Gas Mixture 3/4 7 54 CRYSTAL RIVER - UNIT 3 VII Amendment No. 13, 69

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQL7REMENT set. nON PnGE 3/4.3 ELECTRICAL POWER SYSTEMS 3/4.3.1 A.C. SOURCES Operating 3/4 3-1 Shutdown 3/4 8-6 3/4.3.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating 3/4 8-7 A.C. Distribution - Shutdown 3/4 3-9 D.C. Distribution - Operating 3/4 8-10 D.C. Distribution - Shutdown 3/4 8-12 t i . CRYSTAL RIVER - UNIT 3 VIIA Amendment No. 69 m

INDEX i LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION................................. 3/4 9-1 3/4.9.2 I NSTRUMENTATION..................................... 3/49-2 3/4.9.3 DECAY TIME.......................................... 3/4 9-3 3/4.9.4 CONTAINMENT PENETRATIONS............................ 3/4 9-4 3/4.9.5 COMMUNICATIONS....................................... 3/4 9-5 3/4.9.6 FUEL HANDLING BRIDGE OPERABILITY.................... 3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING..... 3/4 9-7 = 3/4.9.8 COOLANT CIRCULATION................................. 3/4 9-8 i 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM...... 3/4 9-9 3/4.9.10 WATER LEVEL - REACTOR VESSEL........................ 3/4 9-10 3/4.9.11 STORAGE P00L........................................ 3/4 9-11 3/4.9.12 STORAGE POOL VENTILATION............................ 3/4 9-12 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS......................... 3/4 10-1 3/4.10.2 PHYSICS TESTS....................................... 3/4 10-2 3/4.10.3 NO FLOW TESTS....................................... 3/4 10-3 3/4.10.4 SHUTDOWN MARGIN..................................... 3/4 10-4 i, CRYSTAL RIVER - UNIT 3 VIII

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEII. LANC SECTION

? AGE 3/h.11 RADIOACTIVE EFFLUENTS Liquid Effluents - Concentration 3/4 11-1 Liquid Effluents - Dose 3/4 11-5 Gaseous Effluents - Dose Rate 3/4 11-7 Dose - Noble Gases 3/4 11-11 Do:e -I-131, Tritium and Radioactive Particulates 3/4 11-12 Total Dose 3/4 11-14 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING Monitoring Program 3/4 12-1 Land Use Census 3/4 12-10 Interlaboratory Comparison Program 1 3/4 12, CRYSTAL RIVER - UNIT 3 Villa Amendment No.69

INDEX BASES SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT................................. B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS................ B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVE......................... B 3/4 6-4 3/4.6.4 COM80STIBLE GAS CONTR0L............................. 8 3/4 6-4 CRYSTAL RIVER - UNIT 3 XI

~ INDEX BASES 5dCTivN PAGE 3/4,7 PLANT SYSTE!.tS 3/4.7.1 TURBINE CYCLE B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION B 3/4 7-3 3/4.7.3 CLOSED CYCLE COOLING WATER SYSTEM B 3/4 7-3 3/4.7.4 SEA WATER SYSTEM B 3/4 7-3 3/4.7.3 ULTIMATE HEAT SINK B 3/4 7-4 3/4.7.6 FLOOD PROTECTION B 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM B 3/4 7-4 j 3/4.7.8 AUXILIARY BUILDING YENTILATION EXHAUST SYSTEM B 3/4 7-3 3/4.7.9 HYDRAULIC SNUBBERS B 3/4 7-3 3/4.7.10 SEALED SOURCE CONTAMINATION B 3/4 7-6 3/4.7.11 FIRE SUPPRESSION SYSTEMS B 3/4 7-6 3/4.7.12 PENETRATION FIRE BARRIERS B 3/4 7-6 3/4.7.13.1 WASTE GAS DECAY TANKS B 3/4 7-7 3/4.7.13.2 LIQUID WASTE TREATMENT B 3/4 7-7 3/4.7.13.3 WASTE GAS SYSTEM B 3/4 7-8 3/4.7.13.4 SOLID RADIOACTIVE WASTE B 3/4 7-8 3/4.7.13.3 EXPLOSIVE GAS MIXTURE B 3/4 7-8 CRYSTAL RIVER - UNIT 3 XII Amendment No. 73, 69

INDEX BASES SECTION PAGE 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.3.1 A. C. SOURCES B 3/4 3-1 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS B 3/4 8-1 1

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION B 3/4 9-1 3/4.9.2 INSTRUMENTATION B 3/4 9-1 3/4.9.3 DECAY TIME B 3/4 9-1 3/4.9.4 CONTAINMENT PENETRATIONS B 3/4 9-1 3/4.9.5 COMMUNICATIONS B 3/4 9-1 i i CRYSTAL RIVER - UNIT 3 XIIA Amendment No. 69 1 1 ~ ' ~ ~ ~ ~ ~ ~

t INDEX - BASES SECTION PAGE 3/4.9.6 FUEL HANDLING BRIDGE OPERAB ILITY................... ~ 3/4.9.7* CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING 3/4.9.8 COOLANT C IRCULATION........................ u.... 3/4.9.9 t CONTAINMENT PURGE Ale EXHAUST ISOLATION SYSTEM.....- B 3/4 9-2 3/4.9.10 WATER LEVEL - REACTOR VESSEL..................... 3/4.9.11 STORAGE P00L....................................... B 3/4 9-2 3/4.9.12 STORAGE POOL YENTILATI0N........................... B 3/4 9-3 4 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 GROUP HEIGHT, INSERTION AIO POWER DISTR IBUTION L IMITS........................ B 3/410-1 3/4.10.2 PHYSICS TESTS...................................... i B 3/4 10-1 3/4.10.3 NO FLOW TESTS.,.................................... B 3/410-1 3/4.10.4 S HUTD OWN MA RGI N................................. B 3/4 10-1 i i CRYSTAL RIVER - UNIT 3 XIII Amendment No. 2ff

~ INDEX BASES SECTTON i:gg l 3/4.11 RADIOACTIVE EMT ITENTt 3/4.11.1.1 LIQUID EFFLUENTS - CONCENTRATION B 3/4 11-1 3/4.11.1.2 LIQUID EFFLUENTS - DOSE B 3/4 11-1 3/4.11.2.1 GASEOUS EFFLUENTS - DOSE RATE B 3/4 11-2 3/4.11.2.2 GASEOUS EFFLUENTS - DOSE, NOBLE GASES B 3/4 11-2 3/4.11.2.3 GASEOUS EFFLUENTS - DOSE, I-131, TRITIUM AND RADIOACTIVE PARTICULATES B 3/4 11.3-3/4.11.3 TOTAL DOSE B 3/4 11 4 3/4.12 RADIOLOGICAL FNVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM B 3/4 12-1 3/4.12.2 LAND USE CENSUS 4 B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM B 3/4 12-1 CRYSTAL RIVER - UNIT 3 XIIIa Amendment No. 69 l

INDEX DESIGN FEATURES SECh0N PAGE 5.1 SITE Exclusion Area 5-1 Low Population Zone 5-1 Map Def*ning Unrestricted Areas for Radioactive Gaseous and Liquid Effluents 51 4

5.2 CONTAINMENT Configuration 51 Design Pressure and Temperature 54 5.3 REACTOR CORE Fuel Assemblies 5-4 Control Rods 5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature 55 Volume 53 5.5 METEORLOGICAL TOWER LOCATION 53 5.6 FUEL STORAGE Criticality 53 Drainage 53 Capacity 5-6 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 36 i CRYSTAL RIVER - UNIT 3 XIV Amendment No. 69 .,.. ~.- .n ,,~ ---.,,.. ~, --

h INCEX ,i h ACHIlilases ae CONTROLS 11 i SECTIOil PAGE 6.1 R ES PO N S I B I L ITY......................................... 6-1 d 6.2 ORGANIZATION 0ffsita....................................... ..;:.:..~ 6-1 Facil i ty Sta ff. ; ; '.. ; ;...... ; ; ;............ I...'......... ' 6-1 -~ 6__. 3 FACILITY STAFF 00A L IFICATIONS..........................., 6-5 6.4 T RA I N I N G................................................ 6-5 i i 6.5 REVIEW AND AUDIT = 6.5.1 PLANT REVIEW COMMITTEE i Function.............................................. 6-5 Composition........................................... 6-5 Alternates............................................ a 6-5 Me e ti n g F r eq uen cy.................................... 1 6-5 Q u o r um............................................... 6-6 j Re s po n s i b i l i ti es......................................6-6 A u t ho r i ty.............................................6-7 Records............................................... 6-7 6.5.2 NUCLEAR GENERAL REVIEW COMMITTEE Function.............................................. 6-7 Composition........................................... 6-8 Qua l i fi c a ti on s........................................ 6-8 Al te rn a te s............................................ 6-8 Consultants........................................... 6-9 rCRYSTAL RIVER - UNIT 3 XV f

~ INDEX ADMTNtSTR ATIVE CONTROLS i ] SECTION PAGE Meeting Frequency 6-9 Quorum 6-9 Review 6-9 Audits 6-10 Authority 6-11 ] i Records 1 6-11 6.6 REPORTABLE OCCURRENCE ACTION 6-11 j 6.7 5AFETY LIMIT VIOLATION 6-12 6.8 PROCEDURE 5 6-12 4 J 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE AND REPOP. TABLE OCCURRENCES 6-13 i ) 5tartup Report 6-13 Annual and Semlannual Reports 6-14 Menthly Operating Report 6-15 Report ble Occurrences 6-15 Promp. Notification with Written Followup 6-13 Thirty Day Written Reports 6-17 6.9.2 SPECIAL REPORTS 6-17a 6.10 RECORD RETENTION 6-18 i 6.11 RADIATION PROTECTION PROC RAM i 6-19 6.12 HIGH RADIATION AREA 4-19 6.13 ENVIRONMENTAL QUALIFICITION 6 20 6.14 PROCE55 CONTROL PROGftAM 6 20 6.15 OFF5ITE DO5E CALCULAT:Q'4 MANUAL 6 21 j 6.16 MAJOR CHANGE 5 TO RADICACTIVE WASTE TREATMENT SYSTEMS 6 21 i i k CRYSTAL RIVER - UNIT 3 XVI Amendment No. 7, 69' .._.._._____.,,._______,;.L_____._._____..-...._-,__._....__.,.___.

.,.o DEFINITIONS per disintegration (in MeV) for isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95f, of the total non-iodine activity in the coolant. i STAGGERED TEST BASIS I 1.21 A STAGGERED TEST BASIS shall consist of:'r 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 at the beginning of each subinterval. FREQUENCY NOTATION 1.22 The FREQUENCY NOTATION specified for 5 perfonnance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2. AXIAL POWER IMBALANCE 1.23 AXIAL POWER IPEALANCE shall be the THERMAL POWER in the top half of the core expressed as a percentage of RATED THERMAL POWER minus the THERMAL POWER in the bottom half of the core expressed as a percentage of RATED THERMAL POWER. REACTOR PROTECTION SYSTEM RESPONSE TIME 1.24 The REACTOR PROTECTION SYSTEM RESPONSE TIE shall be that time interval from when the monitored parameter exceeds its trip setpoint at l the channel sensor until power interruption at the control rod drive breakers. l 5 CRYSTAL RIVER - UNIT 3 1-5

.. =. DEFINITIONS ENGINEERED SAFETY FEATURE RESPONSE TIME 1.25 The ENGINEERED SAFETY FEATURE RESPONSE TIME rhall be that time interval frota when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., rho valven travel to their required positions, pump discharge pressures reach their recuired values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable. PHYSICS TESTS 1.26 PHYSICS TESTS sha.11 be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 13 of the FN.,

2) authorized under the provisions of 10 CFR 50.59, or

3) otherwise approved by the Commission, i

SOURCE CHECK ~ 1.27 A SOURCE CHECK shall be he qualitative assessment of channel response when the char al sensot is exposed to a radioactive source. PROCESS CONTROL PROGRAM (PCP) 1.28 The PROCESS CONTROL PROGRAM is th sampling, tests, analyses, and formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems.is assured. SOLIDIFICATION ~ ~ 1.29 SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground.requirenents. OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.30 The OFFSITE DOSE CALCULATION MANUAL is the document which contains the methocology and parameters used in the calculation of offsite doses due to radicactive gaseous'and liquid effluents and in the calculation of gaseous-and'11guid effluent monitoring alarm / trip setpoints, and in the conduct of the Environmental -Radiological Monitoring Program. WASTE GAS SYSTEM 1.31 A WASTE GAS SYSTEM is an7 equipment (e.g., tanks, vessels, piping) capable of collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. t 1., s N CRYSTAL RIVER

UNI'E3 1-6 Amend $ent No. 69 1

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/ _ ; f f _t .y. ' 0 ' y

1 DEFINITIONS VENT!I.ATION EXHAUST TREA"'"2NT SYSTEM 1.32 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust strema prior to release to the environment (such a system is not considered to have any effect on noble gas effluents). ragineered Safety Feature (ESP) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. PURGE - PURGING i 1.33 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. ) VENTING i 1.34 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, does not imply a VENTING process. INDEPENDENT VERIFICATION 1.35 INDEPENDENT VERIFICATION is a separate act of confirming or cubstantiating that an activity or condition has been completed or implemented, in accordance with specified requirements, by an individual not associated with the original determination that the activity or condition was completed or implemented in cccordance with specified requirements. i I J LIQUID RADWASTE TREATMENT SYSTEM 1.36 The LIQUID RADWASTE TREATMENT SYSTEM shall be 'any available cquipment (e.g., filters, evaporators) capable of reducing the quantity of radioactive material, in liquid effluents, prior to discharge. CRYSTAL RIVER - UNIT 3 1-7 Amendir.ent flo. 69 + ,,,.-,,.--.-.-e,

DEFINITIONS MEMBER (S) OF THE PUBLIC i 1.37 MEMBER (S) OF THE PUBLIC shall include all individuals who i 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 1 plant functions. This category.shall not include non-employees such as vending machine servicemen or postmen who, as part of their normal job function, occasionally enter an area that is contro?. led by the licensee for purposes of protection of individ.als from exposure to radiation and radioactive materials. i SITE BOUNDARY 1.38 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee. l UNRESTRICTED AREA 1.39 An UNRESTRICTED AREA shall le an M rea at or beyond the site boundary, access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the site boundary used for residential quarters or industrial, commercial, institutional, and/or recreational purposes. i l CRYSTAL RIVER - UNIT 3 1-8 Amendment No. 69.

TABLE 1.1 OPERATIONAL MODES REACTIVITY % RATED AVERAGE COOLANT MODE CONDITION, X,ff THERMAL POWER

TEMPERATURE 1.

POWER OPERATION > 0.99 > 51 2 1 80*F 2. STARTUP > 0.99 1% > 280*F 5 3. HOT STAN08Y < 0.99 0 > 280*F 4. HOT SHUTDOWN < Q.99 0 280*F > T,,9 > 200*F 5. COLD SHUTDOWN < 0.99 0 2 1 00*F 6. REFUELING ** < 0.95 0 < 140*F Excluding decay beat. Reactor vessei head unbolted or removed and fuel in the vessel. i e .~ CRYSTAL RIVER - UNIT 3 1 -3 Amendment No. 69

i TABLE 1.2 FRICUENCY NOTATION MOTATION FREQUENCY S At least once per 12 hours. D At least once per 24 hours. W At least once per 7 days. M At least once per 31 days. Q At least once per 92 days. SA At least once per 6 months. R At least once per 18 months. S/U Prict to eich reactor startup. ~ P Completed prior to each release. l ] N.A. Not applicable. l -n CRYSTAL RIVER - UNIT 3 1-10 Amendment No. 69

g d _ TABLE 3.3-6 v g RADIATION MONITORING INSTRUMENTATION 5 MINIMUM g CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT R_,A N G E ACT!ON Ey 1. AREA MONITORS w Fuel Storage Pool area a. 1. Criticallty Monitor i d 15 mr/hr 10-1-10 mr/hr 14 2. PROCESS MONITORS Reactor Building a. u 1. Gaseous Activity-RCS Leakage .y Detection i 1,2,3,4 Not Applicable 0

11. todine Activity-1 6

10 -10 cpm 15 RCS Leakage Detection i 1,2,l,4 Not Applicable 1 10 -106 cpm 15 b. Control Room 1. Iodine Activity-Ventilation g System isolation / g Recirculation i All Modes n 2 x background 103-806 cpm 18 N

With fuel in the storage pool or building U

i 8 l

l l 9t! l TABLE 3.3-6 (cont.) RADIATION MONITORING INSTRUMENTATION i I E ti MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASURENENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTIOl 2. Process Monitors (Continued) O c. Condenser Vacuum Pump D Exhaust Monitor - Gaseous Activity Monitor (RM-A12) I g 1,2,3,4 19 d. Nuclear Services Closed Cooling Water Monitor (RM-L3) 1 All Modes E 19 k e. Decay Heat Closed ,1 Cooling Water Monitors S (RM-L5 and RM-LG) 1 All Modes 5 19 9 4 9

TABLE 3.3-4 (Contined) TABLE NOTATION ACTION 14 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requircment, perform area surveys of the monitored area with portable monitccing instrumentation at least once per 24 hours. ACTION 15-With the number of channels dPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1 l ACTION 13 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, within I hour initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation. ACTI0tt 19 - With the number of channels OPERABLE less than required by the itinimum Channels OPERABLE requirement, plant operation may continuo provided grab samples are collected and analyzed for gross activity

at least once per 24 hours.

m

LLD fgr noble gas principal gama emitters shall be

~ 5x10 Ci/cc. LLD for liquid samples shall be 1x10-6 Cf/ml. l l CRYSTAL RIVER - UNIT 3 3/4 3-24 Amendment tio. 44,69 l l ~'~ ~ ~

i TABLE 4.3-3 l 9 h RADIATION WHITORING INSTRUMENTATION SURVEILLANCE REQUIREMEN CIIANNEL MODES IN WillCil CHANNEL CilANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK

CALIBRATION TEST REQUIRED AREA MONITORS i

w a. Fuel Storage Pool Area i. Criticality Monitor S R M e 2. PROCESS MONITORS 1 a.' Reactor Building { l. Gaseous Activity - Y RCS Leakage 0 Detection S R M

11. lodine Activity -

I,2,3,4 RCS Leakage Detection S R M b. Control Room 1,2,3,4 1. lodine Activity - Ventilation System Isolation / Recirculation S R M All Modes y

With fuel in the storage pool or building l

m f se la

i O I g ? $l TABLE 4.3-3 (cont.) RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CllANNEL MODES IN WH CHANNEL CHANNEL FUNCTIONAL !.klRVEILLAN c INSTRUMENT CHECK CALIBRATION TEST REQUIRED 2 !}

2. Process Monitors (continued) c.

Condenser Vacuum Pump D R M 1, 2, 3, Exhaust Monitor - Gaseous Activity Monitor (RM-A12) is i d. Nuclear Services D R US Closed cooling Water Monitor M all MODES D (RM-L3) e. Decay Heat Closed D R H ,11 MODES Cooling Water Monitors (RM-L5 and RM-L6) F N E e 9 m

' INSTRUMENTATION INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 As a minimum, the incore detectors shall be OPERABLE as specified below. a. For AXIAL

POWER IMBALANCE measursments:

1;; Minedetectorsshallbearrangedsuchthatth[rearethree detectors in each of three strings and there are three detectors lying in the same axial plane with one plane at the core mid-plane and one plane in each axial core half. - 2. The axial planes in each core half shall be,symetrical about the core mid-plane. 3. The detector strings shall not have radial symmetry. 4 b. For QUADRANT POWER TILT sensurements with the Minimum Ir.: ore Detector System: = 1. Two sets of 4 detectors shall lie in each core half. Each set of detectors shall lie in the same axial plane. The two sets in the same core half may lie in the same axial plane. 2. Detectors in the same plane shall have quarter core radial symmetry. For QUADRANT POWER TILT measurements with the Symetric Incore c. Detector System at least 75% of the deta:: tors in each core j quadrant shall be OPERABLE. APPLICABILITY: When the incere detection system is used for surveillance of: a. The AXIAL POWER IMBALANCE, or b. 'The QUADRANT POWER TILT. ACTION: With less than the specified minimum incere detector arrangement OPERAELE, do not use.incore detector measurements to determine AXIAL POWER IMBA or QUADRANT POWER TILT. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. ' CRYSTAL RIVER - UNIT 3 3/4 3-26

i TABLE 3.3-11 FIRE DETECTION INSTRUMENTS MINIMUM DETECTORS OPERABLE DETECTOR LOCATION HEAT / SMOKE 1 Control Complex a. Elevation l08'0" l. Zone 4 (Plant Battery Room 38) NA/1 2. Zone 5 (Plant Battery Room 3A) NA/1 3. Zone 6 (Battery Charger Room 38) NA/1 4 Zone 7 (Battery Charger Room 3A) NA/1 5.. Zone 8 (4160V Switchgear Bus Room 38) NA/1 6. Zone 9. (4160V Switchgear Bus Room 3A) NA/1 7 Zone 10 (Inverter Room 38) NA/1 8. Zone 11 (Inverter Room 3A) NA/1 b. Elevation 120'b" 1. Zone 5 (Control Rod Drive EquipmeiiFRoom) NA/2 2. Zone 7 (480V Switchgear Bus Room 38) NA/1 3. Zone 8 (480V Switchgear Bus Room 3A) NA/1 c. Elevation 134'0" 1. Zone 3A (Cable Spreading Room) NA/5 or 2. Zone 38 (Cable Spreading Room) NA/3 d. Elevation 145'0" 1. Zone 4 (Satellite Instrument Shop and Office)NA/2. 2. Zone 5 (Control Room) I/6 e. Elevation 164'0" 1. Zone 3 (HVAC Equipnent Room) NA/S 2. Zone 4 (HVAC Emergency Equipment 38) NA/1 3. Zone 5 (HVAC Emergency Equipment 3A) NA/1 2 Auxiliary Building a. Elevation 119'0" 1. l Zone 20 (Emergency Diesel Generator 38 1 Controls Room) Zone 21 (Emergency Diesel Generator 3A 1/NA 2. l i Controls Room) 1/NA 3. Zone 27 (Emergency Diesel Generator Room 38) 5/NA , CRYSTAL RIffR 2ONIT $ (Emergency Diesel Generator Room 3A) 5/NA 2 3/4 3 41 Amendment 'No.13 t J

~ INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION l LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of specification 3.11.1.1 are not exceeded. The setpoints shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). APPLICABILITY: As shown on Table 3.3-12'. ACTION: a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required above, without delay suspend. i the release of radioactive liquid effluents monitored by the affected channel, or change the setpoint so that it is acceptably conservative, or declare the channel inoperable. b. With one or more radioactive lfguid effluent monitoring. Instrumentation channels inoperable, take the ACTION shown in Table 3.3-12. Exert best efforts to return ) the inoperable instrument (s) to OPERABLE status within 30 days. If the affacted instrument (s) cannot be returned to OPERABLE status within 30 days, provide information on the reasons for inoperability and lack of timely corrective action in the next Semiannual Radioactive Effluent Release Report. c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. !ll d. The reporting requirements of Specification 6.9.1.9.b are not applicable. i SURVEILLANCE REQUIREMENTS .i 7 l-4.3.3.8 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8. CRYSTAL RIVER - UNIT 3 3/4 3-42 Amendment No. 69

9 d d TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION H MINIMUM g CHANNELS APPLICABLE g INSTRUMENT 8 OPERABLE MODES AC l'IOli w 1. GROSS RADIOACTIVITY MONITORS.PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Auxiliary Building Liquid Radwaste 1

All MODES 21 Effluent Line (RM-L2)

b. Secondary Drain Tank Liquid w

1 Effluent Line (RM-L7) 1 All MODES 22 w 2. FLOM RATE MEASUREMENT DEVICES

a. Auxiliary Building Liquid Radweste Effluent Line 1

All MODES 23

b. Secondary Drain Tank Liquid Effluent Line 1

All MODES 23 i e i = n L

Toble 3.3-12 (Continusd) TABLE NOTATION ACTION 21 With less than the required number of OPERABLE channels, offluent releases via this pathway may continue, provided that prior to initiating a release: At least two independent samples are analyzed in a. accordance with specification 4.11.1.1.1, and b. An INDEPENDENT VERIFICATION of release rate calculations is perf.sraed, and { l c. An INDEPENDENT VERIFICATION of discharge valve lineup is performed. i Otherwise, suspend releases of radioactive materials via this pathway. ACTION 22 With less than the required number of OPERABLE channels, effluent releases via this pathway may continue, provided that grab samples are collected and analyzed for gross radioactiDity at least once per 8 hours, at an LLD of at least 10-i microcuries/al. - l ACTION 23 With less than the required number of OPERABLE channels, effluent releases via this pathway may continue, provided that the flow rate is estimated at least once per 4 hours during actual releases. i i CRYSTAL RIVER - UNIT 3 3/4 3-44 Amendment No. 69 I t (

a. ..-u.---~.. ^ 1 9 M H TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION SURVEILLANCE CHAN11EL g CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT g CHECK CHECK CALIBRATION TEST H u 1. GROSS RADIOACTIVITY MONITORS' PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE N? a. Auxiliary Building Liquid D* P R(1) M Radwaste Effluent Line w 1, (RM-L2) un b. Secondary Drain Tank D* D R(1) M Liquid Effluent Line (RM-L7) f 2. FLOW RATE MEASUREMENT DEVICES a. Auxiliary Building Liquid D(2) N.A. R K.A. Radwaste Effluent Line = b. Secondary Drain Tank Liquid D(2) N.A. R K.A. I Effluent Line a .E

TABLE 4.3 (Continued) 4 TABLE NOTATION

During periods of release.

(1) CHANNEL CALIBRATION shall be performed using: One or more standards traceable to the National a. Bureau of Standards, or i b. Standards obtained from suppliers that. participate in measurement assurance activities with the National Bureau of Standards, or Standards related to previous calibrations c. performed using (a) or (b) above. (2) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. A CHANNEL CHECK shall be performed at least once per day on any day that continuous, periodic or batch releases are made. i

.49 I!

1 s t d CRYSTAL RIVER - UNIT 3 3/4 3-46 Amendnent No. 69 r,

.,-,,,_.m._.

~ INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with the effluent release isolation alarm / trip setpoints { set to ensure that tha limits of Specification 3.11.2.1 are not exceeded. The t satpoints shall ba determined in accordance.with.the OFFSITE DOSE CALCULATION MANUAL (ODCM). APPLICABILITY: As shown in Table 3.3-13 ACTION: h With a radioactive gaseous effluent monitoring instrumentation channel a. alarm / trip setpoint less conservative than required above, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel where appilcable, or change the setpoint so that it is acceptably conservative, or declare the channel inoperable. b. With one or more radioactive gaseous effluent monitoring instrumentation channels inoperable, take the ACTION -abown in Table 3.3-13. Exert best efforts to return the inoperable instrument (s) to OPERABLE status within 30 days. If the affected instruments cannot be returned to OPERABLE status within 30 days, provide information on reasons for inoperability and lack of timely corrective action in the next Effluent and Waste Disposal Semiannual Report. c. The provisions of Specifl:ations 3.0.3 and 3.0.4 are not applicable. d. The reporting requirements of Specification 6.9.1.9.6 are not applicable. SURVEILLANCE REQUIREMENTS I 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be .l. demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and frequencies shown in Table 4.3-9. ,!I 'i

1 CRYSTAL RIVER - UNIT 3 3/4 3-47 Amendment flo.

69

l TABLE 3.3-13 Q d RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION H b MINIMUM i 5 CHANNELS APPLICABLE A OPERABLE MODES ACTION Y 1. Waste Gas Decay Tank Monitor (RM-All) a. Noble Gas Activity Monitor

ti b.

Effluent System Flow Rate Monitor All MODES I i 24 All MODF.S 26 2. Reactor Building Purge Exhaust Duct Monitor (RM-AI) Noble Gas Activity Monitor a.

1. Operating Range n

1

11. Mid Range #

All MODES 1 27 ill. High Range # 1, 2, 3 & 4 1 29 w b. lodine Sampler 1, 2, 3 & 4 29 3 c. 1 Particulate Sampler All MODES ,i i 25 u d. Effluent System Flow Rate Monitor All MODES L e. i 25 Sampler Flow Rate Monitor All MODES i 26 e. All MODijS 26 3. Auxiliary Building and Fuel llandlin Area Exhaust Duct Monitor (RM-A2 l Noble Gas Activity Monitor a.

1. Operating Range'

11. Mid Range #

l All MODES 23 1 ill. High Range # 1, 2, 3 & 4 29 b. lodine Sampler 1 1, 2, 3 & 4 29 i Particulate Sampler All MODES c. i 25 d. Eliluent System Flow Rate Monitor All MODES { Sampler Flow Rate Monitor i 25 e. All MODES a i 26 All MODES P. 26 a E

Provides control room alarm and automatic termination of release.

There is no isolation seapoint. or release termination function for this mor.itor; Alarm setpoints approprlate system procedures.

are determined by the l

i ~, TABLE 3.3-13 (Continued) ' TABLE NOTATION 1 ACTION 24 With less than the required number of OPERABLE channels Waste Gas Decay Tank may be released to the environment, prov e to initiating a release 1. (RM-A2)is OPERABLE with its setpoints set to Specification 3.11.2.1 are not exceededi The setpoint shall be determ in accordance with the OFFSITE DOSE CALCULATION MANUAL, 2.

a. At least two independent samples of the tanWs contents are analyz accordance with Table 4.11-2 and

b. An INDEPENDENT VERIFICATION of release rate ca Performed, and

c. An INDEPENDENT YERIFICATION of discharge valve lineup is performed.

l Otherwise, suspend releases of radioactivTeffluents via this pathway. A I ACTION 23 With the number of OPERABLE channels less than required eff collected with auxiliary sampling equipment as req { ( e eases i l ACTION 26 With the number of OPERABLE channels less than required effl via this pathway may continue, provided flow rate is estimated at least releases 1 per 4 hours. 1 4 ACTION 27 With the riumber of OPERABLE channels less than required suspend PURGING of radioactive effluents via this pathway. , immediately i CRYSTAL RIVER - UNIT 3 3/4 3-49 Amendment fle. 69

TABLE 3.3-13 (Continued) TABLE NOTATIO.N ACTION 23 With the numoer of OPERABLE channels less than required, releases via this pathway may continue, provided grab samples are collected at least once per 12 hours and analyzed within 24 hours, and either the requirements of ACTION 24 Part 2 are met or Radiation Monitor RM-All is OPERABLE prior to releasing the contents of the Waste Gas Decay Tanks. ACTION 29 With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter (s), within 72 hours, and: 1) Either restore the inoperabie Channei(s) to OPERABLE status within 7 days of the event, or 2) Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 14 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status. 4 NOTE:, Actjon, Statement 3.3.3.9.a knot applicable '!'i l 11 i l' CRYSTAL RIVER - UNIT 3 3/4 3-50 Amendment No. 69

TABLE 4.3-9 k RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRilMENTATION SURVEILLANCE REOUIREMENTS Mji: CHANNEL MODES IN WHICil CHANNEL SOURCE Cl]ANNEL FUNCTIONAL SURVEILLANCE y INSTRUMENT CHECK CHECK CALIBRATION TEST REOUIRED Y l. WASTE GAS DECAY TANK MONITOR (RM-All) H

a. Noble Gas Activity P

P R(1) M All MODES w Monitor

b. Effluent System Flow P

N.A. R M All MODES Rate Monitor 2. REACTOR BUILDING PURGE EXHAUST DUCT MONITOR (RM-AI)

a. Noble Gas Activity Monitor 1.

Operatin~g Range D# P R(1) M 1, 2, 3, 4 R

11. Mid Range W

M R(1) M 1, 2, 3, 4 lit. High Range W M R(1) M 1, 2, 3, 4 y

b. lodine Sampler W#

N.A. N.A. N.A. All MODES

c. Particulate Sampler W#

N.A. N.A. N.A. All MODES

d. Effluent System Flow D#

N.A. R M All MODES Rate Monitor l

e. Sampler Flow Rate D#

N.A. R M All MODES Monitor 3. AUXILIARY BUILDING & FUEL HANDLING AREA EXHAUST DUCT i MONITOR (RM-A2) f

a. Noble Gas Activity a

Monitor ( i. Operating Range D# P R(1) M All MODES 11., Mid Range W M R(l) M 1, 2, 3, 4 a" lii. High Range W M R(1) M 1, 2, 3, 4 i f

b. lodine Sampler W

N.A. N.A. N.A. All MODES ' (

c. Particulate Sampler W

N.A. N.A. N.A. All MODES

d. Effluent System Flow D

N.A. R M All MODES e Rate Monitor

e. Sam ler Flow Rate D

N.A. R M All MODES M tor

TABLE 4.3-9 (Continued) TABLE NuTAT:ON

During periods of Reactor Building Purge.

(1) CHANNEL CALIBRATION shall be performed using: One or more standards traceable to the National Bureau of Standards, or a. b. Standards obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards, or Standards related to previous callbrations using (a) or (b) above. c. l l l 1^j l i!, CRYSTAL RIVER - UNIT 3 3/4 3-52 Amendment ?!o. 69

i i l l INSTRUMENTATION WASTE GAS DECAY TANK - EXPLCSIVE GAS MONITORING INSTRITrir.'.NTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The Waste Gas Decay Tanks shall have one hydrogen and one oxygen monitoring channel OPERABLE. APPLICABILITY: All MODES. ACTION: With the number of OPERABLE channels less than required above, operation of this system may continue for up to 14 days, provided grab samples are collected and analyzed (a) at least once per 4 hours during degassing operations l (b) at least once per 24 hours during other operations. i SURVEILLANCE REQUIREMENTS E i 4.3.3.10 The Waste Gas Decay Tank explosive gas monitoring instrumentation shall be demonstrated cperable by performing the i CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBPATION at the frequencies shown in Table 4.3-10. >I .J ,4 i l l CRYSTAL RIW.R-UNIT 3 3/4 3-53 Amendment No. 69 i i

O da TABLE 4.3-10 N 6 WASTE GAS SYSTEM EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l 4 u

CHANNEL CHANNEL CHANNEL FUNCTIONAL

, INSTRUMENT CHECK CALIBRATION TEST w %g 1. Hydrogen Monitors ' D y Q* M i ve* 2. Oxygen Monitors D Q* H f i '* The CHANNEL CALIBRATION shall include the use of standard gas samples containisg a noninal k Hydrogen Monitors a 1 volume percent hydrogen, balance nitrogen. = a. P b. 4 volume percent hydrogen, balance nitrogen. E Oxygen Monitors 1 volume percent oxygen, balance nitrogen. c. d. 4 volume percent oxygen, balance nitrogen. V

PLANT SYSTE$tS 3/4 7.12 FIRE BARRIER PENETRATIONS LIMITING CONDITION FCR CPERATICN 3.7.12 All fire barrier penetrations (including cable penetration barriers, firedoors and fire dampers) in fire zone boundaries protecting safety related areas shall be functional. APPLICABILITY: At all times. ACTION: 2. With one or more of the above required fire barrier penetrations non-functional, within one hour either, establish a continuous fire watch on at least one side of the affected penetration, or verify the OPERABILITY of fire detectors on at least one side of the non-functional fire barrier and establish an hourly fire watch iiatrol. I ~ b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVFTT LANCE REQUIREMENTS 4.7.12 Each of the above required fire barrier penetrations shall be verified to be functional e At least once per 18 months by a visual inspection. a. b. Prior to returning a fire barrier penetration to functional status following repairs or maintenance by performance of a visual inspection of the affected fire barrier penetration (s). I gj. CRYSTAL RIVER UNIT 3 3/4 7-47 Amendment No. U, G5 t I 8

i PLANT SYSTEMS 3/ 4. 7'.13 ' RADIOACTIVE WASTE SYSTEMS WASTE GAS DECAY TAlg LIMITING CONDITION FOR OPERATION 3.7.13.1 The quantity of radioactivity contained in each Waste Gas Decay Tank shall be limitad to less than or equal to 39000 curies (considered as Xe 133).. l

t APPLICABILITY:

At all times. ~ ACTIOM a. With the quantity of radioactivity in any waste Gas Decay Tank exceeding the above limit, immediately suspend all additions of radioactive material to that tank, and within 48 hours reduce j the tank contents to within its limit. b. The provisions of Spec 1 Mcations 3.0.3 and 3.0.4 i are not applicable. SURVEILIJLNCE PEQUIREMENTS 4.7.13.1 The quantity of radioactive waterial contained in each Waste Gas Decay Tank shall be determined to be within the limit at least once per 7 days whenever radioactive materials are being added to the tank, and at least once per 24 hours during primary coolant system degassing operations, f i Li ~ i i i l CRYSTAL RIVER - UNIT 3 3/4 7-48 Amendment No. 69 i . a

5 PLANT SYSTEMS LIQUID RADWASTE TREATMENT SYSTEM LINITING CONDITION FOR OPERATION 3.7.13.2 The LIQUID RADWASTE TREATMENT SYSTEM shall be used, as required, to reduce radioactive materials in liquid wastes prior to their discharge, when projected monthly doses due to liquid effluents discharged to UNRESTRICTED AREAS (see Figure 5.1-3) would exceed the following values: a. 0.06 area who~e body; b. 0.2 ares to any organ. APPLICADILITY: At all times. l ACTION: a. When radioactive liquid waste, in excess of the above limits, is discharged without prior treatment, prepare and submit to the Commission within 30 days, a Special Report pursuant to Specification 6.9.2, which includes the following information:

1. Identification of inoperable equipment and the reasons for inoperability.

2. Acti'ns taken to restore the inoperable o

equipment to OPERABLE status.

j: 3. Actions taken to prevent recurrence.

2 [i b. The provisions of Specifications 3.0.3 and 3.0.4 l t are not applicable, j c. The reporting requirements of Specification 6.9.1.9.b are not applicable. 1 ,~ CRYSTAL RIVER - UNIT 3 3/4 7-49 Amendment Nd. 69 ~

PLANT SYSTEMS LIQUID RADWASTE TREATMENT SYSTEM (Continued) SURVEILLANCE REQUIREMENTS 4.7.13.2 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). m e I ( h { \\ i s q a ~. .+ 1 i i i ) ? g CRYSTAL RIVER UNIT 3 3/4 7-50 Amendment No. 69 e 7 ')-

j ~ PLANT $YSTEMS j i WASTE GAS SYSTEM i LIMITING CONDITION FOR OPERATION 3.7.13.3 The WASTE GAS SYSTEM shall be used, as required, to reduce the radioactivity of materials in gaseous waste prior to discharge, when projected monthly air doses due to releases of gaseous effluents from the site to areas at or beyond the' SITE BOUNDARY (see Figure 5.1-3) would exceed: 1) 0.2 mrad gamma; 2) 0.4 mrad beta; and The VENTILATION EXHAUST TREATMENT SYSTEM shall be used, as required, to reduce the quantity of radioactive materials in gaseous waste prior to discharge, when projected monthly air doses due to release of gaseous effluents from the site to areas at or beyond the SITE BOUNDARY would exceed: 1) 0.3 area to any organ. APPLICABILITY: At all times. ACTION: a. When the WASTE GAS SYSTEM and/or VENTILATION EXEAUST TREATMENT SYSTEM are not used and gaseous waste in excess of the above limits is discharged without prior treatment, prepare and submit to the .~ commission, within 30 days a special Report,- pursuant to Specification 6.9.2, which includes:

1) Identification of the inoperable equipment and

>'j the reason (s) for inoperability. !}

2) Actions taken to restore the inoperable

-( equipment to OPERABLE status. j

3) Actions taken.to prevent recurrence.

l* b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. c. The reporting requirements of Specification 6.9.1.9.b are not applicable. CRYSTAL RIVER - UNIT 3 3/4 7-51 Amendment No. 69

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.13.3 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). 6 - I N l - - ~ ~ _ i i' CRYSTAL RIVER - UNIT 3 3/4 7-52

PLANT SYSTEMS l WASTE SOLIDIFICATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.13.4 The solid radwaste system shall be used in accordance with a PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet shipping and burial ground requirements. APPLICABILITY: At all times. ~ ACTION: With the provisions of the PROCESS CONTROL PROGRAM not a. satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site. b. The provisions of Specifications 3.0.3 and 3.0.4 are i not applicable. c. The reporting requirements of Specification 6.9.1.9.b are not applicable. SURVEILLANCE REQUIRENENTS 4.7.13.4 The PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (e.g., filter sludges, spent resins, evaporator bottoms, and boric acid solutions). 1 CRYSTAL RIVER - UNIT 3 3/4 7-53 Amendment No. 69 ._,,,_--.,-e,-..- N

.m+ B =vA PLANT SYSTEMS ) WASTE GAS DECAY TANK - EXPLOSIVT GAS MIXTUTdi; LIMITING CONDITION FOR OPERATION 3.7.13.5 The concentration of oxygen in any Waste Gas Decay Tank shall be limited to less than or equal to 24 by volume whenever the concentration of hydrogen in that Waste Gas Decay Tank is greater than or equal to 44 by volume. APPLICABILITY: At all times. ACTION: Whenever the concentration of hydrogen in any Waste Gas Decay Tank is greater than or equal to 44 by volume, and The concentration of oxygen in that Waste Gas Decay a. Tank is greater than 24 by volume, but less than 44 by volume, without delay begin to reduce the oxygen concentration to within its Timit. b. The concentration of oxygen in that Waste Gas Decay Tank is greater than or equal to 44 by volume, imwediately suspend additions of waste gas to that Waste Gas Decay Tank and without delay begin to reduce the oxygen concentration to within its limit. c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.7.13.5 The concentrations of hydrogen and oxygen in ths Waste ~ Gas Decay Tank shall be continuously monitored with the hydrogen and oxygen monitors required OPERABLE by Specification 3.3.3.10 or by sampling in accordance with Specification 3.3.3.10 if the hydrogen and/or oxygen monitors are inoperable. CRYSTAL RIVER - UNIT 3 3/4 7-54 Amendment No. 69

'.~ .~ 3/4.11-RADIOACTIVE EFFLUENTS. 3/4.11.1 LIQUID EFFLUENTS l l l COMCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released to UNRESTRICTED AREAS (see Figure 5.1-3) shall be less than or equal 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 less than or equal to 2x10-4 microcuries/ml. total activity. APPLICABILITY: At all times. ACTION: a. With the concentration of radioactive materials released to UNRESTRICTED AREAS exceeding the above. v,_^ limits, without delay restore the concentration of 6 radioactive materials being released to UNRESTRIC'TED ~ AREAS to within the above limits. If the concentration of radioactive materials being released in excess of the above limite-is related to a plant operating characteristic, appropriate corrective measures (e.g., power reduction, plant shutdown) shall be taken to restore the concentration of radioactive materials being released to UNRESTRICTED AREAS to within the above limits. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. c. The reporting requirements of Specification 6.9.1.9.b are not applicable. y 1] SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed in accordance with the sampling and analysis program of Table 4.11-1. 4.11.1.1.2 The results of the radioactivity analyses shall be i used in accordance with the methods in the OFFSITE DOSE CALCULATION MANUAL (ODCM) to assure the concentrations of radioactive material released from the site are maintained within the limits of Specification 3.11.1.1. CRYSTAL RIVER - UNIT 3 3/4 11-1 Amendment No. 69 i

T A h t; 4 11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit of l l Minimum Detection l Liquid Release Sampling Analysis Type of Activity (LLD) I Type Frequency Frequency Analysis (11Ci/ml) " A. Batch Waste P P l Releage Each Batch Each Batch PrincipagGamma 5x10-7 Tanks Emitters i l

1. Evaporator Condensate I-131 lx10-6 Storage I

-5 P M Dissolved and 1x10

2. Laundry &

One Batch /M Entrained Gases Shower Sump (Gamma Emitters) Tanks (2) -5 P M H-3 1x10 b Each Batch Composite ~7 Gross Alpha lx10 P Q Sr-89, Sr-90 5x10-8 h Each Batch Composite ~0 Fe-55 1x10 B. Continuogs W -7 Principa 5x10 Emitters} Gamma C Releases Continuous Composite *

1. Secondary Drain Tank I-131 1x10-0

-5 M M Dissolved and 1x10 Grab Sample Entrained Gases i (Gamma Emitters) M H-3 lx10-5 Continuous" Composite C -7 Gross Alpha lx10 -8 Q Sr-89, Sr-90 Continuous Composite 5x10 e c -6 Fe-55 lx10 CRYSTAL RIVER - UNIT 3 3/4 11-2 Amendment No. 69 I e~.--m, -.,,--_,,.--,,----,--,n-y ,,,--...,,.,..,en-- _.,----,.,,,.--,-.,..,w

TABLE 4.11-1 (Continued) TABLE NOTATION l l a. The LLD* is the smallest concentration of radioactive i material in a sample that will be detected with 95% l probability with 54 probability of falsely concluding that a blank observation represwnts a "real" signal. For a particular measurement system (which may include radiochemical separation): 4.66sb (E) (V) (2.22x10') (Y) (a -^^3 Where LLD is the lower limit of detection as defined above (as microcurie per unit mass or volume), sb is the standard deviation of the background counting ratie or of the counting. rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per disintegration), V is the sample size (in units of mass or volume), 6 2.22x10 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable), A is the radioactive decay constant for the particular radionuclide, and j at is the elapsed time between midpoint of sample collection and time of counting (for plant offluents, not environmental l samples). li Typical values of E, V, Y, and at shall be used in the calculation. 1

The LLD 12 defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a_ posteriori (after the fact) limit for a particular measurement.

CRYSTAL RIVER - UNIT 3 3/4 11-3 Amendment No. 69

l TABLE 4.11'-1 (Continued) TABLE NOTATION, l l b. A composite sample is one in whien the quantity of liquid sampled 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. i I c. To be representative of the quantities and concentrations of i radioactive materials in liquid effluents, samples shall be I collected continuously in proportion to the rate of flow of the affluent stream. Prior to analyses, all samples,_taken~ for the composite shall be thoroughly mixed in order for the _. composite sample to be representative of the affluent release. d. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling. e. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume or system that has an input flow during the continuo e release. f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, I and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are i measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the'LLD for the analyses shall be reported as "less than" the nuclide's LLD, and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations. I ii 9 CRYSTAL RIVER - UNIT 3 3/4 11-4 Amendment No.69

RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS - DOSE l l LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited as follows: l a. During any calendar quarter to less than or equal to l.5 area to the total body and less than or equal to 5 area to any organ. n-b. During any calendar year to less than or equal to 3 aren to the total body and to less than or equal to 10 area to any organ. ^ APPLICABILITIY: At all times. ACTION: n. With the calculated dose 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 6.9.2, which includes: 1. Identification of the cause for exceeding the limit (s); 2. Corrective action taken to reduce the release of radioactive materials in liquid effluents J during the remainder of the current calendar j{ quarter and during the remainder of the current calendar year so that the dose or dose commitment to a MEMBER OF THE PUBLIC from this source is less than or equal to 3 area total body and less than or equal to 10 area to any organ during the calendar year. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable, c. The reporting requirements of Specification 6.9.1.9.b are not applicable. CRYSTAL RIVER - UNIT 3 3/4 11-5 Amendsent No. 69 -,c y g,. .-,-..e,,- y ,-,-.w -,,--,--.-----,,i,,,,-,,,,,y%.,---.-,-,,,,..-,,,-,-,.mm-- m.

l RADIOACTIVE EFFLUSTTS l SURVEILLANCE PROUTREMMfTS I 4.11.1.2 DOSE CALCULATIONS. Cumulative dose contributions from liquid effluents shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) at least once per 31 days. ~ i i CRYSTAL RIVER - UNIT 3 3/4 11-6 Amendment No. 69

RADIOACTIVE EFFLUENTS ~ 3/4.11.2 GASEOUS EF?LUT'T*"" - CO"O ?AE l LIMITING CONDI? TOM IPOR O*1Pon? TOM I 3.11.2.1 The dose rate at or beyond the SITE BOUNDARY, due to j radioactive materials released in gaseous effluents (sce Figure 5.1-3), shall be limited as follows: a. Noble gases: less than or equal to 500 ares / year total body and less than or equal to 3000 aren/ year to the skin. b. Iodine-131, Tritium, and radicactive particulates with half-lives of greater than 8 days: less than or equal to 1500 aren/ year to any organ. APPLICABILITY: At all times ACTION: a. With dose rate (s) exceeding the above limits, without delay decrease the dose rate to within the above l limits (s). If the dose rate at or beyond the SITE l BOUNDARY due to radioactive terials in gaseous effluents in excess of the ve limits is related to a plant operating characteristic, appropriate ~ corrective measures (e.g., power reduction, plant shutdown) shall be taken to decrease the dose rate to within the above limits, b. The provisions of specifications 3.0.3 and 3.0.4 are not applicable, The reporti'ng requirements of specification 6.9.1.9.b c. are not applicable. jj SURVEILLANCE REQUIREMENTS i!l, 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of the OFFSITE DOSE CALCULATION MANUAL (ODCN). 4.11.2.1.2 The dose rate due to radioactive materials specified above, other than noble gases, in gaseous effluents shall be determined to be within the above limits in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) by obtaining representative samples and performing analyses in accordance with Table 4.11-2. i CRYSTAL RIVER - UNIT 3 3/4 11-7 Amendment No. 69

m---,

,,,,,,.,.n-,. -.,.n.--,-,_.,,,.-,-n,,,,,,_~.- _..,.,--,--_,,.r,.-n-, _ n, n-

k TT"LE 4.11-2 O RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM i a. E Minimum Lower Limit of y Sampling Analysis T pe of DetectionfLLD) H Gaseous Release Type Frequency Frequency Activ ty Analysis (aC1/ml) l h ~4' A. Wasta Gas Decay Bach Tank Each Tank Principal Gamma Emitters lx10 j Tank Grab j y Sample 2 3 P P l B. Reactor Building Bach Purge Bach Purge Principal Gamma Emitters 'I lul0 l ~4 i Purge Exhaust Grab ~D Duct Monitor Sample H-3 1x!0 w (aM-A1) s '~ i C. Auxiliary Building M* M Principal Gamma Emittera,f 3xt0 ' I b ~ O and Fuel Handling Grab j ___D i Area Exh'aust Duct Sample B-3 lxi i Monitor (RM-A2) d D. All Release Types Continuous

M t

-12 as Listed in A, B, Charcoal I-131 1x10 l C above Sample l Continuoes' W" Principal Gamma Emitters' ~Al 1x10 Particulate (I-131, Others) Sample k Continuous

M Gross Alpha lx10~11

= I Composite Particulate k Sample Continuous

Q Sr-89, Sr-90 luio-11 Composite g

Particulate l Sample Continuous

Noble Gas Noble Gases lxID Monitor Gross Beta & Gamma s

TABLE 4.11'-2 (Continued) ) TABLE ?!CTATIC?! l i a. The LLD* is the smallest concentration of radioactive material in a sample that will be detected with 954 probability with 54 probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation): 4.66s b LLD = (E) (V) (2.22x10') (Y)' ( e~ ^ ^ t ). Where: , n;;+& - LLD is the lower limit of detection as defined above (as microcurie per unit mass or volume), sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as i counts per minute), E is the counting efficiency (as counts per disintegration), V is the sample size (in units of mass or volume), I 0 2.22x10 is the number of disintegrations per minute per microcurie, i Y is the fractional radiochemical yield (when applicable), A is the radioactive decay constant for the particular radionuclide, and i At is the elapsed time between midpoint of sample li collection and time of counting (for plant effluents, not j environmental samples). i Typical values of E, V, Y, and At shall be used in the + calculation. l4 i

The LLD is defined as an a priori (before the fact) limit l

representing the capability of a measurement system and not as an l a,nesteriori (after the fact) limit for a particular measurement. l CRYSTAL RIVER - UNIT 3 3/4 11-9 Amendment No. 69

TABLE 4.11-2'(Continued) TABLE Mo*A"'ICM I b. Analyses shall also be performed between 2 and 6 hours following shutdown, startup or a change in power level exceeding 15% RATED THERMAL POWER within one hour. c. Tritium grab samples shall be taken between 12 and 24 hours after flooding the refueling canal and at least once per 7 days thereafter while the refueling canal is flooded. d. Samples shall be changed a't least once per 7 days and i analyses shall be completed within 48 hours after changing (or after removal from sampler). Sampling and analyses shall,be performed at least once per 24 hours for at least 7 days following each shutdown, startup or change in power level exceeding 15% of RATED THERMAL POWER within one hour, l unless the Iodine Monitoring Channels in Radiation Monitors RM-Al and RM-A2 show that the Radiciodine concentration in 1 the Auxiliary Building and Fuel Bandling Area or the Reactor i Building Purge Exhaust Ducts will lead to a release which is less than 10% of the 10 CFR 20, Appendix B, Table II, Column I limits, at or beyond the SITE BQUNDARY. 4 ~ o. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with the specifications 3.11.2.1, 3.11.2.2 and 3.1.2.3. f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-i l 134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD and shall not be reported as being present t at the LLD level for that nuclide. The "less than" values: l shall not be used in the required dose calculations. i CRYSTAL RIVER - UNIT 3 3/4 11-10 Amendment No. 69

~ P.'.D I O.'.C"!"" ""'".Urt"'c .. _. ~ g i - -. =. _ = 3.11.2.2 The air done at or beyond the SITE BGUNDARY (see Figure 5.1-3), due to radioactive noble gases released in gaseous effluents shall be limited to a. During any calendar quarter: less than or equal to 5 nrad g-- a and lass than or equal to 10 mrad beta radiation, and I b. During any calendar year: less than or equal to 10 mrad gamma and less than or equal to 20 mrad beta l radiation. APPLICABILITY: At all times, i ACTION: a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above i limits, prepare and submit to the Commission, within 30 days, a special Report, pursuant to Specification 6.9.2, which includes: 1) Identification of the cause for exceeding the limit (s). 1 2) Corrective action taken to reduce the release of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the remainder of the current calendar year so that the average dose during the calendar year is less than or equal to 10 urad gamma and 20 mrad beta radiation. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. c. The reporting requirements of Specification 6.9.1.9.b are not applicable. 4, SURVEILLANCE REQUIREMENTS 4.11.2.2 DOSE CALCULATIONS: Cumulative dose contributions for the current calendar quarter and current calendar year shall be l determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) at least once per 31 days. CRYSTAL RIVER - UNIT 3 3/4 11-11 Amendment No. 69

RADIOACTIVE EFFLUENTS 0000 - ICOINC-131, IRIIIUii, niiL AaLIGaCTIVs raariCULAn:S LIMITING CONDITION FOR OPERATION i 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from Iodine-131, Tritium, and radioactive particulates with half-lives greater than 8 days in gaseous effluents released from the site to areas at or beyond the SITE BOUNDARY (See Figure 5.1-3) shall be limited as follows: a. During any calendar quarter: less than or equal to j 7.5 ares to any organ, and i b. During any calendar years less than or equal to 15 ares to any organ. 4 i APPLICABILITY: At all times. ACTION: a. With the calculated dose from the release of Iodine-l 131, Tritium, and radioactive particulates with l greater than 8 day half-lives, in gaseous effluents, exceeding any of the above limits, prepare and submit to the commission, within 30 days, a Special Report, pursuant to Specification 6.9.2, which includes: I 1) Identification of the cause for exceeding the limits (s); i 2) Corrective action to reduce those ' releases during the remainder of the current calendar quarter and the remainder of the current calander year so that the average dose to any orgar. is less than or equal to 15 area. i b. The provisions of Specifications 3.0.3 and 3.0.4 are a not applicable. i c. The reporting requirements of Specification 6.9.1.9.b are not applicable. l CRYSTAL RIVER - UNIT 3 g 3/4 11-12 Amendment No. 69 rr--- - + - -- -

,-,w,-,-,m,

,v---. ,,-,.-ww.w.,,-, - - - -.. - - -,,-- ---+-_y-

.v-m---.-,

, - - - -. - -, - - -. - - - -, - ~.... <

RADIOACTIV" EFFLUENTS I DOSE - I_ODINE-131, TRITIUM, A_ND,, RADIOACTIVE _PARTICULATES l 1-...... ..o, SURVEILLANCE REQUIREMENTS 4.11.2.3 DOSE CALCULATIONS: Cumulative dose calculations for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE LOSE CALCULATION MANUAL (ODCM) at least once per 31 days. l F ~ i l e 1 i i l CRYSTAL RIVER - UNIT 3 3/4 11-13 Amendment No. 69

f RADIOACTIVE EFFLUENTS 3/4.11.3 'itTAL 0051', I::::TI::0 CO:: : TION 00n Ortn?.T!On 3.11.3 The calendar year dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 areas to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 areas). APPLICABILITY: At all times. ,m ACTION: a. With the calculated. doses from the release of radioactive materials in liquid or gaseous affluents exceeding twice the limits of specification 3.11.1.2.a, 3.11.1. 2. b, 3.11. 2. 2. a, 3. ll. 2. 2. b, 3. ll. 2. 3. a, or 3.11.2.3.b, calculations should be made, which include direct radiation contributions from the reactor, to determine whether the above limits of Specification 3.11.3 bave been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6. E2, a Special Report that defines the corrective action to be taken to reduce l subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This l Special Report, as defined in 10 CFR Part 20.405c, t shall include an analysis that estimates the radiation j exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle mources, includ'ing all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the esposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in. 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 provisions of 40 CFR Part 190. Schmittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable. c. The reporting requirements of Specification 6.9.1.9.b are not applicable. l CRYSTAL RIVER - UNIT 3 3/4 11-14 Asendsent No. 69 l l

RADIOACTIVE EFFLTTE??TS 3/4.11.3 TOTAL DOSE (Continued) l l SURVEILLANCE REQUIREMENTS 4.11.3 DOSE CALCULATIONS - Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the OFFSITE COSE CALCULATION tWICAL (CCC:1). ~ 'i CRYSTAL RIVER - UNIT 3 3/4 11-15 Amendment No. 69 --.7

l '/4.12 "'OICLOC'" """"""'""E""""*"'"C 3/. 1a.1 JCG;T0a UG 2 ROC;Ad I L "!T7"O cot *0TTTOti 700 0702.'.?i*" i 3.12.1.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1. APPLICABILITY: At all times. ACTION: I a. With the radiological environmental monitoring program i not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual-Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. b. With the level of radioactivity, resulting from plant effluents, in an environmental sampling medium exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, prepare and submit l to the Commission, within 3D-days of obtaining analytical results from the affected sampling period, g a Special Report pursuant to Specification 6.9.2, which identifies the cause(s) for exceeding the limit (s) and defines corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3. When more than one of the 1 radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if: concentration (1) concentration (2) 1 + +... > 1.0 limit level (1) limit level (2) 4 When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is greater than or equal to the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not i required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report. CRYSTAL RIVER - UNIT 3 3/4 12-1 Amendment No. 69 1 . ~...

~ ACTION (Continued) i c. Wisa alix or tresa leary vegetaoAe samples unavalAmole l from vue or more of the mumple locations required by i Tacle 3.12-1, id n ify the cau22 0d =ce un272:4201_ :y et i of samples and identify 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 those required by Table 3.12-1, provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations. d. The provisions of Specifications 3.0.3 and 3.0.4 are ~ not applicable. j e. The reporting requirements of Specification 6.9.1.9.b are not applicable. i ~ SURVEILLANCE REQUIREMENTS ~ 4.12.1.1 The radiological environmental monitoring samples shall i bo collected pursuant to Table 3.12-1 from the locations given in i the table and figure (s) in the OFFSITE DOSE CALCULATION MANUAL j (ODCM) and shall be analyzed pursuant to the requirements of Tchles.3.12-1 and 4.12-1. 1 4 CRYSTAL RIVER - UNIT 3 3/4 12-2 Amendment No. 69 ,-,.- m ---..--,-.--vm,+ .---y .,.w

~ TABLE 3.12-1 1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM n5 M# h Eaposure Pathway Number of Samples Sarnpling/ Type /Fregrency .g and/or Sasaple and Locations Collection Frequency of Analysis + c-h

1. AIRBORNE One sample each:

Continuous sampler / Radiolodme canisters Radioiodine and CO7, CIS, C40, C41, Weekly collection y particulates C46, and Control a) 1-131 analysis weekly Location C47 Particulate sampler a) Grossp at I 24 hours / following weekly filter change. b) Composite gamma sp/ctral analysis (by location) R quarterly. (Gamma Spectral Analysis shall also be d performed on individ al 4, samples if gross beta activity of any samph is 3 greater than 1.0 p Ci/m !i and which is also greater than ten times the control samg te activity.)

2. DIRECT RADIATION

1) Site Boundary:

Continuous Gamma exposure rate /quitterly C60, C61, C62, C63, placement / Quarterly C64, C65, C66, C67, collection g C68, C69, C41, C70, g C27,C71,C72,C73 3

2) Five Miles:

CIS, C03, C04, C74, g C75,C76,C08,C77, C09, C78, Cl4G, C01, C79

3) Control Location:

C47

g if. TABLE 3.12-1 (Continued) a> { OPERATK)NAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM G FTl ? ? C 5 Exposure Pathway Number of Samples Sampling / Type / Frequency [ and/or Sample and Locations Collection Frequency of Analysis 4 1

3. WATERBORNE One sample each:

Seawater Cl4H, Cl4G Grab sample / Monthly Gamma spectral Control Location Cl3 analysis / monthly i Tritium analysis on each scmple i or on a quarterly compctite u . of monthly samples i 1 Ground water One sample: C40 (Control Grab sample / Gamma spectral and j 4 7 Location) semiannual Tritium analysis /each sa.nple li Drinking water One sample each: l I C07, CIO, CIS Grab sample / quarterly Gamma spectral and Tritiom i (All Control analysis /each sample Locations) i i Shoreline sediment One sample each: , c Gamma spectral analysis /each Cl4H, Cl4M, Cl4G Semiannual sample Control Location sample F C09 lb l 3 l

4. INGESTION iE'"

3 Fish & Invertebrates One sample each: Quarterly: , Gamma spectral analysis on i C29, Control Location Oysters and carnivorous edible portions /each sasi pie i C30 fish.

e i

i j ~ L . + - i,

-^ ^ ~ 9 ~ i TABLE 3.12-1 (Continued) o OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2 y E U Exposure Pathway Number of Samples Sampling / Type / Frequency and/or Sample and Locations Collection Frequency of Analysis w One sample each: Monthly (when available): Gamma spectral and I-lil Food Products C48a', C48b', Sample comprised of analysis /each sample Control Location C47 three (3) types of broad leaf vegetation from each location One sample: Annual during harvest: Gamma spectral analysis / y Cl9 Citrus each sample M One sample: Annual during harvest: Gamma spectral analysi: / C04 Watermelon each sample i,. i I E E$

Stations C48a and C48b are located at or beyond the 4400 tt. site boundary for gaseous ef fluents in the two sectors uhleh 3 cid i

E the highest historical annual average D/Q values. E i )

T. .. v bCO.a i - ~,. ~ 9 s TABLE 3.12-2 Y REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES B c 5 Water Airborne Particulate Fish Milk Food Products Analysis (pCl/I) or Gases (pCi/m3) (pCl/Kg, wet) (pCl/1) (pCl/Kg, wet) u I H-3 20,p00 *I un-34 1,000 30,000 Fe-39 400 10,000 Co-SS 1,000 30,000 u1 Co-60 300 10,000 a 7 Zn-63 300 20,000 m Zr-Nb-93 400 ICI 1-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 30 20 2,000 70 2,000 Ba-La-140(b) g g E I a (a) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, = ,o a value of 30,000 pCi/l may be used. E (b) An equilibrium mixture of the parent and daughter isotope which contains the reporting value of i the parent isotope. (c) For drinking water samples only.. l

.:a. i ~ 9 S'i TABLE 4.12-1 ?~ ~ MAXIMUM VALUES FOR TN LOWER LIMITS OF DETECTION (LLD) a,d m2 m, E Water Airterne Partir*date Fish Mille Food Products St dia nt Q Analysis (pCi/I) or Caen (pC1/m3) (pCl/Kg, wet) (pCi/1) (pCl/Kg, wet) (p 3/Kc, dry) sa -0.01 gross beta 3H 34 13 130 h 39, 30 260 7 g 38 13 IM g g 60 13 130 g 63 3o 260 h C 1 93 IS g f

131, i

0.079 t 60 i 134 13 0.03' 130 13 60 I0 g 137 IS 0.06* ISO 18 80 1:.0 g -j 140 IS IS C C t ~ a E e l

I TABLE 4.12-1 (Continued) u TABLE NOTATION a. The LLD* ls the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal. +. For a particular measurement system (which may include radiochemical separation): 4.66_ LLD = 'b i-(E) (V) (2.22) (Y) (e" ^ ^ * ) Where: LLD is the lower limit of detection as defined above (as picocurie per unit mass or volume), sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as a,ppropriate (as counts per minute), E is the counting efficiency (as counts per disintegration), V is the sample size (in units of mass or volume), 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yleid (when applicable), A is the radioactive decay constant for the particular radionuclide, and

~

At is the elapsed time between sample collection (or end of the sample

i collection perod) and time of counting (for environmental samples, not plant i-effluent samples).

't Typical values of E, Y, Y andet should be used in the calculation. l-

The LLD is defined as an' a_ priori (before the fact) limit representing the capability of the measurement system and not as an a, posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLD's will be achieved under routine conditions. Occasionally, backgrour.d fluctuations, unavoidable small sample sizes, the presence of interferring nuclides, or other uncontrollable circumstances I

may render these LLD's unachievable. In such cases, the contributing factors shall be C Identified and described in the Annual Radiological Environmental Operating Report. CRYSTAL RIVER - UNIT 3 3/4 12-8 Amendment No. 69 l l l

i 1 l TABLE 4.12-1 (Continued) l 1 TEL NcT/mcN b. LLD for drinking water. If no drinking water pathway exits, a value of 3000 pCi/l may be used. i c. . The specified LLD is for an equilibrium mixture of parent and daughter nuclides which contain 15 pel/l of the parent nuclide. d. Other peaks which are measurable and identifiable, together with the radionuclides in Table 4.12-1, shall be identified and reported. m Cs-134, and Cs-137 LLD's apply only to the quarterly composite gamma spectral analysis, not to analyses of single particulate filters. f. LLD for drinking Ete. If no drinking water pathway exists, the LLD of gamma Isotopic analysis may be used. g. LLD for I-131 applies to a single weekly fil'er. t t 4 1 4 s J 4 -k i I i. i, 1 J. j ,~ 6 r i e f y '. j; 7' g /. - a l ~ CRYSTAL RIVER - UNIT 3. .( 3/4 12-9 Amendme,nt No. 69 / .'/ e 3 . ~~' r--~~ / Ea 5 7~~N 5~~

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C ) RADI AL SYMMETRY - ( ( / / IN THIS PLANE y % ~l / l V i .i /---% / \\ / \\ \\ l Bases Figure 3 2 incore instrumentation Specificatum Acceptable Minimum OUADRANT POWER TILT Arrangement CRYSTAL RIVER - UNIT 3 8 3/4 3-5
3/4.3 INSTRUMENTATION BASES 3/4.3.3.8 RADIOACTIVE LIQUID EFFLI*ENT INSTRUMENTATION ' The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instru-ments shall be calculated in accordance with the proc'edures in the OFFSITE DOSE CALCULATION MANUAL (ODCM) to ensure that the alarm / trip will occur prior to exceeding the' limits of 10 CFR -e i Part 20. The OPERASILITY 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. 3/4.3.3.9 RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments are calculated in accordance with the procedures in the OFFSITE DOSE CALCULATION MANUAL (ODCM) to e'nsure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. 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. 3/4.3.3.10 WASTE GAS DECAY TANK - EXPLOSIVE GAS MONITORING INSTRUMENTATION The OPERABILITY of the Waste Gas Decay Tank explosive gas "~ l ' monitoring instrumentation or the sampling and analysis program l] required by this specification provides for the monitoring (and 's controlling) of potentially explosive gas mixtures in the Waste Gas Decay Tanks. ! i i CRYSTAL RIVER - UNIT 3 B 3/4 3-6 Amendment No. 69
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BASES 1 3/4.7.13.1 WASTE GAS DECAY TANKS Restricting the quantity of radioactivity contained in each waste gas decay tank provides assurance that in the event of a simultaneous uncontrolled release of all of the tanks' contents, the resulting total body exposure to an individual at.the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with FSAR accident analyses.
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.[.4.53., };;Q ; i.. ::.'.:.i._:.29l-2-;; s . u '1H YDNJ@F r--- 3/4."[.13.2 LIQUID WASTE TREATMENT ,-c. The requirement that these systems be used when specified' provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably- < F' achievable" (ALARA). This specification implements the
V-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 CPR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of,the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.
e i CRYSTAL RIVER - UNIT 3 B 3/4 7-7 Amendment No. 69
PLAFT SYSTEMS l BASES 1 I 3/4.7.13.3 WASTE GAS SYSTEM The requirement that these systems be used when specified provides reasonable assurance that the releasas of radioactive materials in gaseous effluents will be kept "as low as is reasonable achievable" (ALARA).. 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 were specified as a suitable fraction of the dose design-objectives set forth in Sections II.B and II.C of Appendix I,~10 CFR Part 50, for gaseous effluents. _ = ~ ~ ~ + 3/4.7.13.4 SOLID RADIOACTIVE WASTE -t This specification implements the requirements of 10 CFR Part 50.36 and General Design Criterion 60 cf 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 chemica1 constituents, ~- mixing and curing times. 3/4.7.13.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the Waste Gas Decay Tanks is maintained below the flmamability limits of j . hydrogen and oxygen. Maintaining the congentration of hydrogen ,j and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in -2 l~j conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50. l t i I CRYSTAL RIVER - UNIT 3 B 3/4 7-8 Amendment No. 69 u
y l ~ 3/4.11 RADIOACTIVE EFFLUENTS l DASCS l 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. . l ?his limitation provides additional assurance that the levels of j radioactive materials in bodies of water in UNRESTRICTEu.. YEAS, will result in exposures within. (1) the Section II.A design ob-u jectives of Appendix I, 10 CFR 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR 20.106(e) to the population. Thei concentration limit for dissolved or entrained noble gases is based upon the assum'ption that Xe-135 is the controlling ?;.,< radioisotope and its MPC in air (submersion was converted to an., equivalent concentration in water using the methods described in Interndtional Commission on Radiological Protection (ICRP) l Publication 2.) 3/4.11.1.2 DOSE ~ 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 Operation implements the guides set forth in Section II.A of Appendix I. The ACTION ctatement provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be 2 kept "as low as is reasonably achievable" (ALARA). The dose calculations in the OFFSITE DOSE CALCULATION MANUAL (ODCM) 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 a MEMBER OF.THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the OFFSITE DOSE CALCULATION MANUAL (ODCM). 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 Effluent from Accidental and Routine Reactor Releases for the Purpose Of Implementing Appendix I," April 1977. CRYSTAL RIVER - UNIT 3 B 3/4 11-1 Amendment No. 69 -,n ,n,n.-. ,,...n ,.m
l i RADIOACTIVE EFFLUENTS j I BASES 3.4.11.2 GASEOUS EFFLUENTS 3.4.11.2.1 DOSE RATE This specification is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents will be within the annual dose limits of 10 CFR Part 20. The annual l dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II Co.lumn 1. These limits' provide reasonable assurance that radioactive material discharged - in gaseous effluents will not result in the exposure of a MEMBER.-L. .P OF THE PUBLIC, either within or outside the SITE BOUNDARY to" w annual average concentrations exceeding the limits specified in.d ' Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106 (b) (1) )., For a MEMBER OF THE PUBLIC who may at time be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE l PUBLIC will be sufficiently low to compensate for any increase in. - the atmospheric diffusion factor above that for the SITEW-BOUNDARY. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem / yea'r to the total body or to less than or equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem / year. 3/4.11.2.2 DOSE, NOBLE GASES l, 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 l Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the -required operating flexibility and at the same time implement the N guides set forth in Section IV.A of Appendix I to assure that the ' releases of radioar-tive material in ' gaseous effluents will be kept "as low as is reasonably achievable" (ALARA). 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 that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the OFFSITE DOSE CALCULATION MANUAL (ODCM) for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in l Regulatory Gui'de 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the P urpose of l l CRYSTAL RIVER - UNIT 3 B 3/4 11-2 Amendment No. 69 l
RADIOACTIVE EFFLUENTS l i I l BASES l l l l ,3/4.11.2.2 DOSE, NOBLE GASES (Continued) 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 OFFSITE DOSE CALCULATION MANUAL (ODCM) equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the, historical average atmospheric conditions._.,: j . ;.c.. - -. e q..:, ..?w.r. g : :..i - 3/4.11.2.3 DOSE, IODINE-131, TRITIUM, AND RADIOACTIVE 9 ~ ....x g.v.4;.3..h. PARTICULATES 2 e.. 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 i Limiting conditions for Operation are the guides set forth in i Section II.C of Appendix I. The ACTION statements provide the 'equired 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 is reasonably achievabl e" '( ALARA). The OFFSITE DOSE CALCULATION MANUAL (ODCM) calculational methods spacified 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 that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The OFFSITE DOSE CALCULATION MANUAL (ODCM) methods for calculating the dose due.to the actual release rates of the subject materials 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 Regulat'ory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous
~~a Effluents in Routine Releases from Light' Water-Cooled Reactors,"~~
Revision 1, July 1977. These equations also provide for 1 determining the actual doses based upon the historical average l atmospheric conditions. The release rate specifications for Iodine-131, Tritium, and radioactive particulates with half-life less than eight days are dependent on the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways which were examined in the development of these calcu-lations were: 1) Individual inhalation of airborne radionuclides,
2) deposition of radionuclides onto green leaf vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with con-sumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.
CRYSTAL RIVER - UNIT 3 B 3/4 11-:3 Amendment No.69
RADIOACTIVE EFFLUENTS BA'sEs 3/4.11.3 TOTAL CCSE This specification is provided to meet the dose limitations of 40 CFR Part 190 that have now been incorporated into 10 CFR Part 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 design objective doses of Appendix I. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190. if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose cantributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.405c, is considered t'o be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190 and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Specifications 3.11.1 and 3.11.2. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. 'N ll ,i't i l CRYSTAL RIVER - UNIT 3 B 3/4 11-4 Amendment No. -69 "T-~*-+v -en- .,.,-_.,,y,
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological 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 MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program 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' 32.. efflu~ent measurements and modeling of the environmental exposure. pathways. Program changes may be initiated based on operational,
~~g. -~~
~ experience. I f The LLD's required by Table 4.12-1 are considered optimum for routine environmental measurements in industrial laboratories. The LLD's for drinking water meet the requirements of 40 CFR 141. 3/4.12.2 LAND USE CENSUS i This specification is provided to ensure that changes in the use of areas at or.beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census. Adequate information gained from door-to-door or aerial surveys or through consultation with local agricultural authorities shall.be used. 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 required to produce the quantity i (26 kg/ year) of leafy vegetables assumed.in Regulatory Guide 1.109 for consumption by a child. To determine this minimum -sm '~ garden size, the following assumptions were used:
~~1) that 20% of i~~
the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2). a vegetation yield of 2 i I kg/ square meter. 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM j 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. CRYSTAL RIVER - UNIT 3 8 3/4 12-1 Amendment No. 69 l
5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area is shown on Figure 5.1-1. LOW POPULATION ZONE 5.1.2 The low population zone is shown on Figure 5.1-2. MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS 5.1.3 Information regarding radioactive gaseous and liquid effluents, which allows identification of structures and release I points as well as definition of UNRESTRICTED AREAS within the_. SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC, shall ~ ~ be as shown in Figure 5.1-3. 5.2 CONTAINMENT CONFIGURATION 5.2.1 The reactor containment building is a steel lined, reinforced concrete building of cylindrical shape, with a dome roof and having the following design features: a. Nominal inside diameter = 130 feet, b. Nominal inside height = 157 feet. c. Minimum thickness of concrete walls = 3.5 feet. d. Minimum thickness of concrete roof = 3 feet. i e. Minimum thickness of concrete ficor pad = 12.5 feet. f. Nominal thickness of steel liner = 3/8 inches. ~ g. Net free volume = 2 x 106 cubic feet. h CRYSTAL RIVER - UNIT 3 5-1 Amendment No. 69 w- . - - - ~ ~ - -, av.----- ,,~,- .x w ,n..- -. - -a w
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FOR LIQUID EFFLUENTS g WITHIN SITE BOUND-SH Tm u.se 3 v l ~ gy ,q p----r A' latete Coast -A 2 f p Casi tard g met. i,, 9 ge N m .2 hb 5 @ kwlt = z y O O W (LD 9 6
1 I DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 Thereactorcontainmentbuildingisdesignedandshallbemaintsined for a maximum internal pressure of 55 psig and a temperature of 281*F. 5.3 REACTOR CORE e FUEL ASSEMBLIES 5.3.1 The rector core shall contain 177 fuel assemblies with 'each fuel assembly containing 208 fuel rods clad with Zircaloy -4.- Each fuel rod shall have a nominal active fuel length of 144 inches and contain a maximum total weight of 2253 grams uranium. The initial core loading shall .s l Reload fuel shall be - . have a maximum enrichment of 2.83 weight percent U-235; similat n physical design to the initial core loading and'shall_have aj'"e i~ { inaximum enrichment of J.30 weight forcent _U-235Kg{ r;- % ., ?.: ^ i. ~.,.=._ . t... -a . n.,. r..:.. 2 _. ~- ~ CONTROL RODS 5.3.2 The reactor core shall contain 61 safety and regulating and 8 axial power shaping (APSR) control rods. The safety and regulating control rods shall contain a nominal.134 inches of absorber material. The APSR's shall contain a nominal 36 inches. of absorbe~r material at their lower ends. The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing. ^! R., i CRYSTAL RIVER - UNIT 3 5-4 Amendment No. M 36 1
ADMINISTRAT2VE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each mercer of.the facility staff shall meet or excaed the minim::m qualifi::ti:ns f ANSI N13.1-1:i71 fer : r: arable positions, ex ect or exceed the cualifications of Regulatory Guide 1.8, Septenner 1975, for the Chemistry and Radiation Protection Manager who shall' meet 1 and tne Operacions Technical Advisor. who shall have a 3achalcr's degree, or the equivalent, in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents. 6.4 TRAINING 6.4.1 A retraining and replacement training program for the fadility staff shall be maintained under the direction of the Nuclear Plant Manager and shall meet or exceed the requirements and reconmendations of. Section 5.5. of _ ANSI _N18_.1-19,71 andAccen. dix"A."of10,CFR_Part556...,..', ~- 1 6.4.2 A'1Faining pmgram for the Fire Brigade shall til maintaiiie'd'undr direction of the Nuclear Plant Training Manager and shall meet or: l exceed the requirements of Section 27 of the NFPA Code-1976, except i for Fire Brigade training sessions which shall be held at least quarterly.. .7 ) 6.5 REVIEW AND AUDIT' 6.5.1 PLANT REVIEW COMMI ic: (PRC) FUNCTION ~ 6.5.1.1 The Plant Review Cocc:ittee shall function to ad. vise the Nuclear Plant j Manager on all matters related to nuclear safety. COMPOSITION 6.5.1.2 The ' Plant Review Committee shall be composed of the: Chainnan: Technical Services Superinteindent Mee er: Operations Superintendent a! Mam er: Maintenance Superintendent Member: Nuclear Technical Services Superintendent (Security) Mad er: QA/QC Compliance Manager ,j Mod er: Chem / Rad Protection Manager Member: Technical Support Engineer 4' Member: Perfomance Engineering Supervisor i Member: At Large (Designated by Chainnan) ,y Member: At Large (Deisignated by Chairran) i ALTERNATES 6.5.1.3 All altamate members shall be appointed in writing by the PRC Chair-man to serve on a temporary basis; no more than two alternates shall participate as voting meters in PRC activities at any one time. i MEETING FREQUENCY 6.5.1.4 The PRC shall meet at least once per calendar month and as convened by the PRC Chaiman or his designated alternate. CRYSTAL RIVER - UNIT 3 6-5 Amendnent No. J. U, Jf, )),57 .-..,,--,-e., ..w, 3m-. w . - - -m-m.,
ADMINISTRATIVE CONTROLS QUORCM 6.5.1.5 A quorum of the PRC shall consist of the Chairman or his designated alternate and five members including alternares. RESPONSIBILITIES' I 6.5.1.6 The Plant Review Committee shall be responsible for: a. Review of 1) all procedures and changes thereto as required by Specification 6.8.2, 2) any other proposed procedures or changes thereto as determined by the Nuclear Plant Manager to affect nuclear safety.. ~ { b. Review of all proposed tests and experiments that l affect nuclear safety. Review of all proposed changes to the Appendix "A" c. Technical Specifications, d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety, and changes to radwaste systems which could significantly alter their ability to meet Appendix I. I Investigation of all. violations of the Technical e. Specifications including the preparation and ~ forwarding of reports covering evaluation and recommendations to prevent recurrence to the vice President, Nuclear Operations and to the Chairman of l the Nuclear General Review Committee, f. Review of events requiring 24-hour written notification to the Commissien. l, g. Review of facility operations to detect potential I nuclear safety hazards. h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Nuclear General Review Committee. i. Review of the' Plant Security Plan and' implementing procedures, j., Review of the Emergency Plan and implementing procedures. i { CRYSTAL RIVER - UNIT 3 - 6-6 Amendment No. Jl 7), J7, 69 l L
l* l i l ADMINISTRATIVE CONTROLS l l l RESPONSIBILITIES (Continued) k. Review of every unplanned on-site release of radioactive material to the environs, including the review and forwarding of reports covering evaluation, recommendations and disposition of the corrective action taken to prevent recurrence to the Plant Manager'and Nuclear General Review Committee. 1. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.~ '.,.45._i,..... .J. u. _.... :.,. 3 ....~ k 4 1 1 ~j 1 i i ^ i CRYSTAL RIVER - UNIT 3 6-6a Amendment No. 69
ADMINISTRATIVE CONTROLS CONSULTANTS ~ 6.5.2.5' Consultants shall be utilized as detemined by the NGRC Chairuan to provide expert advice to th~e NGRC. MEETING FREQUENCY -+ 6.5.2.6' The NGRC shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter. QUORUM
~~6. 5. 2. 7 A quorum of NGitC siialY' cons'ist of the Chairman or his designated alternate and five additional NGRC members, including alternates.~~
No more than a minority of the quorum shall have line responsibility for operation of the facility. REVIEW 6.5.2.8 The NGRC shall review: The safety evaluations for 1) changes to procedures, equipment a. or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question. b. proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59,10 CFR. c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59,10 CFR. d. Proposed changes in Technical Specifications or this Operating Li cense.. e. Violations of codes, regulations, orders, Technical Specifications, l' license requirements, or of internal procedures or instructions having nuclear safety significance. f. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety. CRYSTAL RIVER - UNIT 3 6-9 ~ - - a
ADMINISTRATIVE CONTROLS REVIEW (Continued) g. Events requiring 24-hour written notification to the Commission. h. All recognized indications of an unanticipated deficiency in some aspect of design of operation of safety related structures, systems, or components. i. Reports and meetings minutes of the Plant Review Committee. J. Changes to the PROCESS CONTROL PROGRAM and to the OFFSITE DOSE CALCULATION MANUAL. AUDITS -- c ~' 6.5.2.9 Audits of facility activities shall be performed under the cognizance of the NGRC. These audits shall encompass: The conformance of facility operation to provisions contained within the a. Technical Specifications and applicable license conditions at least once per 12 months. b. The perfcrmance, training, and qualifications of the entire facility staff at least once per 12 months. The results of actions taken to correct deficiencies occurring in facility c. equipment, structures, systems or method of operation that affect' nuclear safety at least once per 6 months. 3 d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B,10 CFR 50, at least once per 24 months. k-The Facility Emergency Plan and implementing procedures at least once per e. 24 months. f. The radiological environmental monitoring program and the results thereof at least once per 12 months. N I. Li g. The OFFSITE DOSE CALCULATION. MANUAL and implementing procedures at least once per 24 months. h. The PROCESS CONTROL PROGRAM and implementing procedures for i solidfication of radioactive wastes at least once per 24 months. I 1. The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 12 months. CRYSTAL RIVER - UNIT 3 6-10 Amendment No. J, 73, 69 i
ADMINISTRATIVE CONTROLS ~ AUDITS (Continued) f. The Facility Security Plan and implementing procedures at least once per 24 months. g. The facility fire protection program and implementing procedures at least once per'24 months. h. Any other area of facility operation considered appropriate by the NGtC or the Senior Vice_ President-Engineering and Construction. ik($55y..'h: y...5. -- _ &p:s@,~g.jpm#:;i. p ; y, 9,.. AUTHORITY r ?.,.m... .p: n ay,n 6.5.2.105 The' NGRC shall report'to-and advise.the Senior Vice.- j ;.? p, President-2:ngineering and Construction on those areas of responsibility specified in Sections 6.5.2.8 and 6.5.2.9. 1 1 RECORDS W c I 6.5.2.11 Records of NGRC activities shall be prepared, approved, l and distributed as indicated belows i a. Minutes of each NGRC meeting shall be prepared,.. 4 approved and forwarded to the Senior Vice President-Engineering'and Construction within 14 days following each meeting. b. Reports of reviews encompassed by Section 6.5.2.8 above, shall be prepared, approved and forwarded to the Senior Vice President-Engineering and Construction within 14 days following completion of the review. 1 c. Audit reports encompassed by Section 6.5.2.9 above, shall be forwarded to the Senior Vice President-Engineering and Construction and to the management i': positions responsible for the areas audited within 30 )) days after completion of the audit. 6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES: a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9. b. Each REPORTABLE OCCURRENCE requiring 24. hour notification to the Commission shall be' reviewed by the PRC and submitted to the NGRC and'the Vice-President, Nuclear Oper~ations. CRYSTAL RIVER - UNIT 3; 6-11 Asendment No. ), U, J7,69 ..e--- _,--,,n. ,, -.,.,,,,,,, -, - _ _ - -,,,.,,., _, -,. - - -,... _, - ~,,,,,,,, -.., -,,, - -,. -,
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 facility shall be placed in at least HOT STANDBY within one hour. b. The Safety Limit violation shall be reported to the Commission, the Vice President, Nuclear Operations and to the NGRC within 24 hours. 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 NGRC and the Vice President, Nuclear Operations 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 recommended in Appendix "A" of Regulatory Guide 1.33, November,1972. b. Refueling operations. c. Surveillance and test activities of safety related equipment. d. Security Plan implementation. e. Emergency Plan implementation. l f. , Fire Protection Program implementation. } g. Systems Integrity Program implementation. ,] h. Iodine Monitoring Program implementation. 1. PROCESS CONTROL PROGRAM implementation. !] j. OFF-SITE DOSE CALCULATION MANUAL implementation. l 3 l k. Quality Assurance Program for effluent and environmental monitoring. CRYSTAL RIVER - UNIT 3 6-12 Amendment No. 5, 7)9, 25, Jp,... 57, 6 w-c -,--r-r -.. -- m--.
~ ADMINISTRATIVE CONTROLS 6.8 PROCEDURES (Continued) 6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed and approved prior to implementation as follows: The Emergency Plan, Security Plan, Fire Protection a. Plan and implementing procedures, Administrative Instructions and those test procedures associated with plant modifications shall be reviewed and approved by the PRC and the Nuclear Plant Manager prior to implementation.. .m :.. .n, -m.r. c-5,: :.m.. ^ b. Fo'r all other' procedures, the review cycle shall-consist of: an intradepartmental review by a.se-- . r. Qualified Reviewer, and interdisciplinary review by Qualified Reviewer (s) in interfacing departments, as specified in Administrative Procedures, and approval by the responsible Superintendent or Manager, as specified by Administrative Procedures. The PRC shall then review the 10 CFR 50.59 evaluation within 14 days of approval, The training and qualification of Qualified Reviewers c. shall be governed by Administrative Procedures, with final certification by the Nuclear Plant Manager. Recertification will be required on a periodic basis and upon transfer between departments. As a minimum, all Qualified Reviewers shall meet the requirements of ANSI N18.1-1971, Sections 4.2, 4.3, 4.4, or 4.6, or the equivalent. d. Each procedure and administrative policy of 6.8.1 shall be reviewed on a periodic basis as set forth in Administrative Procedures. t CRYSTAL RIVER - UNIT 3 6-12a Amendment No. 57, 69
o ADMINISTRATIVE CONTROLS ' 5. 8. 3 Temporary changes t' procecures of 6.8.1 aoove may be made provided: 4 a. The intant of.ne original precedure is not altered. b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License. c. The change is documented and subsequently reviewed and approved within 14 days of implementation, in accordance with the requirements of. Specification 6.8.2. 6.9 rep 0RTING REQUIREMENTS ROUTINE rep 0RTS AND rep 0RTABLE OCCURRENCES a. 6.9.1 ~ In addition to the applicable reporting recuirements of Title 10 Code of Federal Regulations, the following reports shall be sub-mitted to the Director of the Regional Cffice of Inspection and Enforcement unless otherwise noted., STARTUp rep 0FTS~ 6.9.1.1 A su= nary report of plant startup a.,d power es:21ation testing will be submitted following (1) receipt of an operating license, (2) amendment to the license involving a olanned increase in power level. j (3) iristallation of fuel that 'has a different desi manufac.ured by a different fuel supplier, and (4)gn or has been nodifications that j may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. 6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a descriction of the measured values of the operating conditions or characteristics catained during the test program and a.comparisen of these values with design predictio.ns and specifications. Any corrective actions that were required +a obtain satisfactory operation shall also be described. Any additional
~~specific details requested in license conditions based on other j~~
commitments shall be included in this report. Startup reports shall be submitted within (1) 90 days following 6.9.1.3 completion of the startup test program, (2) 90 days following(3) resumption or comencement of comercial power operation, or 9 months following initial criticality, whichever is earliest. 2 If the Startup Report does not cover all three events (i.e., initial criticality, ecmpletion of startup test program, and the resumption or comencement of comercial power operation), supple-mentary reports shall be submitted at least every three months until all three events have been completed. ), 1. i CRYSTAL RIVER - UNIT 3 6-13 Amendment No. ), 7,57 l m J
ADMINISTRATIVE CONTROLS ANNUAL AND SEMIANNUAL REPORTS l 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year..The initial report shall be submitted prior to March I of the year following initial criticality. 6.9.1.5 Reports required on an annual basis shallinclude: A tabulation of the number of station, utility, and other personnel a. (including contractors) receiving exposures greater than 100 mrem /yr. and their associated man-rem exposure according to work and job functions 1 e.g., reactor operations and surveillance, inservice inspection, routine maintenance,. special maintenance (describe maintenance), waste processing, and refueling. The dose assignments to various duty functionO.,- may be estimated based on pocket dosimeter, TLD, or film badge ~" measurements. Small exposures totalling less than 20 percent of the7 J Individual total dose need not be accounted for. In the aggregate, at least ' 30 percent of the total whole body dose received from external sources should be assigned to specific major work functions. ,...a, b. A list of the reactor vessel material surveillance capsules installed in the reactor at the end of the report period and a summary of any withdrawals ~ or insertions of capsules during the report period. In supplying this information, the ownership of each capsule shall be indicated and the l irradiation location in the vessel of each capsule which was inserted l during the report period shall be identified. A routine Annual Radiological Environmental Operating Report covering c. the operation of the unit during the previous calendar year shall be j-submitted prior to May 1 of each year. The Annual Radiological Environmental Operating Report shall include 1 summaries, interpretations, unachievable LLDs, and an analysis of trends i of the results of the radiological environmental studies and previous i Annual Radiological Environmental Operating Reports and an assessment of any observed impacts of the plant operation on the environment. If harmful effects or N I This tabulation supplements the requirements of 20.407 of 10 CFR Part 20. CRYSTAL RIVER - UNIT 3 6-14 - hoendment S, J7,69 9 ,.m.. ~..,., -, -,,. - - - - - -..

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l ~ ' ADMINISTRATIVE COyTROLS AWNUAL AiW SEiiIyNUAL REFCRTS (Continued) evidence of irresarsible damage ard detected by the i monitoring, the report shall provide an analysis of the. problem and a planned course.of action to al%eviate the problem. j The Annual Radiological Environmental Operating Report, shall include, summarized a.nd tabulated results in the format of Regulatory Guide 4.8, December 1975, of all radiological environmental samples taken during-the.r,eport period. In the event that some results' are not available for inclusion with the ' rep;rt, the report shall be submitted noting and explainir.g the reasons for the missing results. -The'misning results shall be submitted as soon as possible in a e supplementary report. l The report, shall also include the following a summary description of the radiological environmental monitoring program; a<n,ap of all sampling locations keyed to a table giving distances and directions from the reactor; the unavailability of milk or fresh leafy vegetable samples required by Table 3.12-1; the results of land use censuses required by, Specification,- 3.12.1.2; and the results of licensee pa.:ticipation in ~ the Interlaboratory, Comparison Program,. required by Specification 3.12.1.3. d. A semiannual Radioactive Effluent Release Report. l covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 r days'after January 1 and Jul'y 1 of each year. ~ ,e y The Semiannual Radioactive Effluent Release Report shall include a summary of. the.quantiti'es of' radioactiv.e liquid and gaseous affluents and solid waste released from the plant as outlined in Regulatoly' Guide 1.21, " Measuring, Evaluating and'r i Reporting Radioactivity in Solid Wastes and Releases Jof1 Radioactive Materials in Liquid'and' Gaseous ' Effluebacffrom Light-Water-Cooled Nuclear' Power !PlantF,' Revision 1, June 1974, with 6ata summarized ! on a* quarterly basiG'following the format cf Appendix s ' B thereof. af ti v s - y ' 'The SeNiadnual Radioactive ~ Effluent Release Report which is submitted 160 Says after January 1 of each year shall' include an annual summary of hourly meteorological dqta collected'over the previous year. This annual su:smary may be either in the form of ~ ( v.s i f 6-14a7'/ is CRYSTAL RIVER - UNIT 3 Amendment No. 69 s a s
l ADMINISTRATIVE CONTROLS ANNUAL AND SEMIANNUAL REPORTS (Continued) an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form.of joint frequency distributions of wind speed, wind direction, and atmospheric stability.* This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit during the previous calendar year. This + same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous ~ effluents -to individuals due to their activities 7 -. inside the. SITE BOUNDARY (Figure 5.1-3) during thez report period.- All assumptions used in making theseX1 ~ assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous affluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE 1 CALCULATION MANUAL (ODCM). The radioactive effluent release report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the hypothetical worst case incividual from reactor releases (including doses from primary affluent' pathways and direct radiation) for the previous calendar year. Acceptable methods for calculating the dose contribution from liqafd and gaseous effluents are given in Regulatory Guide 1.109, Revision 1. 1 1 The radioactive affluent release report. shall include lj] the following information for each type of solid waste shipped offsite during the report periods ~ i 1) container volume, l 2) total curie quantity (specify whether determined by measurement or estimate), . 3) principal radionuclides (specify whether determined by measurement or estimate),
~~In lieu of submittal, these meteorological data may be retained in an on-site file and provided to the NRC upon request.~~
CRYSTAL RIVER - UNIT 3 6-14b Amendment No. w- = m-- .-v- .,wm,--=vre. ,--e---
~ ADMINISTRATIVE CONTROLS l 4 ANNUAL AND SEMIANNUAL REPORTS (Continued) i 4) type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms), 5) type of container (e.g., LSA, Type A, Type B, Large Quantity), and 6) solidification agent (e.g., cement). The Semiannual Radioactive Effluent Release' Report shall include a list and description of unplanned releases to UNRESTRICTED AREAS of Iadioactive" '~ ~ materials in gaseous and liquid effluents made during the' reporting period.+
~~' %': 9' "~~
~ The Semiannual Radioactive Effluent Release Report - shall include a description of any changes to the PROCESS CONTROL PROGRAM (PCP), the Radioactive Waste; Treatment Systems, the OFFSITE DOSE CALCULATION MANUAL, as well as a listing of new Environmental Radiological Monitoring Program dose calculation location changes identified by the land use census made during the reporting period. 4 t. 4 d i: d CRYSTAL RIVER - UNIT 3 6-14c Amendment No.69
1 ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of.operaring statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analysi. U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with.a copy to the - Regional Office, submitted no later than~the 15th of each month following the calendar month covered by the report. REPORTABLE OCCURRENCES 6.9.1.7 The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9 below, including corrective actions and measures to S prevent recurrence, shall be reported to the NRC.- Supplemental'., reports may be required to fully describe final resolution of.- occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date. PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.8 The types of events listed below shall be reported within 24 hours by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate no later than the first working day following the event, with a' written followup report within 14 days. The written followup report shall include, as a minimum, a completed copy of a licensee event report fom. Information provided on the licensee event report fora shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event. a. Failure of.the reactor protection system or other Lystems subject to limiting safety-system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint specified i as the limiting safety-system settiry in the technical I specifications or failure to complet a the required ) protective function. o b. Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the Limiting Condition for Operation established in the technical specifications. c. Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment. CRYSTAL RIVER - UNIT 3 6-15 Amendment No. 7, 69
ADMINISTRATIVE CONTROLS y. Reactivity ancaalias involving disagreewent with che predicted value cf reactivity balanca undar staady-stata ccalli*cnc Caric.: ecwar c:eratica creater than ~~ or equal to 14 Ak/k ; a calculated reactivity balance indicating a shutdown margin less conservative than specified in the technical specifications; short-term reactivity increases that correspond to a reactor startup rate of greater than 5.2 DPM or, if subcritical, an unplannsi reactivity insertion of more than 0.5% Ak/k; or occurrence of any unplanned criticality. e. Failure or malfunction of one or more com'ponents which' prevents or could prevent, by itself, the fulfillment ~ of the functional requirements of system (s)'used to cope with accidents analyzed in the SAR.,,.. c. . = y...; f. Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to. cope with accidents analyzed in the SAR.. g. Conditions arising from natural or man-made events l that, as a direct result of the~ event, require plant shutdown, operation of safety systems, or other protective measures required by technical sp'cifications. e h. Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or .t could have permitted reactor operation in a manner less conservative than assumed in the analyses, i. Performance of structures, systems, or components that requires remedial action or corrective measurta to ~- prevent operation in a manner less censervative than that assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition. 1 CRYSTAL RIVER - UNIT 3 6-16 Amendment No. 7, 25, 69 l
ADMINISTRATIVE CONTROLS THIRTY-DAY WRITTEN REPORT 6.9.!.9 The type: cf eve.t: li:t:d 5:!ow shr.!! 5: th: :ubicct of written reports to the D! ::tc. f th ". ;!:r.r.: Cf!::: whh r. Z ays cf occurcer.ce of t;,e cent. The writ:en report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event. Reactor protection system or engineered safety feature instrument settings a. which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems. 3.. b. Conditions leading to operation in a degraded mode permitted by 'a limiting ^ condition for operation or plant shutdown required by a limiting condition for operation. c. Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems. d. Abnormal degradation of systems other than those specified in 6.9.1.8.c above, designed to contain radioactive material resulting from the fission process. I i -1 ~m . 1 .]. i; ) t i j 2 I l 9 CRYSTAL RIVER - UNIT 3 6-17 Amendment No. 9, 73,69 i e S .m,
~. d ADMINISTRATIVE CONTROLS j SPECIAL REPORTS E.9.2 Special reyrts shall be mbaitted to % Direter of the Office of Inspection and Enforcement, Region II, within the time naried'snecified for each report. These reports shan be suomicced covering LL=.csivision identiZi.J bale pescant to the requirements of the applicable reference specification: a; ECCS Actuation, Specification 3.5.2 and 3.5.3. i b. Inoperable seismic Monitoring Instrumentation, l Specification 3.3.3.3. c. Inoperable Meterorological Monitoring Instrumentation, l specificatio.n 3.3.3.4. I l l d. Seismic event analysis, specification 4.3.3.3.2. Inoperable Fire Detection Monitoring Instrumentation, e.. Specification 3.3.3.7. _f f. Inoperable Fire suppression System, specifications C ~ 3.7.11.1, 3.7.11.2, 3.7.11.3, and 3.7. n.4 3 g. Dose due to radioactive materials in liquid effluents in excess of specified limits,. Specification 3. n.1.2. h. Dose due to noble gas in gaseous effluents in excess of specified limits, Specification 3.11.2.2. l 1. Total calculated dose due to release of radioactive effluents exceeding twice the limits of Specifications 3.n.1.2.a,.3.11.1.2.b, 3.11.2.2.a, 3. n.2.2.b, l 3.11.2.3.a, or 3.11.2.3.b (required by Specification 3.11.3). j. Dose due to Iodine-131, Tritium, and radioactive particulates with greater than 8 day half-lives, in gaseous affluents in excess of specified limits, Specification 3.11.2.3. k. Failure to process liquid radwaste, in excess of . limits, prior to release, specification 3.7.13.2. 1. Failure to process gaseous radwasca, in excess of limits, prior to release, Specification 3.7.13.3. m. Measured levels of radioactivity in environmental sampling medium in excess of the reporting levels of Table 3.12-2, when averaged over any quarterly sampling period, specification 3.12.1.1. n. Unavailability of milk or fresh leafy vegetable samples, Specification 3.12.1. o, Inoperable. Mid or High Range Noble
~~Gas Efficient Monitoring Instrumentation, Specification 3.3.3.1.~~
CRYSTAL RIVER - UNIT 3 6-17a Amendment No.69
AD.MINISTRATI','E C0hT..0L5 i l 4 i6.10 RECORD RETENTION 6.10.1 The following records'shall be reta.ined for at least five years: ~ a. Records and logs of facility operation covering time intervals at each power level. i b' Records' and lo'g's 'of principal maintenance ' activities, inspec-tions',' re;iair an(replacement of principal items of equipment '1 ~- related to 'n'uclear safetyg- . u.v- '~~ l c. All REPORTABLE OCCURRENCES submitted to the Comissione d.T Ric'6rds of'sdrveillance activities, inspections and calibra-tions required by these Technical Specifications. i e. Records of reactor tests and experiments. f. Records of changes made to Operating Procedures. g. Records of radioactive shipments. h. Recorcs of :ealed source and fission detector leak tests and results. i. Records of annual physical inventory of all sealed source material of record. 6.10.2 The following records shall be retained for the duration of i the Facility Operating License: 4 1 Records and drawing changes reflecting facility design modifi- ] a. cations made to systems and equipment described in the Final Safety Analysis Report. 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. CRYSTAL RIVER - UNIT 3 6-18 Amendment No. 9 l
r ~ ADMINISTPATIVE CONTROLS l e. Records of gaseous and liquid radioactive material ralcasad to thc cnvircns. l l f. Records of transient or operational cycles for those facility components identified in Table 5.7.-l. l g. Records of training and qualification for current members of the plant staff. l h. Records of inservice inspections performed.p,ursuant to these Technical Specifications. I i 1. Records of Quality Assurance activities required by - the QA Manual. w. g :. y :. n ;.. J r:,;. j. Records of reviews performed for changes made to pro-cedures or equipment or reviews of tests and experi-ments pursuant to 10 CFR 50.59. RecordsofshetingsofthePRCandNGRC. l k. t 1. Records for Environmental Qualification which are covered under the provisions of paragraph 6.13. m. Records of analytical results required by the Operational Radiological Environmental Monitoring Program. 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. j 6.12 HIGH RADIATION AREA q l 6 12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2) of 10 CFR 20: i a. A High Radiation Area'in which the intensity of radia-tion is greater than 100 arem/hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted 2 as a High Radiation Area and entrance thereto shall be controlled by issuance of a Radiation Work Permit and any individual or group of individuals permitted to, enter such areas shall be provided with a radiation monitoring device which continuously indicates the i radiation dose rate in the area. Amendment No orth!F.dt t. M. 7. CRYSTAL RIVER - UNIT 3 6-19 69 9 ,-e.. --,---w, n.
~ ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA (Cont inuec) b. A High Radiation Area in which the intensity of radia-tion is greater than 1000 mrem /hr shall be subject to the provisions of 6.12.la above, and in addition locked doors shall be provided to prevent unauthorized entry into such area. The keys shall be maintained under the administrative control of the Health Physics 7 Supervisor with one key assigned to the administrative control of Shift Supervisor en duty. - +:+.,P S .g j._ p. n ?-W-6.13 ENVIRONMENTAL QUALIFICATION T'? - a n;:.- -
..... - i. :

g.;. ; -
6.13.1 By no later t an June 30, 1982, all safety-related h electrical equipment in the facility shall be qualified in t accordance with the provisions of Division of Operating Reactors " Guidelines for Evaluating Environmental Qualification cf Class., 0.- J lE Electrical Equipment in Operating Reactors" (DOR Guidelines) or NUREG-0588 " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," December, 1979. Copies of these documents are attached to Order for Modification of License DPR-72 dated October 24, 1980. 6.13.2 By no later than. December 1, 1980, complete and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588. Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified. e ] 6.14 PROCESS CONTROL PROGRAM (PCP) 6'.14.1 The PCP shall be approved by the Commission prior to j j implementation. 6.14.2 Licensee initiated changes to the PCP: i 1. Shall be submitted to the Commission in the Semi-annual Radioactive Effluent Release Report for the period in which the change (s) was made. 2. Shall become effective upon review and acceptance by the Plant Review Committee. CRYSTAL RIVER - UNIT 3 6 20 Deder 44+:.lC/2*T8tT, Amendment No. 69 ,-.-----s., ,-.,%wm--,-.-----,.w-- +.-v-, - -, .>---s-- -r ..me.,,en--.w-.- -%-n n-.-w--- e-,me-. - -, -,.-,-. ,-w--- u.----. e,..-
ADMINISTRATIVE CONTROLS 1 G.15 0""OI"E COSE CALCULATION M_A'7UAL (ODNi l 6.15.1 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall be l approved by the Commission prior to implementation. 6.15.2 Licensee initiated changes to the OFFSITE DOSE CALCULATION MANUAL (ODCM): I 1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the ' period in which the change (s) was made effective. 2. Shall become effective upon review and acceptance by. _. the Plant Review Committee. =/, ~- -- ~ ~ ' ol .p 6.16 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous and Solid) t l 6.16.1 Licensee initiated major changes
~~to the radioactive waste systems (liquid, gaseous and solid):~~
i 1. Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Review Com ittee or be included as part of the. annual FSAR update. 2. May be implemented upon review and acceptance by the Plant Review Committee. lr 1' i l* 1
~~A major change to a radioactive waste system shall be any change which would alter the ability of the plant or system to meet the requirements of 10 CFR 50, Appendix I.~~
~~CR'.STAL RIVER - UNIT 3 6-21 Amendment No. 69 .}}~~

v t e Letter Sequence Approval
TAC:08985, (Open)
Initiation Request Acceptance... Administration Meeting Questions Answers Results Approval, Approval Other: 3F1283-21, Suppl 2 to 830117 Tech Spec Change Request 36 to Amend License DPR-72 Making Editorial Clarifications to Operational Environ Monitoring Program,Per NRC Request, ML19250B821, ML20054G586, ML20072A835, ML20072A838, ML20074A408, ML20081K366, ML20083C480, ML20087M288, ML20093D015, ML20151H898
MONTHYEAR1983-10-13 [Table View]

ML20093D006

Text

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