ML20072A838
| ML20072A838 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/17/1983 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20072A836 | List: |
| References | |
| TAC-08985, TAC-8985, NUDOCS 8301240165 | |
| Download: ML20072A838 (93) | |
Text
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INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS DEFINED TERMS 1-1 THERMAL POWER l-1 RATED THERMAL POWER l-1 OPERATIONAL MODE l-1 ACTION 1 OPERABLE - OPERABILITY 1-1 REPORTABLE OCCURRENCE l-2 CONTAINMENT INTEGRITY l-2 CHANNEL CALIBRATION 1-2 CHANNEL CHECK 1-2 CHANNEL FUNCTIONAL TEST l-3 CORE ALTERATION 1-3 SHUTDOWN MARGIN 1-3 IDENTIFIED LEAKAGE l-3 UNIDENTIFIED LEAKAGE l-4 PRESSURE BOUNDARY LEAKAGE l-4 CONTROLLED LEAKAGE l-4 QUADRANT POWER TILT l-4 DOSE EQUIVALENT I-131 1-4 E-AVERAGE DISINTEGRATION ENERGY 1-4 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 CRYSTAL RIVER - UNIT 3 I
~' 8301240165"830117 ~ ~
5 PDR ADOCK 05000302 P
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.Q INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS (Continued)
WASTE GAS SYSTEM l-6 VENTILATION EXHAUST TREATMENT SYSTEM l-6a PURGE-PURGING l-6a VENTING l-6a INDEPENDENT VERIFICATION 1-6a LIQUID RADWASTE TREATMENT SYSTEM 1-6a MEMBER (S) OF THE PUBLIC 1-6b SITE BOUNDARY 1-6b UNRESTRICTED AREA 1-6b OPERATIONAL MODES (TABLE 1.1) 1-7 FREQUENCY NOTATION (TABLE 1.2) 1-8 CRYSTAL RIVER - UNIT 3 la
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 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 - FQ 3/4 2-4 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - F H 3/4 2-6 3/4.2.4 QUADRANT POWER TILT 3/4 2-8 3/4.2.5 DNB PARAMETERS 3/4 2-12 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 3-26 Seismic Instrumentation 3/4 3-28 Meteorological Instrumentation 3/4 3-31 Remote Shutdown Instrumentation 3/4 3-34 Post-accident Instrumentation 3/4 3-37 Fire Detection Instrumentation 3/4 3-40 Radioactive Liquid Effluent Monitoring Instrumentation 3/4 3-42 Radioactive Gaseous Effluent Monitoring Instrumentation 3/4 3-47 Waste Gas Decay Tank - Explosive Gas Monitoring Instrumentation 3/4 3-53 CRYSTAL RIVER - UNIT 3 IV 4<
r-4 INDEX LIMITING CONDITIO6 FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS 3/4 4-1 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 CRYSTAL RIVER - UNIT 3 IVa
l INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 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 Decay Heat Sea Water System 3/4 7-17 3/4.7.5 ULTIMATE HEAT SINK 3/4 7-18 3/4.7.6 FLOOD PROTECTION 3/4 7-19 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM 3/4 7-20 3/4.7.8 AUXILIARY BUILDING VENTILATION EXHAUST SYSTEM 3/4 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 FIRE 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 7-45 3/4.7.12 PENETRATION FIRE BARRIERS 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
o INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Operating 3/4 8-1 Shutdown 3/4 8-6 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating 3/4 8-7 A.C. Distribution - Shutdown 3/4 8-9 D.C. Distributicn - Operating 3/4 8-10 D.C. Distribution - Siiutdown 3/4 8-12 CRYSTAL RIVER - UNIT 3 VIIA 1
INDEf LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.11 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 Dose -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 3/4 12-11 i
CRYSTAL RIVER - UNIT 3 VIIIa l
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't INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 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 3/4.7.5 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 3/4.7.8 AUXILIARY BUILDING VENTILATION EXHAUST SYSTEM B 3/4 7-5 1
3/4.7.9 HYDRAULIC SNU8BERS B 3/4 7-5 3/4.7.10 SEALED SOURCE CONTAMINATION B 3/4 7-6 3/4.7.11 FIRE SUPPRESSION SYSTEMS B 3/4 7-6 f
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 i
3/4.7.13.5 EXPLOSIVE GAS MIXTURE B 3/4 7-8 CRYSTAL RIVER - UNIT 3 XII i
INDEX BASES SECTION PAGE 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A. C. SOURCES B 3/4 8-1 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION B 3/4 9-1 i
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 l
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CRYSTAL RIVER - UNIT 3 XIIA
INDEX BASES SECTION PAGE 3/4.11 RADIOACTIVE EFFLUENTS 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,1-131, TRITIUM AND RADIOACTIVE PARTICUL ATES B 3/4 11-2a 3/4.11.3 TOTAL DOSE B 3/4 11 3 t
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM B 3/4 12-1 3/4.12.2 LAND USE CENSUS B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM B 3/4 12-1 l
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CRYSTAL RIVER - UNIT 3 XIIIa
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INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE Exclusion Area 5-1 Low Population Zone 5-1 Map Defining Unrestricted Areas for Radioactive Gaseous and Liquid Effluents 5-1 5.2 CONTAINMENT Configuration 5-1 Design Pressure and Temperature 5-4 5.3 REACTOR CORE Fuel Assemblies 3-4 Conu ol Rods 3-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature 5-5 Volume 3-5
)
5.5 METEORLOGICAL TOWER LOCATION 5-5 5.6 FUEL STORAGE Criticality 5-5 Drainage 5-5 Capacity 5-6 l
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5-6 l
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l CRYSTAL RIVER - UNIT 3 XIV i
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INDEX ADMINISTRATIVE CONTROLS SECTION PAGE Meeting Frequency 6-9 Quorum 6-9 Review 6-9 Audits 6-10 Authority 6-11 Records 6-11 6.6 REPORTABLE OCCURRENCE ACTION 6-11 6.7 SAFETY LIMIT VIOLATION 6-12 6.8 PROCEDtJRF.S 6-12 1
6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE AND REPORTABLE OCCURRENCES 6-13 Startup Report 6-13 f
Annual and Semiannual Reports 6-14 Monthly Operating Report 6-15 Reportable Occurrences 6-15 Prompt Notification with Written Followup 6.15 Thirty Day Written Reports 6-17 6.9.2 SPECIAL REPORTS 6-17a 6.10 RECORD RETENTION 6-18 6.11 RADIATION PROTECTION PROGRAM 6-19 6.12 HIGH RADIATION AREA 6-19 6.13 ENVIRONMENTAL QUALIFICATION 6-21 6.14 PROCES} CONTROL PROGRAM 6-21 6.15 OFFSITE DOSE CALCULATION MANUAL 6-22 6.16 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS 6-22 l
CRYSTAL RIVER - UNIT 3 XVI
DEFINITIONS ENGINEERED SAFETY FEATURE RESPONSE TIME 1.25 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from 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., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).
Times shall include diesel generator starting and sequence loading delays where applicable.
PHYSICS TESTS 1.26 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 13 cf the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or
- 3) etaerwise approved by the Commission.
SOURCE CHECK 1.27 A SOURCE CHECK shall be the qualitative a3sessment of channel response when the channel sensor is expcued to a radioactive source.
PROCESS CONTPOL PROGRAM (PCP) 1.28 The PROCESS CONTFOL PROGRAM is the sampling, tests, i
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 requirements.
OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.30 The OFFSITE DOSE CALCULATION MANUAL is the document which contains the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid 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 any equipment (e.g., tanks, vessels, piping) capable of collecting primary coolant system offgases trom the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
CRYSTAL RIVER - UNIT 3 1-6
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DEFINITIONS VENTILATION EXHAUST TREATMENT SYSTEM 1.32 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing lodines or particulates from the gaseous exhaust stream prior to release to the environment (such a system is not considered to have any effect on noble gas effluents).
Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
l PURGE - PURGING 1.33 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, l
humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
VENTING l.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 l
VENTING.
Vent, used in system names, does not imply a VENTING j
prc:ess.
INDEPENDENT VERIFICATION 1.35 INDEPENDENT VERIFICATION is a separate act of confirming or substantiating 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 i
the activity or condition was completed or implemented in accordance with specified requirements.
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LIQUID RADWASTE TREATMENT SYSTEM i
1.36 The LIQUID RADWASTE TREATMENT SYSTEM shall be any available equipment (e.g., filters, evaporators) capable of reducing the quantity of radioactive material, in liquid effluents, prior to j
discharge.
CRYSTAL RIVER - UNIT 3 1-6a
i DEFINITIONS MEMBER (S) OF THE PUBLIC 1.37 MEMBER (S) OF THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant.
This category shall include non-employees of the licensee who are permitted td use portions of the site for recreational, occupational, or other purposes not associated with 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 controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materialc.
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.
UNRESTRICTED AREA 1.39 An UNRESTRICTED AREA shall be any area at or beyond tha 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.
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L CRYSTAL RIVER - UNIT 3 1-6b
FREQUENCY NOTATION NOTATION FREQUENCY S
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W At least once per 7 days.
M At least once per 31 days.
Q At least once per 92 days.
i SA At least once per 6 months.
R At least once per 18 months.
S/U Prior to each reactor startup.
P Completed prior to each release.
N.A.
Not applicable.
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CRYSTAL RIVER - UNIT 3 1-8
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TABLE 3.3-6 e
m RADIATION MONITORING INSTRUMENTATION 9
e Hd MINIMUM w
CHANNELS APPLICABLE ALi.RM/ TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION 2.
Process Monitors (Continued)
Y U
d.
Condenser Vacuum Pump S
Exhaust Monitor - Gaseous Activity Monitor (RM-A12) 1 1,
2, 3, 4
19 e.
Nuclear Services Closed Cooling Water Monitor (RM-L3) 1 All Modes 19 f.
Decay Heat Closed Cooling Water Monitors l
(RM-L5 and RM-L6) 1 All Modes 19 l
l
TABLE 3.3-6 (Continued)
TABLE NOTATION ACTION 14 -- With the number of channels OPERABLE less than required by-the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 15 -- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.
ACTION 16 -- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12.
ACTION 17 -- With number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.
ACTION 18 -- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.
ACTION 19 -- Wf.th the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, plant operation may continue provided grab samples are collected and analyzed for gross activity
- at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
-5
- LLDfornoblegasprincipalgammaemitterssgallbe5x10 Ci/cc.
LLD for liquid samples shall be lx10 Ci/ml.
CRYSTAL RIVER - UNIT 3 3/4 3-24 1
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TABLE 4.3-3
>r RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ENN CHANNEL MODES IN WHICH i
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REQUIRED cZ U
- 2. Process Monitors (continued) w d.
Condenser Vacuum Pump D
R M
1, 2, 3, 4 Exhaust Monitor - Gaseous Activity Monitor (RM-A12) w I
e.
Nuclear Servicas D
R M
All MODES Closed Cooling Water Monitor (RM-L3) f.
Decay Heat Closed D
R M
All MODES Cooling Water Monitors (RM-L5 and RM-L6) l l
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INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 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 set points shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
APPLICABILITY:
As shown on Table 3.3-12.
ACTION:
I With a radioactive liquid effluent monitoring a.
instrumentation channel alarm / trip setpoint less conservative than required above, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or change the setpoint so that it is acceptably cense:vative, or declare the channel inoperable.
t b.
With one or more radioacive liquid 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 affected 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.
The provisions of Specifications 3.0.3 and 3.0.4 are c.
not applicable.
d.
The reporting requirements of Specification 6.9.1.9.b are not applicable.
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SURVEILLANCE REQUIREMENTS 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 j
frequencies shown in Table 4.3-8.
l CRYSTAL RIVER - UNIT 3 3/4 3-42
O n8 TABLE 3.3-12 e
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION g
E 9
MINIMUM c
CHANNELS APPLICABLE INSTRUMENT OPERABLE MODES ACTION e
w 1.
GROSS RADIOACTIVITY MONITORS.PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE 1
- a. Auxiliary Building Liquid Radwaste 1
All MODES 21 Effluent Line (RM-L2)
- b. Secondary Drain Tank Liquid 1
All MODES 22 w
Effluent Line (RM-L7) 2.
FLOW RATE MEASUREMENT DEVICES
- a. Auxiliary Building Liquid Radwaste 1
All MODES 23 Effluent Line
- b. Secondary Drain Tank Liquid 1
All MODES 23 Mffluent Line 9
Table 3.3-12 (Continued)
TABLE NOTATION
\\
ACTION 21 With less than the required number of OPERABLE channels, effluent releases via this pathway may continuc, provided that prior to initiating a release:
a.
At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and b.
An INDEPENDENT VERIFICATION cf release rate calculations is performed, and c.
An INDEPENDENT VERIFICATION of discharge valve lineup is performed.
1 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 radioactivityi microcuries/ml.
at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, at an LLD of at least 10-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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
CRYSTAL RIVER - UNIT 3 3/4 3-44 r
-m,-
.,,y---.w.
O se TABLE 4.3-8 b
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS g
E 9
i CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL c
INSTRUMENT CHECK CHECK CALIBRATION TEST e
w 1.
GROSS RADIOACTIVITY MONITORS' PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
^
a.
Auxiliary Building Liquid D*
P R(1)
M Radwaste Effluent Line w
1 (RM L2) w b.
Secondary Drain Tank D*
D R(1)
M Liquid Effluent Line (RM-L7) 2.
FLOW RATE MEASUREMENT DEVICES a.
Auxiliary Building Liquid D(2)
N.A.
R N.A.
Radwaste Effluent Line b.
Secondary Drain Tank Liquid D(2)
N.A.
R N.A.
Effluent Line l
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TABLE 4.3-8 (Continued)
TABLE NOTATION
- During periods of release.
(1)
CHANNEL CALIBRATION shall be performed using:
a.
One or more standards traceable to the National Bureau of Standards, or b.
Standards obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards, or c.
Standards related to previous calibrations 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.
CRYSTAL RIVER - UNIT 3 3/4 3-46
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 their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.
The setpoints shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
APPLICABILITY:
As shown in Table 3.3-13.
ACTION t
a.
With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required above, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or change the setpoint so that it is acceptably conservative, or declare the channel inoperable.
b.
With cne or more radioactive gaseous effluent monitoring instrumentation channels inoperable, take the ACTION shown 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 Semiannual Radioactive Effluent Release Report..
The provisions of Specifications 3.0.3 and 3.0.4 c.
are not applicable.
d.
The reporting requirements of Specification l
6.9.1.9.b are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radiocctive gaseous effluent monitoring instrumentation channel shall be 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.
CRYSTAL RIVER - UNIT 3 3/4 3-47
L Oy TABLE 3.3-13 8
RADIOACTIVE GASEOUS uPFLUENT MONITORING INSTRUMENTATION 5
sW MINIMUM CHANNELS APPLICABLE OPERABLE MODES ACTION cz 1.
Waste Gas Decay Tank Monitor (RM-All) w a.
Noble Gas Activity Monitor
- 1 All MODES 24 b.
Effluent System Flow Rate Monitor 1
All MODES 26 u
2.
Reactor Building Purge Exhaust Duct w
i Monitor (RM-Al) m a.
Noble Gas Activity Monitor
- 1 All MODES 27 b.
Iodine Sampler 1
All MODES 25 c.
Particulate Sampler 1
All MODES 25 d.
Effluent System Flow Rate Monitor 1
All MODES 26 e.
Sampler Flow Rate Monitor 1
All MODES 26 3.
Auxiliary Building and Fuel Handling Area Exhaust Duct Monitor (RM-A2) a.
Noble Gas Activity Monitor
- 1 All MODES 28 b.
Iodine Sampler 1
All MODES 25 c.
Particulate Sampler 1
All MODES 25 d.
Effluent System Flow Rate Monitor 1
All MODES 26 e.
Sampler Flow Rate Monitor 1
All MODES 26
- Provides control room alarm and automatic termination of release.
TABLE 3.3-13 (Continued)
TABLE NOTATION ACTION 24 With less than the required number of OPERABLE channels, the contents of the Waste Gas Decay Tank may be released to the environment, provided that prior to initiating a release:
1.
The Auxiliary Building & Fuel Handling Area Exhaust Duct Monitor (RM-A2) is OPERABLE with it's setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.
The setpoint shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL, or 2.
- a. At least two independent samples of the tank's contents are analyzed in accordance with Table 4.11-2 and
- b. An INDEPENDENT VERIFICATION of release rate calculations is performed, and
- c. An INDEPENDENT VERIFICATION of discharge valve lineup is performed.
Otherwise, suspend releases of radioactive effluents via this pathway.
ACTION 25 With the number of OPERABLE channels less than required, effluent releases via the affected pathway may continue, provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.
ACTION 26 With the number of OPERABLE channels less than required, effluent releases via this pathway may continue, provided flow rate is estimated at least i
once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
l ACTION 27 With the number of OPERABLE channels less than required, immediately suspend PURGING of racioactive effluents via this pathway.
l l
CRYSTAL RIVER - UNIT 3 3/4 3-49 1
TABLE 3.3-13 (Continued)
~
TABLE NOTATION ACTION 28 With the number of OPERABLE channels less than required, releases via this pathway may continue, provided grab samples are collected at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 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.
G CRYSTAL RIVER - UNIT 3 3/4 3-50
Q TABLE 4.3-9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE W
INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED I
1.
WASTE GAS DECAY TANK cz MONITOR (RM-All) y
- a. Noble Gas Activity P
P R(1)
M All MODES Monitor g
- b. Effluent System Flow P
N.A.
R M
All MODES Rate Monitor 2.
REACTOR BUILDING PURGE EXHAUST DUCT MONITOR (RM-Al) w I
- a. Noble Gas Activity Di P
R(1)
M 1,
2, 3, 4 i
Monitor
- b. Iodine Sampler Wi N.A.
N.A.
N.A.
All' MODES
- c. Particulate Sampler Wi N.A.
N.A.
N.A.
All MODES
- d. Effluent System Flow Di N.A.
R M
All MODES Rate Monitor
- e. Sampler Flow Rate Di N.A.
R M
All MODES Monitor 3.
AUXILIARY BUILDING & FUEL HANDLING AREA EXHAUST DUCT MONITOR (RM-A2)
- a. Noble Gas Activity D
M R(1)
M All MODES Monitor
- b. Iodine 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
- e. Sampler Flow Rate D
N.A.
R M
All MODES Monitor e
G
TABLE 4.3-9 (Continued)
TABLE NOTATION
- During periods of Reactor Building Purge.
(1)
CHANNEL CALIBRATION shall be performed using:
a.
One or more standards traceable to the National Bureau of Standards, or b.
Standards obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards, or c.
Standards related to previous calibrations using (a) or (b) above.
CRYSTAL RIVER - UNIT 3 3/4 3-52
INSTRUMENTATION WASTE GAS DECAY TANK - EXPLOSIVE GAS MONITORING INSTRUMENTATION 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations (b) at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during othat operations.
SURVEILLANCE REQUIREMENTS 4.3.3.10 The Waste Gas Decay Tank explosive gas monitoring instrumentation shall be demonstrated operable by performing the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST anu CHANNEL CALIBRATION at the frequencies shown in Table 4.3-10.
CRYSTAL RIVER-UNIT 3 3/4 3-53
0 da TABLE 4.3-10
>c k
WASTE GAS SYSTEM EXPLOSIVE GAS MONITORING INSTRUMENTATION MW SURVEILLANCE REQUIREMENTS I
C
$e CHANNEL w
CHANNEL CHANNEL FUNCTIONAL INSTRUMENT CHECK CALIBRATION TEST 1.
Hydrogen Monitors D
Q*
M 4'
2.
Oxygen Monitors D
Q*
M
- The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
Hydrogen Monitors a.
1 volume percent hydrogen, balance nitrogen.
b.
4 volume percent hydrogen, balance nitrog9n.
Oxygen Monitors c.
1 volume percent oxygen, balance nitrogen, d.
4 volume percent oxygen, balance nitrogen.
PLANT SYSTEMS 3/4.7'.13.1 RADIOACTIVE WASTE SYSTEMS WASTE GAS DECAY TANKS LIMITING CONDITION FOR OPERATION 3.7.13.1 The quantity of radioactivity contained in each Waste Gas Decay Tank shall be limited to less than or equal to 39000 curies (considered as Xe 133).
APPLICABILITY:
At all times.
ACTION:
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 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within its limit.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.13.1 The quantity of radioactive material contained in each Waste Gas Decay Tank shall be determined to be within the limit at least once per 7 days whenever radioactive materisis are being added to the tank, and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> duting primary coolant system degassing operations.
l e
CRYSTAL RIVER - UNIT 3 3/4 7-48
PLANT SYSTEMS LIQUID RADWASTE TREATMENT SYSTEM LIMITING 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 mren whole body; b.
0.2 mrem to any organ.
APPLICABILITY:
At all times.
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.
- 3. Actions taken to prevent recurrence, 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 7-49
PLANT SYSTEMS LIQUID RADWASTE TREATMENT SYSTEM (Continued) i i
SURVEILLANCE REQUIREMENTS 4.7.13.2.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
i l
CRYSTAL RIVER - UNIT 3 3/4 7-50
PLANT SYSTEMS WhSTE GAS SYSTEM 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 mrem to any organ.
APPLICABILITY:
At all times.
ACTION:
a.
When the WASTE CAS SYSTEM and/or VENTILATION EXHAUST 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 the reason (s) for inoperability.
l
- 2) Actions taken to restore the inoperable equipment to OPERABLE status.
- 3) Actions taken to prevent recurrence.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
The reporting requirements of Specification c.
6.9.1.9.b are not applicable.
CRYSTAL RIVER - UNIT 3 3/4 7-51
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.13.3.1 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).
i CRYSTAL RIVER - UNIT 3 3/4 7-52
RADIOACTIVE EFFLUENTS WASTE SOLIDIFICATION SYSTEM I
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.
t APPLICABILITY:
At all times.
ACTION:
a.
With the provisions of the PROCESS CONTROL PROGRAM not 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 not applicable.
c.
The reporting requirements of Specification 6.9.1.9.b are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.13.4 The PROCESS CONTROL PROGRAM shall be used to verify i
the SOLIDIFICATION of at least one representative test specimen i
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).
i CRYSTAL RIVER - UNIT 3 3/4 7-53
PLANT SYSTEMS WASTE GAS DECAY TANK - EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3/4.7.13.5 The concentration of oxygen in any Waste Gas Decay Tank shall be limited to less than or equal to 2% by volume whenever the concentration of hydrogen in that Waste Gas Decay Tank is greater than or equal to 4% by volume.
APPLICABILITY:
At all times.
bCTION:
Whenever the concentration of hydrogen in any Waste Gas Decay Tank is greater than or equal to 4% by volume, and:
a.
The concentration of oxygen in that Waste Gas Decay Tank is greater than 2% by volume, but less than 4% by volume, without delay begin to reduce the oxygen concentration to within its limit.
b.
The concentration of oxygen in that Waste Gas Decay Tank is greater than or equal to 4% by volume, immediately 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 the 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
3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION 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 limits, without delay restore the concentration of radioactive materials being released to UNRESTRICTED AREAS to within the above limits.
If the concentration of radioactive materials being released in excess of the above limits 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.
l c.
The reporting requirements of Specification 6.9.1.9.b are not applicable.
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 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 1
TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit of Minimum Detection Liquid Release Sampling Analysis Type of Activity (LLD)
Type Frequency Frequency Analysis (11Ci/ml) "
A. Batch Waste P
P
~7 Releage Each Batch Each Batch PrincipagGamma 5x10 Tanks Emitters
- 1. Evaporator
-6 Condensate I-131 lx10 Storage Tanks (2)
-5 P
M Dissolved and lx10
- 2. Laundry &
One Batch /M Entrained Gases Shower Sump (Gamma Emitters)
Tanks (2)
-5 P
M H-3 lx10 b
Each Batch Composite
-7 Gross Alpha lx10 P
Q
- ~
b Each Batch Composite
-6 Fe-55 1x10
~
B. Continuogs W
PrincipagGamma 5x10 c
c Releases Continuous Composite Emitters
- 1. Secondary
-6 Drain Tank I-131 lx10
-5 M
M Dissolved and lx10 Grab Sample Entrained Gases (Gamma Emitters)
-5 M
H-3 lx10 c
c Continuous Composite
~
Gross Alpha lx10
-8 Q
Sr-89, Sr-90 5x10 c
c Continuous Composite
~0 Fe-55 1x10 CRYSTAL RIVER - UNIT 3 3/4 11-2
l
[
TABLE 4.11.1 (Continued)
TABLE NOTATION a.
The LLD* is 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):
4.66s b LLD
=
(E) (V) (2.22x10 ) (Y) (e - Ao t)
D 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 rate 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 At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
Typical values of E, V, Y, and At shall be used in the calculation.
i
- The LLD is 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
_. _~
TABLE 4.11-1 (Continued)
TABLE NOTATION, b.
A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids i
released.
To be representative of the quantities and concentrations of c.
radioactive materials in liquid effluents, samples shall be collected continuously in prooortion to the rate of flow of the effluent stream.
Prior to analyses, all samples taken for the composite shall be throughly mixed in order for the composite sample to be representative of the effluent 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.
i i
e.
A continuous release is the discharge of liquid wastes of a l
nondiscrete volume; e.g.,
from a volume or system that has
]
an input flow during the continuous release.
I f.
The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:
Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. 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 at the LLD level for that nuclide.
The "less than" values shall not be used in the required dose calculations.
J l
CRYSTAL RIVER - UNIT 3 3/4 11-4 i
I RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS - DOSE i
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:
a.
During any calendar quarter to less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ, b.
During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
)
APPLICABILITIY:
At all times.
ACTION:
a.
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 during the remainder of the current calendar 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 mrem total body and less than or equal to 10 mrem 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
RADIOACTIVE EFFLUENTS i
SURVEILLANCE REQUIREMENTS 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.
b d
e CRYSTAL RIVER - UNIT 3 3/4 11-6
~ ^ ~ "
s
t RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS - DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate at or beyond the SITE BOUNDARY, due to radioactive materials released in gaseous effluents (see Figure 5.1-3), shall be limited as follows:
a.
Noble gases:
less than or equal to 500 mrem / year total body and less than or equal to 3000 mrem / year to the skin.
b.
Iodine-131, Tritium, and radioactive particulates with half-lives of greater than 8 days:
less than or equal to 1500 mrem / year to any organ.
APPLICABILITY:
At all times ACTION:
a.
With dose rate (s) exceeding the above limits, without j
delay decrease the dose rate to within the above limits (s).
If the dose rate at or beyond the SITE 4
BOUNDARY due to radioactive materials in gaseous effluents in excess of the above limits is related to a plant operating characteristic, appropriate corrective measures (2,g.,
power reduction, plant shutdown) shall be taken to decrease the dose rate to within the above limits.
I 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.
1 SURVEILLANCE REQUIREMENTS 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 (ODCM).
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
e TABLE 4.11-2 O
RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM de Minimum Lower Limit of Sampling Analysis Type of Detection fLLD) xy Gaseous Release Type Frequency Frequency Activity Analysis (p Ci/ml)
P P
E
-4 A. Waste Gas Decay Each Tank Each Tank Principal Gamma Emitters lx10 E
Tank Grab y
Sample P
P c
b,f
~4 B. Reactor Building Each Purge Each Purge Principal Gamma Emitters lx10 Purge Exhaust Grab
~D Duct Monitor Sample H-3 lx10 (RM-A1) w
-4 c
C. Auxiliary Building M
M Principal Gamma Emitters lx10 2
and Fuel Handling Grab 8
Area Exhaust Duct Sample H-3 lx10,
Monitor (RM-A2)
D. All Release Types Continuous
- W
-12 as Listed in A, B, Charcoal I-131 lx10 C above Sample E
-11 Continuous" W
Principal Gamma Emitters lx10 t
Particulate (I-131, others)
Sample
-11 Continuous
- M Gross Alpha 1x10 Composite Particulate Sample
-11 Continuous
- Q Sr-89, Sr-90 lx10 Composite Particulate Sample Continuous
- Noble Gas Noble Gases lx10
- Monitor Gross Beta & Gamma
s TABLE 4.11-2 (Continued)
TABLE NOTATION a.
The LLD* is 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):
4.66s b LLD
=
(E) (V) (2.22x10') (Y) (e-Aat)
Where:
LLD is the lower limit of detection as defined above (as microcurie per unit mass or volume),
is the standard deviation of the background counting rate sb 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 At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
Typical values of E, V, Y, and at shall be used in the calculation.
- The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (af ter the f act) limit for a particular measurement.
CRYSTAL RIVER - UNIT 3 3/4 11-9
e TABLE 4.11-2 (Continued)
TABLE NOTATION b.
Analyses shall also be performed between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following shutdown, startup or a change in power level exceeding 15% RATED THERMAL POWER within one hour c.
Tritium grab namples shall be taken between 12 and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after flooding the refueling canal and at least once per 7 days thereafter while the refueling canal is flooded.
d.
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler).
Sampling and analyses shall be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup or change in power level exceeding 15% of RATED THERMAL POWER within one hour, unless the Iodine Monitoring Channels in Radiation Monitors RM-Al and RM-A2 show that the Radiciodine concentration in the Auxiliary Building and Fuel Handling Area or the Reactor 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
.c beyond the SITE BOUNDARY.
e.
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 l
emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.
i l
This list does not mean that only these nuclides are to be l
detected and reported.
Other peaks which are measureable 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.
l CRYSTAL RIVER - UNIT 3 3/4 11-10
e I
RADIOACTIVE EFFLUENTS i
DOSE-NOBLE GASES i
l LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose at or beyond the SITE BOUNDARY (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 mrad gamma and less 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 j
radiation.
APPLICABILITY:
At all times.
ACTION:
a.
With the calculated air dose from radioactive noble
~
gases 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:
1)
Identification of the cause for exceeding the l
limit (s).
I 2)
Corrective action taken to reduce the release of l
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 mrad gamma and 20. mrad beta radiation.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
The reporting requirements of Specification 6.9.1.9.b c.
are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2 DOSE CALCULATIONS:
Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) at least once per 31 days.
l CRYSTAL RIVER - UNIT 3 3/4 11-11
I RADIOACTIVE EFFLUENTS DOSE - IODINE-131, TRITIUM, AND RADIOACTIVE PARTICULATES LIMITING CONDITION FOR OPERATION 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 7.5 mrem to any organ, and b.
During any calendar year:
less than or equal to 15 mrem to any organ.
APPLICABILITY:
At all times.
l ACTION:
a.
With the calculated dose from the release of Iodine-131, Tritium, and radioactive particulates with 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:
1)
Identification of the cause for exceeding the limits (s);
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 organ is less than or equal to 15 mrem.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
I The reporting requirements of Specification 6.9.1.9.b c.
are not applicable.
CRYSTAL RIVER - UNIT 3 3/4 11-12
7 RADIOACTIVE EFFLUENTS DOSE - IODINE-131, TRITIUM, AND RADIOACTIVE PARTICULATES i
(Continued) l 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 DOSE CALCUi.ATION MANUAL (ODCM) at least once per 31 days.
4 I
l l
CRYSTAL RIVER - UNIT 3 3/4 11-13 l
RADIOACTIVE EFFLUENTS 3/4.11.3 TOTAL DOSE LIMITING CONDITION FOR OPERATION 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 mrems to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrems).
APPLICABILITY:
At all times.
ACTION:
a.
With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specification 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.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 have been exceeded.
If such is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits.
This Special Report, as defined in 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including 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 exposure levels or concentrations.
If the estimated I
dose (s) exceeds the above limits, and if the release condition resulting in vic1ation of 40 CFR Part 190 has 1
not already been corrected, the Special Report shall l
include a request for a variance in accordance with the I
provisions of 40 CFR Part 190.
Submittal 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.
The reporting requirements of Specification 6.9.1.9.b c.
I are not applicable.
CRYSTAL RIVER - UNIT 3 3/4 11-14
l RADIOACTIVE EFFLUENTS 3/4.11.3 TOTAL DOSE (Continued)
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 DOSE CALCULATION MANUAL (ODCM).
CRYSTAL RIVER - UNIT 3 3/4 11-15 e
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 4
3.12.1.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.
APPLICABILITY:
At all times.
ACTION:
a.
With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1 l
prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a i
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 to the Commission, within 30 days of obtaining analytical results from the affected sampling period, a Special Report pursuant to Specification 6.9.2, which identifies the cause(s) for exceeding the limit (s) and defined 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 radionuclides in Table 3.12-2 are detected in the j
sampling medium, this report shall be submitted if:
concentration (1) concentration (2) limit level (1) limit level (2)
-> 1.0
+
+
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 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
ACTION (Continued) c.
With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1; identify the cause of the unavailability 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.
e.
The reporting requirements of Specification 6.9.1.9.b are not applicable.
RADIOLOGICAL ENVIRONMENTAL MONITORING SURVEILLANCE REQUIREMENTS 4.12.1.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the locations given in the table and figure (s) in the OFFSITE DOSE CALCULATION MANUAL (ODCM) and shall be analyzed pursuant to the requirements of Tables 3.12-1 and 4.12-1.
CRYSTAL RIVER - UNIT 3 3/4 12-2
Q TABLE 3.12-1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
?
my Exposure Pathway Number of Samples Sampling /
Type / Frequency m
and/or Sample and Locations Collection Frequency of Analysis W
4 1.
AIRBORNE One sample each:
Continuous sampler /
Radioiodine canister:
cZ Radioiodine and C07, C18, C40, C41, Weekly collection y
particulates C46, and Control a) I-131 analysis / weekly Location C47 u,
Particulate sampler:
a) Gross g at > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> /
following weekly filter change.
- s a
b) Composite gamma spectral Y
analysis (by location)/
quarterly. (Gamma Spectral Analysis shall also be 4
performed on individual samples if gross beta activity of any sample is greater than ten times the control sample activity.)
2.
DIRECT RADIATION
- 1) Site Boundary:
Continuous Gamma dose /
C60, C61, C62, C63, placement /
quarterly C64, C65, C66, C67, Quarterly Collection C68, C69, C41, C70, C27, C71, C72, C73
- 2) Five Miles:
C18, C03, C04, C74, C75, C76, C08, C77, C09, C78, C14G, C01, C79 t
- 3) Control Location:
C47 i
a
e n
TABLE 3.12-1 (Continued)
OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM g
E 9
Exposure Pathway Number of Samples Sampling /
Type / Frequency 8
g and/or Sample and Locations Collection Frequency of Analysis U
w 3.
WATERBORNE One sample each:
Seawater Cl3, Cl4H, Cl4G Grab sample / Monthly Gamma spectral (All Control analysis / monthly Locations)
Tritium analysis /
w1 quarterly composite of monthly samples Y
a Ground water One sample:
C40 (Control Grab sample /
Gamma spectral and Location) semi-annual Tritium analysis /
each sample Drinking water One sample each:
C07, C10, C18 Grab sample / quarterly Gamma spectral and (All Control Tritium analysis /
Locations) each sample Shoreline One sample each:
sediment Cl4H, Cl4M, Cl4G, Semi-annual sample Gamma spectral Control Location analysis /each sample C09
O<
TABLE 3.12-1 (Continued)
OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3
&w i
Exposure Pathway Number of Samples Sampling /
Type / Frequency and/or Sample and Locations Collection Frequency of Analysis c
58 INGESTION Milk One sample each:
Monthly sample {
Gamma spectral and C49*
I-131/each sample Fish &
One sample each:
Quarterly:
Gamma spectral
[
Invertebrates C29, Control Oysters and analysis on edible Location C30 carnivorous fish portions /each sample 4
Food Products One sample each:
Semi-annual during Gamma spectral and C48*
harvest:
green leafy I-131 analysis /each vegetables sample One sample:
Annual during Gamma spectral C19 harvest:
Citrus analysis /each sample One sample:
Annual during Gamma spectral C04 harvest:
Watermelon analysis /each sample
- Stations C49 and C48 will be determined by annual land use census of Specification 3.12.1.2.
- Milk samples shall be collected twice per month if a milk animal is found to be located within 5 miles of the plant.
i el TABLE 3.12-2 E
REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES E
i 9
Water Airborne Particulate Fish Milk Food Products i
Analysis (pCi/1) or Gases (pCi/m3)
(pCi/Kg, wet)
(pCi/l)
(pCi/Kg, wet) c Me H-3 2x104(a)
Mn-54 1x103 3x104 Fe-59 4x102 lx104 w
Co-58 lx103 3x104 Co-60 3x102 lx104 Zn-65 3x102 2x104 2(b)
Zr-Nb-95 4x10 I-131 2
0.9 3
lx102 Cs-134 30 10 lx103 60 lx103 2
Cs-137 50 20 2x103 70 2x103 2(b) 2(b)
Ba-La-140 2x10 3x10 (a)
For drinking water samples.
This is 40 CFR Part 141 value.
(b)
Total for parent and progeny.
g TABLE 4.12-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,d 5<
Water Airborne Particulate Fish Milk Food Products Sediment AnOlysis (pCi/l) or Gas (pci/m3)
(pCi/Kg, wet)
(pCi/l)
(pCi/Kg, wet)
(pCi/Kg, dry) t i
E i
gross beta 4b 1 x 10-2 b
3H 2000 (1000 )
i 54Mn 15 130
{59e F
30 260 58,60 o 15 130 C
65 n 30 260 Z
95 r-Nb 15c Z
1311 lb 7 x 10-2 1
60 134, 137 s 15(10b), 18 5 x 10-2 130 15 60 150 C
140 a-La 15c 15c B
%s
TABLE 4.12-1 (Continued)
TABLE NOTATION a.
The LLD* is 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):
4.66s b (E) (V) (2.22) (Y) (e-Aat )
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 appropriate (as counts per minute),
i 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 yield (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 collection period) and time of counting (for environmental samples, not plant effluent samples).
Typical values of E, V, Y and At should be used in the calculation.
- 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.
CRYSTAL RIVER - UNIT 3 3/4 12-8 l
TABLE 4.12-1 (Continued)
TABLE NOTATION b.
LLD for drinking water.
c.
Total for parent and progeny.
d.
Other peaks which are measurable and identifiable, together with the radionuclides in Table 4.12-1, shall be identified and reported.
t l
CRYSTAL RIVER - UNIT 3 3/4 12-9 l
t
RADIOLOGICAL ENVIRONMENTAL MONITORING LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.1.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden
- of greater than 500 square feet producing fresh leafy vegetables in each of the land based meteorological sectors within a distance of five miles.
APPLICABILITY:
At all times.
ACTION:
a.
With a land use census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated by Specification 4.11.2.3, identify the new location in the next Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.5.c.
b.
With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) which is at least 20% greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1.1, this location shall be added to the radiological environmental monitoring program within 30 days.
Tne new sampling location shall replace the present sampling location, which has the lower calculated dose or dose commitment (via the same exposure pathway), after June 30 following this land use census..
Identification of the new location and revisions of the appropriate figures from the OFFSITE DOSE CALCULATION MANUAL (ODCM) shall be submitted with the next Semiannual Radioactive Effluent Release l
Report.
c.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
d.
The reporting requirements of Specification 6.9.1.9.b are not applicable.
l
- Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.
CRYSTAL RIVER -UNIT 3 3/4 12-10
I RADIOLOGICAL INVIRONMENTAL MONITORING LAND USE CENSUS (Continued)
SURVEILLANCE REQUIREMENTS 4.12.1.2 The land use census shall be conducted at least once per 12 months between the dates of March 1 and June 1 or September 1 and December 1 by a door-to-door survey, aerial survey, or by consulting local agriculture authorities, using that information which will provide adequate results.
i f
i l
i l
CRYSTAL RIVER -UNIT 3 3/4 12-10a
RADIOLOGICAL ENVIRONMENTAL MONITORING INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1.3 Analyses shall be performed on radioactive materials supplied as part of
.n Interlaboratory Comparison Program which has been approved by the Commission.
A summary of the results obtained from this program shall be included in the Annual Radiological Environinental Operating Report.
APPLICABILITY:
At all times.
ACTION:
a.
With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
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.
SURVEILLANCE REQUIREMENTS 4.12.1.3 No surveillance requirements other than those required by the Interlaboratory Comparison Program.
l CRYSTAL RIVER - UNIT 3 3/4 12-11
~
INSTRUMENTATION BASES 3/4.3.3.8 RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive I
materials in liquid effluents during actual or potential releases of liquid effluents.
The alarm / trip setpoints for these instru-I ments shall be calculated in accordance with the procedures in the OFFSITE DOSE CALCULATION MANUAL (ODCM) to ensure 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.
l 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) ensure l
that the alarm / trip will occur prior to exceeding the limits of l
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 l
INSTRUMENTATION The OPERABILITY of the Waste Gas Decay Tank explosive gas monitoring instrumentation or the sampling and analysis program required by this specification provides for t.he monitoring (and controlling) of potentially explosive gas mixtures in the Waste Gas Decay Tanks.
l i
CRYSTAL RIVER - UNIT 3 B 3/4 3-6 l-L
PLANT SYSTEMS.
BASES 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.
3/4.7.13.2 LIQUID WASTE TREATMENT 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 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 objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.
i 1
CRYSTAL RIVER - UNIT 3 B 3/4 7-7
.--.n.,-.--g
--,-, o
,-----n--<-~m,p-,.-
.,~---,.--,,-nnem-w
,m w
s,--m---
- m
l PLANT SYSTEMS BASES 3/4.7.13.3 WASTE GAS SYSTEM The requirement that these systems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is i
j 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 Apendix I, 10 CFR Part 50, for gaseous effluents.
3/4.7.13.4 SOLID RADIOACTIVE WASTE This specification implements the requirements of 10 CFR Part 50.36 and General Design Criterion 60 of Appendix A to 10 CFR Part 50.
The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste i
type, waste pH, waste / liquid / solidification agent / catalyst ratios, waste oil content, waste principal chemical 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 flammability limits of hydrogen and oxygen.
Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.
l l
l i
CRYSTAL RIVER - UNIT 3 B 3/4 7-8 w-e a-,e-e-e
,--i gi-s--
---,-+ -
-r--r y
,-r
3/4.11 RADIOACTIVE EFFLUENTS 1
BASES 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 i
UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2.
This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design ob-j 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. The concentration limit for dissolved or entrained noble gases is based upon the assumption 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 International Commission on Radiological Protection (ICRP)
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 statement provides the l
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 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 Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
L CRYSTAL RIVER - UNIT 3 B 3/4 11-1
~
RADIOACTIVE EFFLUENTS BASES i
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 dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II Column 1.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER l
OF THE PUBLIC, either within or outside the SITE BOUNDARY to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106 (b) (1) ).
For a MEMBER OF THE PUBLIC who may at time be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in I
the atmospheric diffusion factor above that for the SITE BOUNDARY.
The specified release rate limits restrict, at all times, the corresponding gamma and beta does 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 i
above background to child via the inhalation pathway to less than or equal to 1500 mrem / year.
l 3/4.11.2.2 DOSE, NOBLE GASES l
This Specification is provided to implement the requ'irements of-Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50.
The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I.
The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents 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 Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Rountine Releases of Reactor Effluents for the Purpose of CRYSTAL RIVER - UNIT 3 B 3/4 11-2
RADIOACTIVE EFFLUENTS BASES 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.
3/4.11.2.3 DOSE, IODINE-131, TRITIUM, AND RADIOACTIVE PARTICULATES This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50.
The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.
The ACTION statements provide the required operating flexibility and at the same time 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 resonably achievable" (ALARA).
The OFFSITE DOSE CALCULATION MANUAL (ODCM) calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of l
Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC l
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 I
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 Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"
Revision 1, July 1977.
These equations also provide for determining the actual doses based upon the historical average 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 l
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 l
where milk animals and meat producing animals graze with con-l sumption of the milk and meat by man, and 4) deposition on the j
ground with subsequent exposure of man.
CRYSTAL RIVER - UNIT 3 B 3/4 ll-2a
1 RADIOACTIVE EFFLUENTS BA'SES 3/4.11.3 TOTAL DOSE 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 l
is highly unlikely that the resultant dose to a MEMBER OF THE j
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 contributions 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 to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff 1
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.
1 CRYSTAL RIVER - UNIT 3 B 3/4 11-3
i
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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 j
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 i
measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.
Program changes may be initiated based on operational experience.
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.
1 3/4.12.2 LAND USE CENSUS 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 (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.
To determine this minimum garden size, the following assumptions were used:
- 1) that 20% of the garden was used for growing broad leaf vegetation (i.e.,
l similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter.
3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 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 B 3/4 12-1
I
~
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 points as well as definition of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBIC, 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.
e.
Minimum thickness of concrete floor pad = 12.5 feet.
f.
Nominal thickness of steel liner = 3/8 inches.
g.
Net free volume = 2 x 106 cubic feet.
CRYSTAL RIVER - UNIT 3 5-1
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an-ADMINISTRATIVE CONTROLS QUORUM 6.5.1.5 A quorum of the PRC shall consist of the Chairman or his designated alternate and five members including alternates.
RESPONSIBILITIES 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 j
Nuclear Plant Manager to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
c.
Review of all proposed changes to the Appendix "A" Technical Specifications.
d.
Review of all proposed changes or modifications to
~
plant systems or equipment that affect nuclear safety, i
and changes to radwaste systems which could f
significantly alter their ability to meet Appendix I.
e.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President, Nucle'ar Operations and to the Chairman of the Nuclear General Review Committee.
f.
Review of events requiring 24-hour written notification to the Commission.
g.
Review of facility operations to detect potential 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.
CRYSTAL RIVER - UNIT 3 6-6
ADMINISTRATIVE CONTROLS 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.
CRYSTAL RIVER ~ UNIT 3 6-6a
I ADMINISTRATIVE CONTROLS REVIEW (Continued) g.
Events requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
k.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
1.
The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive wastes at least once per 24 months.
1 m.
The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977, at least once per 12 months.
AUDITS 6.5.2.9 Audits of facility activities shall be performed under the cognizance of the NGRC.
These audits shall encompass:
l a.
The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance, training, and qualifications of the entire facility staff at least once per 12 months.
c.
The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months, d.
The performance of activities required by the Operational Quality Assutance Program to meet the criteria of Appendix B, 10 CFR 50, at least once per 24 months.
e.
The Facility Emergency Plan and implementing procedures at least once per 24 months.
CRYSTAL RIVER - UNIT 3 6-10
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6 ADMINISTRATIVE CONTROLS f
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 NGC or the Senior Vice President-Engineering and Construction.
AUTHORITY 6.5.2.10 The NGRC shall report to and advise the Senior Vice President-Engineering and Construction on those areas of responsibility specified in Sections 6.5.2.8 and 6.5.2.9.
RECORDS 6.5.2.11 Records of NGRC activities shall be prepared, approved, and distributed as indicated below:
a.
Minutes of each NGRC meeting shall be prepared, 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 i
the Senior Vice President-Engineering and Construction within 14 days following completion of the review.
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 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 REPO4diBLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notificati;n to the Commission shall be reviewed by the PRC and submitted to the NGRC and the Vice President, Nuclear Operations.
~
CRYSTAL RIVER - UNIT 3 6-11
O 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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.
l b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
d.
Security Plan implementation.
l e.
Emergency Plan implementation.
f.
Fire Protection Program implementation.
l g.
Systems Integrity Program implementation.
i h.
Iodine Monitoring Program implementation.
i.
PROCESS CONTROL PROGRAM implementation.
j.
OFF-SITE DOSE CALCULATIONAL MANUAL implementation.
k.
Quality Assurance Program for effluent and l
environmental monitoring using the guidance of Regulatory Guide 4.15, December 1977.
CRYSTAL RIVER - UNIT 3 6-12
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~
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, b.
For all other procedures, the review cycle shall consist of:
an intradepartmental review by a 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.
CRYSTAL RIVER - UNIT 3 6-12a m
O L
ADMINISTRATIVE CONTROLS ANNUAL AND SEMIANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as l
described below for the previous calendar year shall be submitted prior to March 1 of each year.
The initial report shall be i
submitted prior to March 1 of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include:
a
)
a.
A tabulation of the number of station, utility, and i
other personnel (including contractors) receiving l
exposures greater than 100 mrem /yr and their associated man-rem exposure according to work and job functional e.g.,
reactor operations and surveillance, l
inservice inspection, routine maintenance, special 1
maintenance (describe maintenance), waste processing, and refueling.
The dose assignments to various duty j
functions may be estimated based on pocket dosimeter, i
TLD, or film badge measurements.
Small exposures totalling less than 20 percent of the individual total dose need not be accounted for.
In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.
t 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 I
capsule shall be indicated and the irradiation location in the vessel of each capsule which was i
inserted during the report period shall be identified.
l l
c.
A routine Annual Radiological Environmental Operating Report-covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.
The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the i
radiological environmental studies, and previous Annual Radiological Environmental Operating Reports l
and an assessment of any observed impacts of the plant operation on the environment.
If harmful effects or 1
This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.
CRYSTAL RIVER - UNIT 3 6-14
~ _ _ _ _ -
I ADMINISTRATIVE CONTROLS ANNUAL AND SEMIANNUAL REPORTS (Continued) i evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of l
the problem and a planned course of action to alleviate the problem.
l l
The Annual Radiological Environmental Operating Reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975, of all radiological environmental samples taken during the report period.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing results j
shall be submitted as soon as possible in a supplementary report.
The reports shall also include the following:
a summary description of the radiological environmental monitoring program; a map of all sampling locations I
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 participation in the Interlaboratory Comparison Program, required by Specification 3.12.1.3.
d.
A semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year, l
l The Semiannual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant as outlined in Regulatory Guide 1.21, " Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix l
B thereof.
The Semiannual Radioactive Effluent Release Report which is submitted 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year.
This annual summary may be either in the form of l
CRYSTAL RIVER - UNIT 3 6-14a
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 inside the SITE BOUNDARY (Figure 5.1-3) during the report period.
All assumptions used in making these 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 effluents (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 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 individual from reactor releases (including doses from primary effluent pathways and direct radiation) for the previous calendar year.
Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1.
l The radioactive effluent release reports shall include the following information for each type of solid waste I
shipped offsite during the report period:
1 1) container volume, 2) total curie quantity (specify whether determined by measurement or estimate),
3) principal radionuclides (specify whether determined by measurement or estimate),
l l
- 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
b ADMINISTRATIVE CONTROLS ANNUAL AND SEMIANNUAL REPORTS (Continued) 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 Reports shall include a list and description of unplanned i
releases to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
The Semiannual Radioactive Effluent Release Reports 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.
i l
l CRYSTAL RIVEP. - UNIT 3 6-14c
ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted n a monthly basis to the Director, Office of Management and Program Analysis, 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 prevent recurrence, shall be reported to the NRC.
Supplemental reports may be required to fully describe final resolution i
occurrence.
In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be l
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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 license 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.
a.
Failure of.the reactor protection system or other systems subject to limiting safety-system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety-system setting in the technical specifications or failure to complete the required protective function.
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 3
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~
ADMINISTRATIVE CONTROLS d.
Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady-state conditions during power operation greater than or equal to 1%
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 unplanned reactivity insertion of more than 0.5%
Ak/k; or occurrence of any unplanned criticality.
e.
Failure or malfunction of one or more components 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.
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 that, as a direct result of the event, require plant shutdown, operation of safety systems, or other protective measures required by technical specifications, 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 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 measures to j
prevent operation in a manner less conservative 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 l
or development of an unsafe condition.
CRYSTAL RIVER - UNIT 3 6-16
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ADMINISTRATIVE CONTROLS THIRT -DAY WRITTEN REPORT 6.9.1.9 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within 30 days occtrrence of the event.
The written 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.
a.
Reactor protection system or engineered safety feature instrument settings 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.
L.
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.
e.
An unplanned offsite release of 1) more than 1 curie i
of radioactive material in liquid effluents, 2) more I
than 150 curies of noble gas in gaseous effluents, or
- 3) more than 0.05 curies of radioiodine in gaseous effluents.
The report of an unplanned offsite release of radioactive material shall include the following information:
1)
A description of the event and equipment involved.
2)
Cause(s) for the unplanned release.
3)
Actions taken to prevent recurrence.
4)
Consequences of the unplanned release.
l CRYSTAL RIVER - UNIT 3 6-17
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ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the director of the Office of Inspection and Enforcement, Region II, within the time period specified for each report.
These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
a.
ECCS Actuation, Specification 3.5.2 and 3.5.3.
b.
Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
Inoperable Meterorological Monitoring Instrumentation, c.
Specification 3.3.3.4.
d.
Seismic event analysis, Specification 4.3.3.3.2.
e.
Inoperable Fire Detection Monitoring Instrumentation, Specification 3.3.3.7.
f.
Inoperable Fire Suppression System, Specifications 3.7.11.1, 3.7.11.2, 3.7.11.3, and 3.7.11.4.
g.
Dose due to radioactive materials in liquid effluents in excess of specified limits, Specification 3.11.1.2.
h.
Dose due to noble gas in gaseous effluents in excess of specified limits, Specification 3.11.2.2.
1.
Total calculated dose due to release of radioactive effluents exceeding twice the limits of Specifications 3.11.1.2.a,.3.11.1.2.b, 3.11.2.2.a, 3.ll.2.2.b, l
3.ll.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 effluents in excess of specified limits, Specification 3.11.2.3.
k.
Failure to process liquid radwaste, in excess of limits, prior to release, Specification 3.7.13.9..
l i
1.
Failure to process gaseous radwaste, 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 l
Table 3.12-2, when averaged over any quarterly l
sampling period, Specification 3.12.1.1.
l l
CRYSTAL RIVER - UNIT 3 6-17a i
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o ADMINISTRATIVE CONTROLS
~
e.
Records of gaseous and liquid radioactive material released to the environs.
f.
Records of transient or operational cycles for those facility components identified in Table 5.7.-l.
g.
Records of training and qualification for current members of the plant staff, h.
Records of inservice inspections performed pursuant to these Technical Specifications, i.
Records of Quality Assurance activities required by the QA Manual.
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.
k.
Records of meetings of the PRC and NGRC.
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.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2) of 10 CFR 20:
a.
A High Radiation Area in which the intensity of radia-tion is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by 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 radiation dose rate in the area.
CRYSTAL RIVER - UNIT 3 6-19
o ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA (Continued) 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 i
Supervisor with one key assigned to the administrative control of Shift Supervisor on duty.
6.13 ENVIRONMENTAL QUALIFICATION 6.13.1 By no later than June 30, 1982, all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of Division of Operating Reactors
" Guidelines for Evaluating Environmental Qualification of Class 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 i
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 environmental qualification method used i
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.
j 6.14 PROCESS CONTROL PROGRAM (PCP) 6.14.1 The PCP shall be approved by the Commission prior to implementation.
6.14.2 Licensee initiated changes to the PCP:
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.
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ADMINISTRATIVE CONTROLS 6.15 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.15.1 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall be approved by the Commission prior to implementation.
6.15.2 Licensee initiated changes to the OFFSITE DOSE CALCULATION MANUAL (ODCM) :
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.
4 2.
Shall become effective upon review and acceptance by the Plant Review Committee.
6.16 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous and Solid) 1 6.16.1 Licensee initiated major changes
- to the radioactive 4
waste systems (liquid, gaseous and solid):
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 Committee or be included as part of the annual FSAR update.
2.
May be implemented upon review and acceptance by the Plant Review Committee.
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I t
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- A major change to a radioactive waste system shall be any change which would alter the ability sf the plant or system to meet the requirements of 10 CFR 50, Appendix I.
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