ML19261B353
| ML19261B353 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/13/1979 |
| From: | Stewart W FLORIDA POWER CORP. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 3--3-E, 3-0-3-E, TAC-08985, TAC-8985, NUDOCS 7902150361 | |
| Download: ML19261B353 (112) | |
Text
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W. P. STEWART. DIR ECTOR g{
POWER PRODUCTION February 13, 1979
- File:
3-0-3 e Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Crystal River Unit No. 3 Docket No. 50-302 Operating License No. DPR-72 Technical Specification Change Re ;uest
Dear Sir:
Enclosed are three (3) originals and forty (40) copies of a d: aft technical specifimation change request to Appendices A and B of Operating License No.
DPR-72 as requested in Mr. Brian K. Grimes' letters of July 11, 1978 and November
.5, 1978. As part of this request, proposed replacement pages for Appendices, and B are enclosed.
The enclosed draft of the Crystal River Unit No. 3 Technical Specifications and Offsite Dose Calculational Manual Table of Contents are based on NUREG-0472, Draf t Radiological Effluent Technical Specification for PWR's, Revision 1, October 1978. Upon final resolution of all discussions with the staf f, a Technical Specification Change Request, the Offsite Dose Calculational Manual, and the Process Control Program will be formally submitted for approval.
Please contact us as soon as possible so that timely resolution of this matter can be accomplished.
Very truly yours, FLORIDA POWER CORPORATION MS W.P.
Stewart Enclosures cc:
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 201 Marietta Street, Suite 3100 Atlanta, GA 30303 (2 copies) 7902150 30 /*.
RMBhlcF01 (2/6D24)
General Office 3201 inirty-fourth street south. P O Box 14042, Et. Petersburg, Florida 33733 813-866-5151
STATE OF FLORIDA COUNTY OF PINELLAS W.P.
Stewart states that he is the Director, Power Production, of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief.
k i
L
'ELOONd W.P. stewart Subscribed ard sworn to before me, a Notary Public in and for the State and County above named, this 13th day of February, 1979.
Y
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k/
W Notary Publip' Notary Public, State of Florida at Large, My Commission Expires: July 25, 1980
TECHNICAL SPECIFICATION CHANGE REQUEST (APPENDICES A&B)
Delete and insert the pages in Appendices A and B of Operating License DPR-72 as indicated on the attached page change list.
Proposed Change These changes will consolidate the radiological ef fluent eca environmental manitoring technical specifications that are presently in Appendix B into Appendix A as well as implementing applicable portions of 10 CFR 20; 10 CFR 50, Sections 50.34a and 50.36a; 10 CFR 50, Appendix A, General besign Criteria 60 and 64; 10 CFR 50, Appendix I; and 40 CFR 190.
Reasons for Proposed Change These changes are being proposed to provide the Commission reasonable assurance that the requirements of 10 CFR 20; 10 CFR 50, Sections 50.34a and 50.36a; 10 CFR 50, Appendix A, General Design Criteria 60 and 64; 10 CFR 50, Appendix I; and 40 CFR 190 are implemented at Crystal River Unit No.3.
Safety Analysis of Proposed Change This change will consolidate the radiological effluent and environmental monitoring programs into Appendix A as well as implement various regulations applicable to these programs.
None of the requirements applicable to the safety analysis are diminished by the proposed change and no unreviewed safety question is involved.
RMBhlcF01 (2/5D24)
Delete and/or insert, as indicated, the following pages of Appendix A and Appendix B to the Facility Operating License DPR-72.
Delete Insert Delete Insert Appendix A 3/4 11-17 3/4 11-18 I
I 3/4 11-19 IV IV 3/4 11-20 VIII VIII 3/4 12-1 XIII XIII 3/4 12-2 XVI XVI 3/4 12-3 1-6 1-6 3/4 12-4 1-7 1-7 3/4 12-5 1-8 1-8 3/4 12-6 1-9 3/4 12-7 3/4 3-16 3/4 3-16 3/4 12-8 3/4 3-23 3/4 3-23 3/4 12-8a 3/4 3-42 3/4 12-9 3/4 3-43 3/4 12-10 3/4 3-44 B 3/4 3-4 B 3/4 3-4 3/4 3-45 B 3/4 3-5 B 3/4 3-5 3/4 3-46 B 3/4 3-6 3/4 3-47 B 3/4 11-1 3/4 3-48 B 3/4 11-2 3/4 3-49 B 3/4 11-3 3/4 3-50 B 3/4 11-4 3/4 3-51 B 3/4 11-5 3/4 3-52 B 3/4 12-1 3/4 3-53 6-6 6-6 3/4 3-54 6-6a 3/4 3-55 6-10 6-10 3/4 3-56 6-11 6-11 3/4 3-57 6-12 6-12 3/4 3-58 6-15 6-15 3/4 3-59 6-16 6-16 3/4 3-60 6-17 6-17 3/4 3-61 6-18 6-18 3/4 3-62 6-19 6-19 3/4 3-63 6-20 3/4 3-64 6-21 3/4 3-65 6-22 3/4 11-1 6-23 3/4 11-2 6-24 3/4 11-3 6-25 3/4 11-4 6-26 3/4 11-5 6-27 3/4 11-6 6-28 3/4 11-7 6-29 3/4 11-8 6-30 3/4 11-9 3/4 11-10 3/4 11-11 3/4 11-12 3/4 11-13 3/4 11-14 3/4 11-15 3/4 11-16
Delete Insert Delete Insert Appendix B i
i 5-10 11 ii 5-10a iii iii 5-11 iv iv 5-12 1-1 1-1 1-3 1-3 2-4 2-4 2-5 2-6 2-7 2-8 2-9 2-10 2-11 2-12 2-13 2-14 2-15 2-16 2-17 2-18 2-19 2-20 2-21 2-22 2-23 3-6 3-8 3-9 3-10 3-1 3-12 3-13 3-14 3-15 3-16 3-17 3-18 3-19 3-20 3-21 3-22 3-23 3-2A 3-25 3-26 3-27 3-28 5-5 5-5 5-6
%6 5-7 5-7 5-8 5-8 5-9 5o
DRAFT OF CRYSTAL RIVER - UNIT 3 TECHNICAL SPECIFICATIONS BASED ON NUREG-0472, REVISION 1, OCTOBER 1978.
February 13, 1979 Changes to NUREG-0472 are delineated by a line in the right margin.
INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS DEFINED TERMS...........................................
1-1 THERMAL P0WER...........................................
1-1 RATED THERMAL P0WER.....................................
1-1 OPERATIONAL M0DE........................................
1-1 ACTI0N..................................................
1-1 OP ER ABLE - O P E R AB I L I TY..................................
1-1 REPORTABLE 0CCURRENCE...................................
1-2 CONTAINMENT INTEGRITY...................................
1-2 CH AN N E L C AL I B R AT I O N.....................................
1-2 CHANNEL CHECK...........................................
1-2 CHANNEL FUNCTIONAL TEST.................................
1-3 CO R E ALTE R AT I O N.........................................
1-3 SHUTDOWN MARGIN.........................................
1-3 I DE NTI F I ED LE AKAGE......................................
1-3 UNIDENTIFIED LEAKAGE....................................
1-4 PRESSURE BOUNDARY LE AKAGE...............................
1-4 CO NTR O L LE D LE AKAGE......................................
1-4 QUADRANT POWER TILT.....................................
1-4 DOSE EQUIVALENT I-131...................................
1-4 E-AVERAGE DISINTEGRATION ENERGY.........................
1-4 STAGGERED TEST BASIS....................................
1-5 FREQUENCY N0TATION......................................
1-5 AXIAL POWER IMBALANCE...................................
1-5 REACTOR PROTECTION SYSTEM RESPONSE TIME.................
1-5 ENGINEERED SAFETY FEATURE RESPONSE TIME.................
1-6 PHYSICS TESTS...........................................
1-6 SOURCE CHECK............................................
1-6 PROCESS CONTROL PR0 GRAM.................................
1-6 SOLIDIFICATION..........................................
1-6 0FFSITE DOSE CALCULATION MANUAL.........................
1-6 GASE0US RADWASTE TREATMENT SYSTEM.......................
1-7 OPERATIONAL MODES (TABLE 1.1)...........................
1-8 FREQUENCY NOTATION (TABLE 1.2)..........................
1-9 CRYSTAL RIVER - UNIT 3 I
INDEX LIMITING CONDITIONS FOR OPERATIGo 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 - Fg..............................
3/4 2-4 3/4.2.3 NUCLEAR ENTHALPY RISE N
HOT CHANNEL FACTOR - F g.........................
3/4 2-6 A
3/4.2.4 QU AD R AN T PO WE R T I LT................................
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 Radi ation Monitori ng Instrumentati on...............
3/4 3-22 Incore Detectors...................................
3/4 3-26 Seismic Instrumentation............................
3/4 3-28 Meteorol ogi cal Instrumentati on.....................
3/4 3-31 Remote Shutdown Instrumentation....................
3/4 3-34 Post-accident Instrumentation......................
3/4 3-37 Fi re Detecti on Instrumentation.....................
3/4 3-40 Radioactive Liquid Effluent Instrumentation........
3/4 3-42 Radioactive Gaseous Effluent Instrumentation.......
3/4 3-52 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT L00PS..............................
3/4 4-1 3/4.4.2 SAFETY VALVES - SHUTD0WN...........................
3/4 4-3 3/4 4.3 SAFETY V ALVE S - 0PE RATI NG..........................
3/4 4-4 CRYSTAL RIVER - UNIT 3 IV
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION................................
3/4 9-1 3/4.9.2 INSTRUMENTATION....................................
3/4 9-2 3/4.9.3 DECAY TIME.........................................
3/4 9-3 3/4.9.4 CONTAINMENT PENETRATIONS...........................
3/4 9-4 3/4.9.5 COMMUNICATIONS.....................................
3/4 9-5 3/4.9.6 FUEL HANDLING BRIDGE OPERABILITY...................
3/4 9-6 3/4.9.7 CRAfiE TRAVEL - SPENT FULL STORAGE P0OL BUILDING....
3/4 9-7 3/4.9.8 COOLANT CIRCULATION................................
3/4 9-8 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM.....
3/4 9-9 3/4.9.10 WATER LEVEL - REACTOR VESSEL.......................
3/4 9-10 3/4.9.11 STORAGE P00L.......................................
3/4 9-11 3/4.9.12 STORAGE P0OL VENTILATION...........................
3/4 9-12 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS........................
3/4 10-1 3/4.10.2 PHYSICS TESTS......................................
3/4 10-2 3/4.10.3 NO FLOW TESTS......................................
3/4 10-3 3/4.10.4 SHUTDOWN MARGIN....................................
3/4 10-4 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS...................................
3/4 11-1 3/4.11.2 GASE0US EFFLUENTS..................................
3/4 11-9 3/4.11.3 SOLID RADI0 ACTIVE WASTE............................
3/4 11-19 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM.................................
3/4 12-1 3/4.12.2 LAND USE CENSUS....................................
3/4 12-9 3/4.12.3 CROSSCHECK PR0 GRAM.................................
3/4 12-10 CRYSTAL RIVER - UNIT 3 VIII
INDEX BliSES SECTION PAGE 3/4.9.6 FUEL HANDLING BRIDGE OPERABILITY...................
B 3/4 9-2 3/4. 9,7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING.........
B 3/4 9-2 3/4.9.8 COOLANT CIRCULATION................................
B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM.....
B 3/4 9-2 3/4.9.10 WATER LEVEL - REACTOR VESSEL.......................
B 3/4 9-2 3/4.9.11 STORAGE P00L.......................................
B 3/4 9-2 3/4.9.12 STORAGE P0OL VENTILATION...........................
B 3/4 9-3 3f4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS........................
B 3/4 10-1 3/4.10.2 PHYSICS TESTS......................................
B 3/4 10-1 3/4.10.3 NO FLOW TESTS......................................
B 3/4 10-1 3/4.10.4 SHUTDOWN MARGIN....................................
B 3/4 10-1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQU:D EFFLUENTS..,................................
B 3/4 11-1 3/4.11.2 GASE0US EFFLUENTS..................................
B 3/4 11-2 3/4.11.3 SOLID RADI0 ACTIVE WASTE............................
B 3/4 11-5 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM.................................
B 3/4 12-1 3/4.12.2 LAND USE CENSUS....................................
B 3/4 12-1 3/4.12.3 CROSSCHECK PR0 GRAM.................................
B 3/4 12-2 CRYSTAL RIVER - UNIT 3 XIII
DEFINITIONS ENGINEERED SAFETY FEATURE RESPONSE TIME 1.25 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that 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 dis-charge 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 fundamen-tal nuclear characteristics of the reactor core and related instrumentation and 1) described ia Chapter 13 of the FSAR, 2) authorized under the provi-sions of 10 CFR 50.59, or 3) otherwise approved by ' he Commission.
SOURCE CHECK 1.27 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
PROCESS CONTP.0L PROGRAM 1.28 A PROCESS CONTROL PROGRAM (PCP) shall be the set of process control parameters within which SOLIDIFICATION of radioacti'se wastes is assured.
SOLIDIFICATION 1.29 SOLIDIFICATION shall be the conversion of radioactive liquid wastes to a unifonnly distributed, monolithic, immobilized solid with definite volume l
and shape, bounded by a stable surface of distinct outline on all sides (free-standing).
0FFSITE DOSE CALCULATION MANUAL 1.30 An 0FFSITE DOSE CALCULAION MANUAL (0DCM) shall be a manual containing the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints. Requirements of the ODCM are provided in Specification 6.14.
CRYSTAL RIVER - UNIT 3 1-6
INDEX ADMINISTRATIVE CONTROLS SECTION PAGE Meeting Frequency..................................
6-9 Quorum.............................................
6-9 Review.............................................
6-9 Audits.............................................
6-10 A ut h o r i ty..........................................
6-11 Records............................................
6-11 6.6 REPORTABLE OCCURRENCE ACTI0N.............................
6-11 6.7 SAFETY LIMIT VIOLATION...................................
6-12 6.8 PROCEDURES...............................................
6-12 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE AND REPORTABLE OCCURRENCES.................
6-13 S t a rt u p R e po rt s....................................
6-13 An n u a l R e po rt s.....................................
6-14 Annual Radiological Environmental Operating Report.
6-15 Semiannual Radioactive Effluent Release Report.....
6-15 Mont hly O pe rat i ng Repo rt...........................
6-18 Reportable Occurrences.............................
6-18 Prompt Notification with Written Followup..........
6-18 Th i rty Day Wri tten Re po rt..........................
6-20 6.9.2 SPECIAL REP 0RTS....................................
6-21 6.10 RECORD RETENTION........................................
6-23 6.11 RADIATION PROTECTION PR0 GRAM............................
6-24 6.12 H I G H R AD I AT I O N AR E A.....................................
6-24 6.13 RADWASTE SOLIDIFICATION.................................
6-25 6.14 0FFSITE DOSE CALCULATION MANUAL.........................
6-26 6.15 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS Li qui d, Gaseous, and Solid 6-27 CRYSTAL RIVER - UNIT 3 XVI
DEFINITIONS GASE0US RADWASTE TREATMENT SYSTEM 1.31 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
CRYSTAL RIVER - UNIT 3 1-7
TABLE 1.1 OPERATIONAL MODES REACTIVITY
% RATED AVERAGE COOLANT MODE CONDITION, Keff THERMAL POWER
- TEMPERATURE 1.
POWER OPERATION
> 0.99
> 5%
)280*F 2.
STARTUP
> 0.99
< 5%
> 280 F 3.
HOT STANDBY
< 0.99 0
> 280 F 4.
HOT SHUTDOWN
< 0.99 0
280 F > Tavg > 200*F 5.
COLD SHUTDOWN
< 0.99 0
< 200 F 6.
REFUE! ING**
< 0.95 0
< 140 F
- Excluding decay heat.
- Reactor vessel head unbolted or removed and fuel in the vessel.
CRYSTAL RIVER - UNIT 3 1-8
TABLE 1.2 FREQUENCY NOTtTION 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.
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.
CRYSTAL RIVER - UNIT 3 1-9
9 TABLE 3.3-6
]h RADIATION MONITORING INSTRUMENTATION x
2 MINIMUM E
CHANNELS APPLICABLE INSTRUPENT OPERABLE MODES ACTION C
1.
AREA MONITORS a.
Fuel Storage Pool Area i.
Criticality Monitor (RM-GIS) 1 14 2.
PROCESS MONITORS a.
Fuel Storage Pool Area a
i.
Gaseous Activity -
Ventilation System w
g Isolation (RM-A4G) 1 16 b.
Reactor Building i.
Gaseous Activity -
a)
Purge Exhaust Duct Isolation (RM-AIG) 1 All 17 b)
RCS Leakage Detection (RM-A6G) 1 1, 2, 3 & 4 15 ii.
Iodine / Particulate Activity -
RCS Leakage Detection (RM-A61/P) 1 1, 2, 3 & 4 15
- With fuel in the storage pool or building
- With irradiated fuel in the storage pool
- Detennined by requirements of Specification 3.3.3.9, Table 3.3-12, Item 3.a.
9 gj TABLE 3.3-4 (Cont'd) r-ENGINEERED SAFETY FEATURE ACTUATION SYSTEMS INSTRUMENTATION TRIP SETPOINTS B
r1 FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES B
Ei 3.
REACTOR BLDG. SPRAY a
a.
Reactor Bldg. Pressure u,
High-High f,30 psig f.30 psig coincident with HPI Signal See 1.a.2, 3, 4 See 1.a.2, 3, 4 b.
Automatic Actuation Logic Not Applicable Not Applicable 4.
OTHER SAFETY SYSTEMS ff a.
Reactor Bldg. Purge Exhaust Duct Isolation on High Radioactivity Y'
Gaseous (RM-AlG)
Not Applicable b.
Steam Line Rupture Matrix 1.
Low SG Pressure 2.600 psig 2,600 psig 2.
Automatic Actuation Logic Not Applicable Not Applicable
- Detennined by requirements of Specification 3.3.3.9, Table 3.3-12, Item A.1.a
INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT 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 within the specified limits.
l APPLICABILITY:
As shown in Table 3.3-12.
ACTION:
a.
With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than the specified value suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.
b.
With one or more radioactive liquid effluent monitoring instrumentation channels inoperable, take the ACTION shown in Table 3.3-12.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS I
4.3.3.8 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.
1 CRYSTAL RIVER - UNIT 3 3/4 3-42
9d TABLE 3.3-12 s{
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 2
m MINIMUM CHANNELS E
INSTRUMENT OPERABLE APPLICABILITY ACTION w
1.
Effluent Radioactivity Monitors Pi oviding Alarm and Automatic Isolation a.
Auxiliary Building Liquid 1
18 Radwaste Effluent Line (RM-L2) b.
Secondary Drain Tank Liquid 1
18
{
Radwaste Effluent Line** (RM-L7) 4' O
During releases via this pathway.
- Includes neutralized waste from secondary system condensate deep bed demineralizers and floor or waste d rai ns.
9 G
TABLE 3.3-12 (Continued)
RADIGACTIVE LIQUID EFFLUEtlT MONITORING INSTRUMENTATION iS M
7 MINIMUM CHANNELS E
INSTRUMENT OPERABLE APPLICABILITY ACTION Z
w 2.
Flow Rate Measurement Devices ***
a.
Auxiliary Building Liquid 1
20 Radwaste Effluent Line b.
Secondary Drain Tank Liquid 1
20 Radwaste Ef fluent Line c.
Turbine Building Sumps Effluent Line 1
20 3.
Radioactivity Recorders a.
Auxiliary Building Liquid 1#
22 Radwaste Effluent Line b.
Secondary Drain Tank Liquid 1#
22 Radwaste Effluent Line During releases via this pathway.
- Pump curves may be utilized to estimate flow; in such cases, Action Statement 20 is not required.
Adding ink or replacing paper when neither has been exhausted does not render the recorder inoperable.
9 d
TABLE 3.3-12 (Continued)
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION M
MINIMUM CHANNELS E
INSTRUMENT OPERABLE APPLICABILITY ACTION w
4.
Tank Level Indicating Devices a.
Borated Water Storage 1
At all times 21 Tank (DitT-1) b.
Condensate Demineralizer 1
At all times 21 Regeneration Waste Neutralization Tank (SDT-1) c.
Condensate Storage Tank (CDT-1) 1 At all times 21 b
d.
Temporary Tank (s)
I per At all times 21 tank 5.
Continuous Cor
.ite Samplers a.
Turbine Building Sumps 1
19 Effluent Line During releases via this pathway.
TABLE 3.3-12 (Continued)
TABLE NOTATION ACTION 22 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the effected pathway may continue for up to 14 days provided the gross radioactivity level is recorded at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> auring actual releases.
ACTION 23 - Deleted ACTION 24 - Deleted CRYSTAL RIVER - UNIT 3 3/4 3-47
TABLE 3.3-12 (Continued)
TABLE NOTATION ACTION 18 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be resumed for up to 14 days provided that prior to initiating a release:
1.
At least two independent samples are analyzed in accordance with Specification 4.11.1.1.3; 2.
At least two independent verifications of the release rate calculations and; 3.
At least two independent verifications of the dischargeline val vi ng; otherwise, suspend release of radioactive effluents via this pathway.
j ACTION 19 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirenient, effluent releases via this pathway may continue for up to 14 days provided that at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> grab samples are collected.
l ACTION 20 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releasts via this pathway may continue for up to 14 days provided 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.
ACTION 21 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue for up to 14 days provided the final tank l
liquid level is estimated prior to each liquid addition to the tank.
CRYSTAL RIVER - UNIT 3 3/4 3-46
9 Ci TABLE 4.3-8 5
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS r
5<
E CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL E
INSTRUfENT CHECK CHECK CALIBRATION TEST 1.
Effluent Radioactivity Monitors w
Providing Alarm and Automatic Isolation a.
Auxiliary Building Liquid D
P R(2)
Q(1)
Radwaste Effluent Line (RM-L2) b.
Secondary Drain Tank Liquid D
P R(2)
Q(1) l g
Radwaste Effluent Line (RM-L7)
?'
E
9 y
TABLE 4.3-8 (Continued)
[
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS M
CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL E
INSTRUMENT CHECK CHECK CALIBRATION TEST a
w 2.
Flow Rate Measurement Devices a.
Auxiliary Building Liquid D*
N/A R
Q Radwaste Ef fluent Line b.
Secondary Drain Tank Liquid D*
N/A R
Q Radwaste Effluent Line R
c.
Turbine Building Sumps D*
N/A R
Q Effluent Line 3.
Radioactivity Recorders a.
Auxiliary Building Liquid D
N/A R
Q Radwaste Effluent Line b.
Secondary Drain Tank Liquid D
N/A R
Q Radwaste Effluent Line
9g TABLE 4.3-8 (Continued) 5 r
RAri10 ACTIVE LIQUID EFFLUENT MONITORING INSTRUENTATION SURVEILLANCE REQUIREENTS M
CNANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL E
INSTRUENT CHECK CHECK CALIBRATION TEST q
4.
Tank Level Monitors w
a.
Borated Water Storage Tank D
N/A R
Q (DHT-1) b.
Condensate Demineralizer D
N/A R
Q Regeneration Waste Neutralization Tank (SDT-1)
R c.
Condensate Storage Tank (CDT-1) D N/A R
Q V'
8 d.
Temporary Tank (s)
D N/A R
Q 5.
Continuous Caposite Samplers a.
Turbine Building Sumps Effluent Line D
N/A N/A Q
l
TABLE 4.3-8 (Continued)
TABLE NOTATION
- - During releases via this pathway.
(1) - The CHANNEL FUNCTION TEST shall also demonstrate that automatic isola-tion of this pathway and control room alarm annunciation occurs if any of the following conditions exist:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode.
(2) - The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed us'.1g one or more standards calibrated to o National Bureau d _cr dards source. For subsequent CHANNEL CALIBRATION, sources '.iat have o ren related to the initial calibration should be usv. at intervalo of at least once per eighteen months.
This can norma' se accomplished during refueling outages.
CRYSTAL RIVER - UNIT 3 3/4 3-51
INSTRUMENTATION RADI0 ACTIVE GASEOUS PROCESS AND EFFLUENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints within the specified limits.
I APPLICABILITY:
As shown in Table 3.3-13.
ACTION:
a.
With a radioactive gaseous process or effluent monitoring instrumentation channel alarm / trip setpoint less conservative than the specified limit, suspend the release of radioactive gaseoi's effluent monitored by the affected channel or declare the cha.;el inoperable.
b.
With one or more radioactive gaseous process or effluent monitoring instrumentation channels inoperable, take the ACTION shown in Table 3.3-13.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous process and effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9.
CRYSTAL RIVER - UNIT 3 3/4 3-52
9 TABLE 3.3-13 7,
5 F
RADI0 ACTIVE GASE0US PROCESS AND EFFLUENT MONITORING INSTRUMENTATION 5s MINIMUM CHANNELS E
INSTRUMENT OPERABLE APPLICABIL;TY-ACTION a
u A.
Effluent Radioactivity Monitors Providing Alam and Automatic Termination of Release 1.
Containment Purge Monitoring System (RM-A1) a.
Noble Gas Activity 28 Monitor 1
{
b.
Iodine Sampler Cartridge 1
33 33 c.
Particulate Sample Filter 1
d.
Eff'.ent System Flow Rate 1#
32 Measuring / Recording Device e.
Sample Flow Rate Measuring Devices
- i. Rotometer 1
28 ii. Vacuum Gauge 1
32 iii. High Flow Alam/ Trip 1
28 iv. Low Flow Alam 1
28 NobleGabActivityRecorder 1#
31 f.
g.
Purge Supply System Flow Rate Measuring / Recording Device 1#
32
TABLE 3.3-13 (Continued)
RADI0 ACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION 5
MINIMUM x
CHANNELS INSTRUMENs OPERABLE APPLICABILITY ACTION C
3 2.
Auxiliary Building Ventilation System (RM-A2) m a.
Noble Gas Activity Monitor 1
27 b.
Iodine Sampler Cartridge 1
33 c.
Particulate Sample Filter 1
33 w
d.
Effluent System Flow Rate 1#
32 Measuring / Recording C ice e.
Sample Flow Rate Measuring Device 1.
Rotometer 1
30
- 11. Vacuum Gauge 1
32 iii.
High Flow Alann/ Trip 1
26 iv. Low Flow Alann 1
26 f.
Noble Gas Activity Recorder 1#
31
9d TABLE 3.3-13 (Continued)
F RADI0 ACTIVE GASE0US PROCESS AND EFFLUENT MONITORING INSTRUMENTATION M
MINIMUM CHANNELS E
INSi. :lMENT
~f,el:F ?LE APPLICABILITY ACTION Z
B.
Process Radioactivity Monitors Providing Alann and Automatic Actuation w
1.
Waste Gas Decay Tank Release System (RM-All) a.
Noble Gas Activity Monitor 1
25 b.
Effluent System Flow Rate 1
28 Measuring Device c.
Noble Gas Activity Recorder 1
31
{
(WD-19-FR) m d.
Effluent System Flow Rate 1
26 Recorder
n Q
TABLE 3.3-13 (Continued)
E RADI0AC' 7E GASE0US PROCESS AND EFFLUENT MONITORING INSTRUMENTATION 5
M MINIMUM CllANNELS g
INSTRUMENT OPERABLE APPLICABILITY ACTION
[
C.
Process Radioactivity Monitors Providing Alann 1.
Condenser Vacuum Pump Exhaust (RM-A12) a.
Noble Gas Activity Monitor 1
27 b.
Sampler Flow Rate Measuring Device 1 30 c.
Noble Gas Activity Recorder 1#
31 y
2.
Waste Gas lloldup System Explosive g
Gas Monitoring System a.
Oxygen Monitor (Periodic) 1 During times when 29 there is a potential for hydrogen input to the waste gas holdup system.
DELETED CRYSTAL RIVER - UNIT 3 3/4 3-57
TABLE 3.3-13 (Crntinued)
TABLE NOTATION During releases via this pathway
- During Condenser Vacuum Pump System operation
- Adding ink or replacing paper when neither is exhausted does not render the recorder inoperable.
ACTION 25 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank may be released to the environment for up to 14 days provided that prior to initiating the release:
1.
At least two independent samples of the tank's content are
- analyzed, 2.
At least two independent verifications of the release rate calculations, 3.
At least two independent verifications of the discharge line valving, and 4.
RM-A2 is OPERABLE; otherwise, suspend release of radioactive effluents via this pathway.
ACTION 26 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days provided the flow rate is estimated / recorded at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during actual releases.
ACTION 27 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, process flow / effluent releases via this pathway may continue for up to 28 days provided grab samples are taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and these samples are analyzed for gross activity.
ACTION 28 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, suspend release of radio-active effluents via this pathway.
ACTION 29 - With the oxygen monitor not OPERABLE, restore the monitor to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, process flow / effluent releases via this pathway may continue for up to 28 days, provided samples CRYSTAL RIVER - UNIT 3 3/4 3-58
TABLE 3.3-13 (Continued)
TABLE NOTATION are continuously collected with auxiliary sampling equipment.
ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, process flow / effluent releases via this pathway may continue for up to 28 days provided the radioactivity is recorded at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during actual releases.
i ACTION 32 - With the number of channels OPERABLE less than required by the i
Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days provided the flow rate is estimated / recorded 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 actual releases.
l ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, replace the required sampling medium.
CRYSTAL RIVER - UNIT 3 3/4 3-59
9 TABLE 4.3-9 h
P RADI0 ACTIVE GASE0US PROCESS AND EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREME 2
m" CH/'4NEL CHANNEL SOURCE CHAflNEL FUNCTIONAL sg INSTRUMENT CHECK CHECK CALIBRATION TEST
=
a w
A.
Effluent Radioactivity Monitors Providing Alann and Automatic Termination of Release 1.
Containment Purge ffonitor System (RM-A1) a.
Noble Gas Activity Monitor D*
P P,{3 )
Q(1) b.
Iodine Sampler Cartridge W*
N/A N/A N/A c.
Particulate Sample Filter W*
N/A N/A N/A d.
Effluent System Flow D*
N/A R
Q
[
Rate Measuring / Recording Devices o
Sampler Flow Rate Measuring Devices e.
- i. Rotometer D*
N/A N/A N/A ii. Vacuum Gauge D*
N/A R
N/A iii. High Flow Alann/ Trip D*
N/A R
Q iv. Low Flow Alann D*
N/A R
Q g.
Noble Gas Activity Recorder D*
N/A R
Q f.
Purge Supply System Flow Rate D*
N/A 1
Q Measuring / Recording Device
TABLE 4.3-9 (Continued) 9 RADI0 ACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL 0
CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST
[
2.
Auxfliary Building Ventilation System (RM-A2) 5 a
a.
Noble Gas Activity Monitor D*
M R(3)
Q(1) w b.
Iodine Sampler Cartridge W*
N/A H/A N/A c.
Particuiate Sample Filter W*
N/A N/A N/A d.
Effluent System Flow Rate D*
N/A R
Q Measuring / Recording Device e.
Sampler Flow Rate Measuring Devices
- i. Rotometer D*
N/A N/A N/A fi.
Vacuum Gauge D*
N/A R
N/A iii. High Flow Alarm / Trio D*
N/A R
Q iv.
Low Flow Alann D*
N/A R
Q f.
Noble Gas Activity Recorder D*
N/A R
Q
TABLE 4.3-9 (Continuedl RADI0 ACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CilANNEL n"
CilANNEL SOURCE CilANNEL FUNCTIONAL INSTRUMENT CHECK CilECK CALIBRATION TEST x
B.
Process Radioacti ity Monitors Providing Alann and Automatic Actuation h
1.
Waste Gas Decay Tank Release System (RM-All) i a.
Noble Gas Activity Monitor D*
P R(3)
Q(1) b.
Effluent System F1ow D*
N/A R
Q Rate Measuring Device c
Not'le Gas Activity Recorder D*
N/A R
Q (WD-19-FR) d.
Effluent System Flow D*
N/A R
Q w
Rate Recorder 1
W
9 gj TABLE 4.3-9 (Continued) 5 r-RADI0 ACTIVE GASE0US PROCESS AND EFFLUENT MONITORING INSTRUMENTATIDN SU B
~~
M CHANNEL SOURCE CHANN INSTRUMENT CHECK CHECK CALIBRA E
- 1 C.
Process Radioactivity Monitors Providing Alarm w
1.
Condenser Vacuum Pump Exhaust (RM-A12) a.
Noble Gas Activity Monitor D**
M R(3) b.
Sampler Flow Rate Measuring Device D**
N/A R
c.
Noble Gas Activity Recorder D**
N/A R
2.
Waste Gas Holdup System Explosive Gas
{'
Monitoring system w
a.
Oxygen Monitor (Periodic)
D N/A Q(4)
DELETED CRYSTAL RIVER - UNIT 3 3/4 3-64
TABLE 4.3-9 (Continued)
TABLE NOTATION
- - During releases via this pathway.
j
- - During Condenser Vacuum Pump System operation (1) - The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alam annunciation occurs if any of the following conditions exist:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode.
(2) - The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alam annunciation occurs if any of the following conditions exist:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode.
(3) - The initial CHANNEL CALIBRATION for radioactivity measument instrumentation shall be performed using one or more standards calibrated to a Naticanal Bureau of Standards source.
For subseq.7nt i
CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at intervals of at least once per eighteen months. This can normally be accomplished during refueling outages.
(4) - The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
1.
One volume percent oxygen, balance nitrogen, and 2.
Four volume percent oxygen, balance nitrogen.
CRYSTAL RIVER - UNIT 3 3/4 3-65
3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released at any time from the site to unrestricted areas (See Figure 3.11-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained nobles gases, ghe maximum permissible l
concentration shall be limited to 2 x 10- uCi/ml.
APPLICABILITY:
At all times.
ACTION:
a.
With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits, restore I
the concentration to within the above limits and provide prompt notification to the Commission pursuant to Specification 6.9.1.12.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.1.1 The concentration of radioactive material at any time in liquid effluents released from the site shall be continuously monitored in accordance with Table 3.3-12.
4.11.1.1.2 The liquid effluent continuous monitors having. provisions for automatic tennination of liquid releases, as listed in Table 3.3-12, shall be used to limit the concentration of radioactive material released at any time from the site to unrestricted areas to the values given in Specification 3.11.1.1.
4.11.1.1.3 The radioactivity content of each batch of radioactive liquid waste to be discharged shall be determined prior to release by sampling and analysis in accordance with Table 4.11-1.
- CRYSTAL RIVER - UNIT 3 3/4 11-1
RADI0 ACTIVE EFFLUENTS (cont'd)
SURVEILLANCE REQUIREMENTS 4.11.1.1.4 Post-release analyses of samples composited from batch releases shall be performed in accordance with Table 4.11.1.
4.11.1.1.5 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 4.11-1.
CRYSTAL RIVER - UNIT 3 3/4 11-2
TABLE 4.11-1 RADI0 ACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM (To Be Completed)
CRYSTAL RIVER - UNIT 3 3/4 11-3
TABLE 4.11-1 (Continued)
TABLE NOTATION (To Be Completed)
CRYST-, RIVER - UNIT 3 3/4 11-4
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RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas (see Figure 3.11-1) shall be limited during any calendar quarter to i 1.5 mrem to the total body and to i 5 mrem to any organ.
l APPLICABILITY:
At all times.
ACTION:
a.
With the calculated dose from the release of radioactive materials in liquid effluents exceeding the above limit, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the remainder nf the calendar year so that the average dose or dose commitment to an individual from such releases during the calendar year is i 3 mrem to the total body and i 10 mrem to any organ.
b.
The provisions of Specifictions 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once per month.
CRYSTAL RIVER - UNIT 3 3/4 11-6
RADI0 ACTIVE EFFLUENTS LIQUID WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.S The liquid radwaste treatment system shall be OPERABLE.
The appropriate subsystems shall be used to reduce the radioactive materials in liquid waste prior to their discharge when the projected doses due to the liquid effluent releases to unrestricted areas (see Figure 3.11-1) when averaged over 31 days, exceed 0.3 mrem to the total body or 0.8 mrem to any l
organ.
APPLICABILITY:
At all times.
ACTION:
a.
With either the licuid radwaste system not OPERABLE for more than i
31 days; or radioactive liquid waste being discharged without treatment and in excess of the above limits; in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2 a Special Report which includes the following information:
1.
Identification of the equipment or subsystems not OPERABLE and the reason for inoperability.
2.
Action (s) taken to restore the inopera' ole equipaent to OPERABLE status.
3.
Summary description of action (s) taken to prevent a recurrence.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases to unrestricted areas shall be projected monthly for at least 31 days.
4.11.1.3.2 The liquid radwaste treatment system shall be demonstrated OPERABLE at least once per quarter unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous quarter.
CRYSTAL RIVER - UNIT 3 3/4 11-7
RADI0 ACTIVE EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material excluding tritium and dissolved or entrained noble gases contained in each of the following tanks shall be limited as follows:
i TANK LIMIT (Curies) a.
Borated Water Storage Tank (DHT-1)
(10) b.
Condensate Demineralizer Regeneration (10) l Waste Neutralization Tank (SDT-1) c.
Condensate Storage Tank (CDT-1)
(10) d.
Temporary Tank (s) 10 per tank APPLICABILITY: At all times.
ACTION:
a.
With the quantity of radioactive material in any of the above listed tanks exceeding its limit, either reduce the tank contents to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or provide prompt notification to the Commission pursuant to Specification 6.9.1.12.
The written followup report shall include a schedule and description of activities planned and/or taken to reduce the tank contents to i
within the above limit.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not appli-cable.
SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within its limit by analyzing a representative sample of the tank's contents at least once per week.
CRYSTAL RIVER - UNIT 3 3/4 11-8
RADI0 ACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION F0k OPERATION 3.11.2.1 The dose rate, at any time, in the unrestricted areas (see Figure-5.1-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:
a.
The dose rate limit for noble gases shall be 1500 mrem /yr to the total body and i 3000 mrem /yr to the skin, and b.
The dose rate limit for all radiciodines and for all radioactive materials in particulate form and radionuclides other than noble gases with half lives greater than 8 days shall be i 1500 mrem /yr to any orgen.
APPLICABILITY:
At all times.
ACTION:
a.
With the dose rate (s) exceeding the above limits, decrease the re-lease rate to within its limit and provide prompt notification to the Commission pursuant to Specification 6.9.1.12.
b.
The provisions of Specification 3.0.3 and 3.0.4 are not applic-f able.
l SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The release rate, at any time, of noble gases in gaseous effluents shall be controlled by the offsite dose rate as established above in Specification 3.11.2.1.
4.11.2.1.2 The noble gas effluent continuous monitors having provisions for the automatic termination of gaseous releases, as listed in Table 3.3-12, shall be used to limit offsite doses when monitor setpoint values are exceeded.
4.11.2.1.3 The release rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 4.11-2.
4.11.2.1.4 The dose rate in unrestricted areas, due to radioactive materi-als other than noble gases released in gaseous effluents, shall be deter-mined to be within the required limits by using the results of the sampling and analysis program, specified in Table 4.11-2, with the calculational methods in the ODCM, in performing the calculations of dose rate in unre-stricted areas.
CRYSTAL RIVER - UNIT 3 3/4 11-9
9 TABLE 4.11-2 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM M
(To Be Completed)
Eq w
N4 b
I TABLE 4.11-2 (Continued) e r
RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM B
(To Be Completed)
E w
N 4
w b'
TABLE 4.11-2 (Continued)
(To Be Completed)
CRYSTAL RIVER - UNIT 3 3/4 11-12
RADI0 ACTIVE EFFLUENTS DOSE, N0BLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose in unrestricted areas (see Figure 5.1-1) due to noble gases released in gaseous effluents shall be limited during any calendar quarter, to i 5 mrad for gamma radiation and i 10 mrad for beta radiation.
l APPLICABILITY: At all times.
ACTION:
a.
With the calculated air dose from radioactive noble gases in gas-eous effluents exceeding the above limit, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainoer of the current calendar quarter and during the remainder of the calendar year so that the average dose during the calendar year is within 10 mrad for gamma radiation l
and 20 mrad for beta radiation.
1 b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the total time period shall be determined in accordance with the ODCM at least once per month.
CRYSTAL RIVER - UNIT 3 3/4 11-13
RADI0 ACTIVE EFFLUENTS DOSE, RADIOI0 DINES, RADI0ACTIVt MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents released to unrestricted areas (see Figure 5.1-1) shall be limited during any calendar quarter to 1 7.5 mrem to any organ.
APPLICABILITY:
At all times.
ACTION:
a.
With the calculated dose from the release of radioiodines, radio-active materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding the above limit, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases of radiciodines, radio-active materials in particulate form, and radionuclides other than noble gases in gaseous effluents during the remainder of the I
current calendar quarter and during the remainder of the calendar year so that the average dose or dose commitment to an individual from such releases during the calendar year is within 15 mrem to any organ.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the total time period shall be determined in accordance with the ODCM at least once per month.
CRYSTAL RIVER - UNIT 3 3/4 11-14
RADI0 ACTIVE EFFLUENTS GASE0US WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be OPERABLE. The I
appropriate subsystems shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases to unrestricted areas (see Figure 5.1-1) when averaged over 31 days would exceed 0.8 mrad for gamma radiation and 1.7 mrad for beta radiation.
APPLICABILITY:
At all times.
ACTION:
a.
With gaseous waste being discharged for more than 31 days without treatment and in excess of the above limits, in lieu of any other i
report required by Specification 6.9.1, prepare and submit to the I
Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following infonnation:
1.
Identification of the equipment or subsystems not OPERABLE and the ree n for inoperability.
2.
Action (C sen to restore the inoperable equipment to OPERABLE s. aus.
3.
Sumary description of action (s) taken to prevent a recurrence.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVFILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases to unrestricted areas shall be projected monthly for at least 31 days.
4.11.2.4.2 The GASE0US RADWASTE TREATMENT SYSTEM shall be demonstrated OPERABLE at lease once per quarter unless the gaseous radwaste treatment system has been utilized to process radioactive gaseous effluents during the previous quarter.
CRYSTAL RIVER - UNIT 3 3/4 11-15
RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.2.5 The calculated dose from the release of radioactive materials in liquid or gaseous ef fluents shall not exceed twice the limits of i
Specifications 3.11.1.2., 3.11.2.2., or 3.11.2.3.
APPLICABILITY:
At all times.
ACTION:
a.
With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.11.1.2., 3.11.2.2. or 3.11.2.3., prepare and submit a Special Report to the Commission, pursuant to Specification 6.9.2, and limit the subsequent releases such that tie dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to 125 mrem to the total body or any organ (except thyroid, which is limited to 175 mrem) over the current calendar year. This Special Report shall include an analysis which demonstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise, obtain a variance from the Commission to permit releases which exceeds the 40 CFR Part 190 Standard.
b.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.5 No additional Surveillance Requirements other than those requir-d by Specifications 3.11.1.2., 3.11.2.2. and 3.11.2.3.
j i
i CRYSTAL RIVER - UNIT 3 3/4 11-16
RADI0 ACTIVE EFFLUENTS EXPLQSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of oxygen in the waste gas holdup system shall be limited to 1 2% by volume.
APPLICABILITY:
During times when there is a potential for hydrogen input to the waste gas holdcp system.
ACTION:
a.
With the concentration of oxygen in the waste gas holdup system
> 2% by volume, restore the concentration of oxygen to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of oxygen in the este gas holdup syska shall be determined to be within the above limits by monitoring the waste gases in the waste gas holdup system with the oxygen monitor required OPERABLE by Table 3.3-13 of Specification 3.3.3.9.
CRYSTAL RIVER - UNIT 3 3/4 11-17
RADI0 ACTIVE EFFLUENTS WASTE GAS DECAY TANKS LIMITING CONDITION FOR OPERATION 3.11.2.7 The quantity of radioactivity contained in each waste gas decay tank shall be limited to 1 (47,000) Curies noble gases (considered as Xe-133).
APPLICABILITY:
At all times.
ACTION:
a.
With the quantity of radioactive material in any waste gas decay tank exceeding the above limit, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> either reduce the tank contents to within the limit or provide prompt notification to the Commission pursuant to Specification 6.9.1.12. The written followup report shall include a description of activities planned and/or taken to reduce the tank contents to within the above limit.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.7 The quantity of radioactive material contained in each waste gas decay tank shalI be determined to be within the above limit at least once per day when radioactive materials are being added to the tank.
CRYSTAL RIVER - UNIT 3 3/4 11-18
RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RADI0 ACTIVE WASTE LIMITING CONDITION FOR OPERATION I
3.11.3.1 The solid radwaste system shall be OPERABLE and used to provide for the SOLIDIFICATION of:
l a.
Liquid radioactive wastes, filter sludges which are 10.003 pCi/gm and spent resins which are 1 0.003 pCi/gm.
b.
Any other radioactive waste that may be solidified.
APPLICABILITY:
At all times.
ACTION:
I a.
With the PROCESS CONTROL PROGRAM not satisfied, ensure the meet-ing of the requirements of 10 CFR Part 20 and 10 CFR Part 71 prior to shipment of defective containers of radioactive wastes from the site.
b.
With the solid radwaste system not OPERABLE for more than 31 days when required to meet 10 CFR Part 20 and 10 CFR Part 71, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specifi-cation 6.9.2, a Special Report which includes the following in-formation:
1.
Identification of the equipment or subsystems not CPERABLE and the reasons for inoperability, 2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, 3._
A description of alternative used for SOLIDIFICATION and Packaging of wastes, 4.
Summary description of action (s) taken to prevent a recur-rence.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applica-ble.
SURVEILLANCE REQUIREMENTS 4.11.3.1.1 The solid radwaste system shall be demonstrated OPERABLE at least once per quarter, or there be the capability for 50cIDIFICATION of waste by meeting one of the following conditions:
CRYSTAL RIVER - UNIT 3 3/4 11-19
RADI0 ACTIVE EFFLUENTS SURVEILLANCE REQUIREMENTS (Continued) a.
By performance of functional tests of the equipment and components of the solid radwaste system.
b.
By operating the sc '( radwaste system at least once in the previous quarter in accordance with the PROCESS CONTROL PROGRAM.
c.
Verification of the existence of a valid contract for SOLIDIFICATION to be perfomed in accordance with a PROCESS CONTROL PROGRAM.
4.11.3.1.2 The SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of radioactive waste shall be verified.
a.
If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION.
SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM. Additionally, the Radwaste Solidificatim Pr, ram shall provide for the collection and testing of represent.o ive test specimens from each consecutive batch of the same type of waste until 3 consecutive initial test specimens demonstrate SOLIDIFICATION.
The PROCESS CONTROL PROGRAM shall be moJified as required to assure SOLIDIFICATION of subsequent batches of waste.
CRYSTAL RIVER - UNIT 3 3/4 11-20
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be con-ducted as specified in Table 3.12-1.
APPLICABILITY:
At a'l times.
ACTION:
a.
With the radiological environmental monitoring program not being conductr ' as specified in Table 3.12-1, prepare and submit to the Comv n, in the Annual Radiological Environmental Operating Rep '., a description of the reasor-for not conducting the pro-gr ~ as required and the plans for preventing a recurrence.
I./iations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, vandalism, seasonal unavailability, or to malfunction of automatic sampling equipment.
If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period.)
b.
With the level of radioactivity in an environmental sampling medium at one or more of the locations specified in Table 3.12-1 exceeding the limits of Table 6.9-2 when averaged over any calen-dar quarter, in lieu of any other report required by Specification 6.3.1, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, pursuant to Specification 6.9.2, a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Table 6.9-2 to be exceeded. 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.
With milk or fresh leafy vegetable samples permanently unavail-c.
able from any of the sample locations required by Table 3.12-1, delete the locations from Table 3.12-1 and Figure 3.12-1 or 3.12-2, add the locations from which replacement samples were obtained to the radiological environmental monitoring program as replacement locations and report and describe the replacement in i
the Annual Radiological Environmental Operating Report.
d.
The provisions of Specifications 3.0.3 and 3.0.4 are not appli-cable.
CRYSTAL RIVER - UNIT 3 3/4 12-1
RADIOLOGICAL ENVIRONMENTAL MONITORING SURVEILL;i!CE REQUIREMENTS 4.12.1.
The radiological environmental monitoring samples shall be col-lected pursuant to the Table 3.12-1 from the locations shown on Figures 3.12-1 and 3.12-2 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
TABLE 3.12-1 RADIOLOGICAL ENVIRONMEdTAL MONITORING PROGRAM Exposure Pathway Number of Samples /
Sampling / Collection Type / Frequency and/or Sample Sample Locations
- Frequency of Analysis 1.
AIRBORNE
- a. Radiciodine One sample at each Continuous / W Radiciodine Canister:
and Partic-location / C04, C07, Analyze for I-131/ W ulates C18, C26, C40, C41, C46, C47 Particulate sampler:
Analyze for gross beta radioactivity / each filter > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> followilig filter change; perform gamma isotopic analysis /
each sample when gross beta activity is > 10 times the mean of control samples; perfom gamma isotopic analysis on composite (by location) sample / Q.
2.
DIRECT
> 2 dosimeters for Continuous / Q Gama dose / Q RADIATION measuring dose at each location /
C04, C07, C09, C14H, C14M, C14G, C43, C46, C47
- Sample locations are shown on Figure 3.12-1 or Figure 3.12-2.
CRYSTAL RIVER - UNIT 3 3/4 12-3
TABLE 3.12-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples /
Sampling / Collection Type / Frequency and/or Sample Sample Locations
- Frequency of Analysis 3.
WATERBORNE
- a. Surface One sample at each M
Gamma isotopic location / C13, C14G analysis / each sample; Tritium analysis of composite (by location)/ Q
- b. Ground One sample / C40.
SA Gamma isotopic and tritium analyses / each sampl e.
- c. Drinking One sample at each Q
Gamma isotopic and location / C07, C10, tritium analyses / each C18.
sample.
- d. Sediment One sample at each SA Gamma isotopic from shore-location / C14G analysis / each sample.
line
- 4. INGESTION
- a. Milk One sample at each M
Gamma isotopic and location / C49 I-131 analyses / each sample.
- b. Fish and One sample at each One sample in season Gamma isotopic analysis Inverte-location / C29, C30.
or SA of each of the on edible portions /
brates following types:
each sample.
1.
Carnivorous fish 2.
Oysters
- c. Food Prod-One sample at each SA of Vegetation Gamma isotopic ucts location /C40, C05 (grasses) analysis /each sample One sample /C19 A or at harvest of Gamma isotopic analysis /each sample One sample /C04 A or at harvest of Gamma isotopic watermelon analysis /each sample One sample at each SA of Green Leafy Gamma isotopic location /C47, C48 Vegetables analysis /each sample
- Sample locations are shown on Figure 3.12.1 or Figure 3.12.2 CRYSTAL RIVER - UNIT 3 3/4 12-4
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9y TABLE 4.12-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a M
Airborne Particulate Water or Gasgs Fish Milk Food Products Sediment E
Analysis (ECi/t)
(pCi/m3)
(pCi/kg, wet)
(pCi/t)
(pCi/kg, wet)
(pCi/kg, dry)
I gross beta 0.03 w
H-3 2000 Mn-54 15 130 Fe-59 30 260
{
Co-58 15 130 y
Co-60 15 130 Zn-65 30 260 Zr-Nb-95**
20 I-131 10(1*)
0.0 '
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50 40 For potable water
- LLD is total for parent and progeny
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 only 5% proba-bility of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66sb LLD =
E V
2.22 Y
exp(-Aat) where LLD is the lower limit of detection as defined above (as pCi 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 transformation)
V is the sample size (in units of mass or volume) 2.22 is the number of transformation per minute per picocurie Y is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radio-nuclide at is the elapsed time between sample collection (or end of the sample collection period) and time of counting (only for environ-mental samples).
The value of sb used in the calculation of the LLD for a detection sys-tem shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appro-priate) rather than on an unverified theoretically predicted variance.
In calculating the LLD for a radionuclide determined by gamma-ray spec-trometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples).
Typical values of E, V, Y and at should be used in I
the calculations.
It should be recognized that the LLD is defined as an a priori (before l
the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.
l CRYSTAL RIVER - UNIT 3 3/4 12-8
TABLE 4.12-1 (Continued)
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.
Occasionally background fluctu-ations, unavoidably small sample sizes, the presence of interferring nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors will be identi-fied and described in the Annual Radiological Environmental Operating Report.
LLD for leafy vegetables.
b CRYSTAL RIVER UNIT 3 3/4 12-8a
RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify the loca-tion of the nearest milk animal, the nearest residence and the nearest gar-den
- of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.
APPLICABILITY:
At all times.
ACTION _:
With a land use census identifying a lomation(s) which yields a a.
calculated dose or dose commitment greater than the values cur-rently being calculated in Specification 4.11.2.3, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the new location (s).
b.
With a land use census identifying a location (s) which yields a calculated dose or commitment (via the same exposure pathway) greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1 add the new loca-tion to the radiological environmental monitoring program within 30 days if possible. The sampling location having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after the March 31 subsequent to the land use census, The provisions of Specifications 3.0.3 and 3.0.4 are not appli-c.
cabl e.
SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted at least once per 12 months between the dates of November 1, and March 1 by a door-to-door survey, aerial survey, consulting local agriculture authorities, or any combination of these methods.
- Broad leaf vegetation sampling may be perfonned 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 12-9
RADIOLOGIC /,L ENVIRONMENTAL MONITORING 3/4.12.3 CROSSCHECK PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by NRC.
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 Commis-sion in the Annual Radiological Environmental Operating Report.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not appli-cable.
SURVEILLANCE REQUIREMENTS 4.12.3 No additional Surveillance Requirements other than those required by the Interlaboratory Comparison Program.
CRYSTAL RIVER - UNIT 3 3/4 12-10
INSTRUMENTATION BASES 3/4.3.3.8 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the 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.
3/4.3.3.9 RADI0 ACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumenation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluants. The alarm / trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring the cor.centrations of potentially l
explosive gas mixtures in the waste gas decay tank release system. The OPERABILITY and use of this instrumentation is consistent wih the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
CRYSTAL RIVER - UNIT 3 B 3/4 3-4
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N CRYSTAL RIVER - UNIT 3 8 3/4 3-6
3/4.11 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radioac-tive materials released in liquid waste effluents from the site to unre-stricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II.
This limitation provides additional assurance that the levels of radioactive materials in bodies of water out-side the site will not result in exposures within (1) the Section II.A de-sigo objeetives of Appendix I,10 CFR Part 50, to an individual and (2) the limits of 10 CFR Part 20.106(e) to the population. The concentration limit for 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 usir- & methods decribed in International Commis-sion on Radiological Prote : tion (ICRF; Publication 2.
3/4.11y.2 DOSE This specification is proiided to implement the requirements of Section IV.A of Appendix I, 10 CFR Part 50.
The Limiting Condition for Operation imrf ements the guides set forth in Section IV.A of Appendix I.The ACTION statement provides the required operating flexibility set forth in Section IV.A of Appendix I to asture that the releases of radioactive material in liquid effluents will bel.ept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conforma 1ce with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individuni through appropriate pathways is unlikely to be substantially underestiFated.
The equations specified in the ODCM for calculating the dose due to the actual release rates of radioactive materials. in liquid eff uents will be consistent with the methodology provided in Regulatory iuide 1.109, " Calculation of Annual Doses to Man from Routine Releases cf 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," Revision 1, April 1977.
NUREG-0133, October 1978, provides methods for dose calculations consistent with Regulatory Guides 1.109, Revision 1, October 1977 and 1.113, Revision 1, April 1977.
The site specific applicable factor for the mixing effect of the discharge structure is 1.0.
CRYSTAL RIVER - UNIT 3 B 3/4 11-1
RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1.3 LIQUID WASTE TREATMENT The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This specification implements the require-ments of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective Section 11.0 of Appendix I to 10 CFR l
Part 50. The specified limits governing the use of appropriate portions of the liquid raddaste treatment system were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I,10 CFR Part 50, for liquid effluents.
3/4.11.1.4 LIQUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting dose or dose commitment to an individual in an unrestricted area will not exceed 0.5 rem.
3/4.11.2 GASE0US EFFLUENTS 3/4.11.2.1 DOSE This specification is provided to ensure that the dose at any time at the exclusion area boundary from gaseous effluents from the unit will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas.
The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II. These limits provide reasonable assurance that radioactive materials discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area either within or outside the exclusion area 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)).The specified release rate limits restrict, at all times, the corresponding gamma and beta dose CRYSTAL RIVER - UNIT 3 8 3/4 11-2
RADI0 ACTIVE EFFLUENTS BASES rates above background to an individual at or beyond the exclusion boundary to i 500 mrem / year to the total body or to 13000 mrem / year to the skin.
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to i 1500 mrem / year for the nearest cow to the plant.
3/4.11.2.2 DOSE, N0BLE GASES This specification is provided to implement the requirements of Section IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section IV.A of Appendix 1.The ACTION statements provide the required operating flexibility 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 reasonbly achievable." The Surveillance Requirements implement the requirements in Section IV.B of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models. and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents were developedfrom the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors,"
Revision 1, July 1977.
The ODCMequations provided for determining the air doses at the exclusion area boundary based upon the historical average atmospheric conditions.
NUREG-0133, October 1978, provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.
3/4.11.2.3. DOSE, RADIOI0 DINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLlDES OTHER THAN NOBLE GASES This specification is provided to implement the requirements of Section IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation are the guides set forth in Section IV.A of Appendix I.
The ACTION statements provide the required operating flexibility set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept.
CRYSTAL RIVER - UNIT 3 B 3/4 11-3
RADI0 ACTIVE EFFLUENTS BASES "as low as is reasonably achievable." The ODCM calculational methods speci-fied in the Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods approved by NRC for calculating the doses due to the actual release rates of the subject materials were also developed using 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 wih 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111,
" Methods for Estimating Atomspheric 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 radioiodines, radioactive material in particulate fonn and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area.
The pathways wttch were examined in the development of these specifications were:
- 1) individ-ual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) depost-tion onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) disposition on the ground with subsequent exposure of man.
3/4.11.2.4 GASEOUS WASTE TREATMENT The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treat-ment prior to release to the environment.
The requirement that the appro-priate portions of this system be used when specified provides reasonable assurance that the releases of radioactive materials in liquid effluents will oe kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR part 50, and the design objectives of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM were specified as a suit-able fraction of the guide set forth in Sections II.B and II.C of Appendix I,10 CFR Part 50, for gaseous effluents.
3/4.11.2.5 DOSE This specification is provided to meet the reporting requirements of 40 CFR 190.
CRYSTAL RIVER - UNIT 3 B 3/4 11-4
lRADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.6 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of poten-tially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. Maintain-l ing 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.
3/4.11.2.7 GAS STORAGE TANKS Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard Review Plan 15.7.1, " Waste Gas System Failure."
3/4.11.3 SOLID RADI0 ACTIVE WASTE The OPERABILITY of the solid radwaste system ensures that the system will be available for use whenever radioactive wastes from liquid system (e.g.,
filter sludges, spent resins, evaporator bottoms, boric acid solutions and sodium sulfate solutions) require processing and packaging prior to baing shipped offsite. This specification implements the requirements of 10 CFR Part 50.36a and General Design Criteria 60 of Appendix A to 10 CFR Part 50.
The process parameters used in establishing the PROCESS CONTROL PROG".AM may include, but are not limited to waste type, waste pH, waste / liquid / solidification agent / catalyst ratios, waste oil centent, waste principal chemical constituents, mixing and curing times.
CRYSTAL RIVER - UNIT 3 B 3/4 11-5
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological monitoring program required by this specification pro-vides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrat-ions 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. The initially specified monitoring pro-gram will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.
The detection capabilities required by Table 4.12-1 are state-of-the-art for routine environmental measurements in industrial laboratories. The LLD's for drinking water meet the requirements of 40 CFR 141.
3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of unre-stricted areas are identified and that modifications to the monitoring program are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part
- 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vege-tables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vege-tables assumed in Regulatory Guide 1.109, Revision 1, October 1977, for consumption by a child. To detennine this minimum garden size, the fol-lowing assumptions were used,1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and
- 2) a vegetation yield of 2 kg/ square meter.
3/4.12.3 CROSSCHECK PROGRAM The requirement for participation in an Interlaboratory Comparison program provided to ensure that indpendent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are perfonned 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
ADMINISTRATIVE CONTROLS QUORUM 6.5.1.5 A quorum of the PRC shall consit. of the Chairman or his designated alternate and four members including alternates.
RESPONSIBILITIES 6.5.1.6 The Plant Review Committee shall be responsible for:
Review of 1) all procedures required by Specification 6.8 and a.
changes thereto, 2) any other proposed procedures or changes thereto as determined by the Nuclear Plant Manager to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
Review of all proposed changes to the Appendix "A" Technical c.
Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
Investigation of all violations of the Technical Specifications e.
including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Director-Power Production and to the Chairman of the Nuclear General Review Committee.
f.
Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commssion.
Review of facility operations to detect potential nuclear safety g.
- hazards, h.
Performance of spec.1 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 and shall submit recommended changes to the Chairman of the Nuclear General Review Committee.
J.
Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Nuclear General Review Committee.
CRYSTAL RIVER - UNIT 3 6-6
ADMINISTRATIVE CONTROLS k.
Review of every unplanned release of radioactive material to the environs; evaluate the event; specify remedial action to prevent recurrence; and document the event description, evaluation, and the corrective action and the disposition of the corrective action in the plant records.
CRYSTAL RIVER - UNIT 3 6-6a
ADMINISTRATIVE CONTROLS REVIEW (Continued) g.
Events requiring 24 hour2.777778e-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 or operation of safety-related structures, systems, or components.
1.
Reports and meetings minutes of the Plant Review Committee.
AUDITS 6.5.2.9 Audits of facility activities shall be perfonned under the cogni-zance of the NGRC. These audits shall encompass:
a.
The conformance of facility operation to provisions contained within the Technical Specifications and applicable license condi-tions at least once per 12 nonths.
b.
The perfonnance, 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 perfonnance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months.
e.
The Facility Emergency Plan and implementing procedures at least once per 24 months.
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.
The radiological environmental monitoring program and the result thereof at least once per 12 months.
i.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
j.
The PROCESS CONTROL PROGRAM for the SOLIDIFICATION of radioactive wastes from liquid systems at least once per 24 months.
CRYST?.L RIVER - UNIT 3 6-10
ADMINISTRAT! "
>NTROLS A_UNTS (Continued) k.
Any other area of faciiity operation considered appropriate by the NGRC or the Senior Vice President-Engineering and Constru:: tion.
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 NRCC meeting shall be prepared, approved and forwarded to the Senior Vice President-Ergineering and Construction within 14 days following eac : e.eeti ng.
b.
Reports of reviews encompassed by Section 6.5.2.8 above, shall be prepared, approved and forwarded to the Senior Vice President-Engineering and Construction within 14 days following completion of the review.
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 OCCURENCES:
a.
The Commission shall be notified and/or a report submitted pursuant to the requirement of Specification 6.9.
b.
Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the PRC and submitted to the NGRC and the Director-Power Production.
CRYSTAL RIVER - UNIT 3 6-11
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 Director-Power Production 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 componenti systems or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Com-mission, the NGRC and the Director-Power Production within 14 days of the violation.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix "A" of Regula-tory Guide 1.33, November,1972.
b.
Refueling operations.
c.
Surveillance and test activities of safety-related equipment.
d.
Setarity Plan implementation.
e.
Emeroency Dlan implementation.
f.
Fire Protection Program implementation.
g.
The radiological envirormental monitoring program.
h.
The Radwaste Solidificatico Program implementation.
i.
OFFSITE DOSE CALCULATION MANUAL IMPLEMENTATION.
6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, except 6.8.1.g shall be reviewed by the PRC and approved by the Nuclear Plant Mariager prior to implementation and reviewed periodically as set forth in administrative procedures.
Each procedure of 6.8.1 9 and changes thereto, shall be reviewed and approved by the Manager, Nuclear Support Services, prior to implementation and reviewed annually.
CRYSTAL RIVER - UNIT 3 6-12
ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.
6.9.1.7 The annual radiological environmental operating reports shall in-clude suninaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational con-trols (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environ-ment.
If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.
The annual radiologi al environmental operating reports shall include sum-marized and tabulate results in the fonnat of Table 6.9-1 of all radiologi-cal environmental samples taken during the report period.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a sup-plementary report.
The reports shall also include the following:
- 1) a map of those sampling locations subject to change based on unusual census results keyed to a table giving distances and directions from the reactor; 2) the results of land uses censuses required by the Specification 3.12.2; and 3) the results of licensee participation in the Interlaboratory Comparison Program required by Specification 3.12.3.
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 Routine radioactive effluent release reports 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.
CRYSTAL RIVER - UNIT 3 6-15
ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.
6.9.1.7 The annual radiological environmental operating reports shall in-clude sumaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational con-trols (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environ-ment.
If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and i planned course of action to alleviate the problem.
The annual radiological environmental operating reports shall include sum-marized and tabulated results in the format of Table 6.9-1 of all radiologi-cal environmental samples taken during the report period.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a sup-plementary report.
The reports shall also include the following:
- 1) a map of those sampling locations subject to change based on unusual census results keyed to a table giving distances and directions from the reactor; 2) the results of land uses censuses required by the Specification 3.12.2; and 3) the results of l
licensee participation in the Interlaboratory Comparison Program required by Specification 3.12.3.
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 Routine r6dioactive effluent release reports 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.
CRYSTAL RIVER - UNIT 3 6-15
O Q
TABLE 6.9-1 n:oj ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
a>r--
Name of Facility Docnet No.
Location of Facility Reporting Period
- o icounty, simiel e
C 5
Typeend Lovver Limit Numtw of H
Me saum or Poehvvey 7 otal Hurster of All Indacator L utions locaelon w th Hegbest Annual Mean Contros lo lone
'g g
g r
w Samsded of Analyses Detection" M*en 18 Name y,, g,g OCCURREliC;t h
Mem til D
n (Unit of Measurerrent)
Performed ILLDI Rease Distence end Direction p
b Range Air Patticulates 3
(pCi/m )
Gross # 416 0.003 0 08(200/312)
Middletown 0.10(5/52) 0.08 (8/104) 1 (0 05-2.0) 5 miles 340*
(0.08 2.0)
(0.05-1.40) 7-Spec.32 cn Cs 0.003 0.05 (4/"*
Smithville 0.08 (?/4)
<tLD 4
M "c
(0 03 0.13p 2.5 miles 160 (0.03 0.13)
S
("
=c 140 g
De 0.003 0 03(2/24)
Podunk 0.05 (2/4) 0.02 (1/8) 1 (0 01-0.08) 4.0 miles 270*
(0.01 0.08)
~
r "Sr 40 0.002
<LLD
<LLD 0
A E
E Sr 40 0.0003
<LLD
<LLD 0
pCi/kg (dry weight) 7-Spec. 8 Cs 00
<LLD
<LLD 90 0 /4)
O Cs 80
<tLD
<LLD
<LLD 0
60Co 80 120 (3/4)
River Mile 35 See column 4
<tLD 0
(90-2001 Podunk River
- Nominal Lower Limit of Detection ILLD) as defined in table noestion e. of Table 4.121 of Specification 4.12.1.1.
bMears and range based upon detectable measurements only. Fractson of detectable measurementa et spectflad locatione le trus&cated in parentheese, it) dNote: The esemple data are provuted for silustrative purposes only.
ADMINISTRATIVE CONTROLS 6.9.1.9 The semiannual radioactive effluent release reports shall include a sunmary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit 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 B thereof.
The semiannual racioactive effluent release reports shall include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.
The semiannual radioactive effluent release reports shall include an assess-ment of the radiation doses from radioactive effluents to individuals due to their activities inside the exclusion area boundary (Figure 5.1-1) during the report period. All assumptions used in making these assessments (e.g.,
specific activity, exposure time and locas fon) shall be included in these reports.
The semiannual radioactive effluent release reports shall include the fol-lowing information for all unplanned offsite releases of radioactive materi-als in gaseous and liquid effluents:
A description of the event and equipment involved.
a.
b.
Cause(s) for the unplanned release.
c.
Actions taken to prevent recurrence.
d.
Consequences of the unplanned release.
The semiannual radioactive effluent release reports shall include an assess-ment of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21, Revision 1, June 1974.
In addition, the unre ricted area boundary maximum noble gas gamma air and beta air doses shall b evaluated. The meterological conditions concurrent with the releases of effluents 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 (0DCM).
The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM made during the reporting period, as provided in Specification 6.14.
CRYSTAL RIVER - UNIT 3 6-17
ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management InforTnation and Program Control, 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.
In addition, any changes to the OFFSITE DOSE CALCULATIONAL MANUAL of Specification 6.14 or the Radioactive Waste Treatiment Systems of Specifications 6.15 shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective.
REPORTABLE OCCURRENCES 6.9.1.11 The REPORTABLE OCCURRENCES of Specifications 6.9.1.12 and 6.9.1.13 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 of occurrence.
In case of corrected or supplemen-tal reports, a licensee event report shall be completed and reference shall be made to the original report date.
PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.12 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 'acsimile 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 com-pleted 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.
Failure of the reactor protection system or other systems subject to limiting safety-system settings to initiate the required pros tective function by the time r monitored parameter reaches the setpoint specified as the limiting safety-system setting in the technical specifications or failure to complete the require J pro-tective 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 specifica-tions.
c.
Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.
CRYSTAL RIVER - UNIT 3 6-18
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 snutdown margin less conservative than specified in the technical specifications; short-term reac-tivity increases that correspond to a reactor period of less than 5 seconds or, if suberitical, an unplanned reactivity insertion o more than 0.5% ak/k; or occurrence of any unplanned criticality.
e.
Failure or malfunction of one or more components which prevents o could prevent, by itself, the fulfillment of the functional re-quirements 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 requirement 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 ystems, 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 analysi report or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conser vative than assumed in the analyses.
i.
Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than that assumed in the accident anal-yses in the safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifi-cally considered in the safety analysis report or technical speci fications that require remedial action or corrective measures to prevent the existence of development of an unsafe condition.
i CRYSTAL RIVER - UNIT 3 6-19
ADMINISTRATIVE CONTROLS THIRTY-DAY WRITTEN REPORT 6.9.1.13 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within 30 days of occurrence 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 fonn 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 estab lished by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.
b.
Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.
c.
Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree o redundancy provided in reactor protection systems or engineered safety feature systems.
d.
Abnormal degradation of systems other than those specified in 6.9.1.12.c above, designed to contain radioactive material resulting from the fission process.
e.
An unplanned offsite release of 1) more than 1 Curie of radioac-tive material in liquid effluents, 2) rncre than 150 Curies of noble gas in gaseous effluents, or 3) more than 0.05 Curies of radiciodine in gaseous effluents. The report of an unplanned off site 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.
CRYSTAL RIVER - UNIT 3 6-20
ADMINISTRATIVE CONTROLS f.
Measured levels of radioactivity in an environmental sampling medium at one or more sampling locations determined to exceed the I
reporting level values of Table 6.9-2 when averaged over any cal-endar quarter sampling period.
When more than one of the radio-nuclides in Table 6.9-2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) + concentration (2) +...) 1.0 limit level (1) limit level (2)
When radionuclides other than those in Table 6.9-2 are detected and are the result of plant effluents, this report shall be sub-mitted if the potential annual dose to an individual is equal to or greater than twice the calendar quarter limits of Specifi-cations 3.11.1.2, 3.11.2.2 or 3.11.2.3.
This report is not re-quired 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 Environtrental Operating Report.
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 iden tified below pursuant to the requirements of the applicable reference speci fication:
a.
ECCS Actuation, Specification 3.5.2 and 3.5.3.
b.
Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
c.
Inoperable Meteorological Monitoring Instrumentation, Specifica-tion 3.3.3.4.
d.
Seismic event analysis, Specification 4.3.3.3.2.
Inoperable Fire Detection Monitoring Instrumentation, Specifica-e.
tion 3.3.3.7.
f.
Inoperable Fire Suppression System, Specifications 3.7.11.1, 3.7.11.~. 3.7.11.3, and 3.7.11.4.
g.
Liquid or Gaseous Effluent Calculated Dose Exceeding Limits, Specification 3.11.1.2, 3.11.2.2, and 3.11.2.3.
h.
Inoperable Radwaste System, Specifications 3.11.1.3, 3.11.2.4, an 3.11.3.1.
CRYSTAL RIVER - UNIT 3 6-21
TABLE 6.9-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES S
<9 Airborne Particulate Water or Gasgs Fish Milk Food Products g
Analysis (pCi/t)
(pCi/m )
(pCi/kg, wet)
(pCi/t)
(pCi/kg, wet) o
[
11 - 3 30000 Mn-54 1000 30000 Fe-59 400 10000 Co-58 1000 30000 R
Co-60 300 10000 u
Zn-65 300 20000
{
Zr-Nb-95**
400 I-131 20 (2*)
0.9 3
100 Cs-134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 Ba-La-140**
200 300 For potable water
- Reporting level is total for parent and progeny.
ADMINISTRATIVE CONTROLS 1.
Liquid or Gaseous Effluent Calculated Dose Exceeding Twice the Limits, Specification 3.11.2.5.
j.
Radiological Environmental Monitoring Program Analysis, Specifica tion 3.12.1.
k.
Land Use Census Analysis, Specification 3.12.2.
6.10 RECORD RETENTION 6.10.1 The following records shal1 be retained for at least five years:
a.
P.ecords and logs of facility operation covering time intervals at each power level.
b.
Records and logs of principal maintenance activities, inspections repair and replacement of principal items of equipment related to nuclear safety, c.
All REPORTABLE OCCURRENCES submitted to the Commission.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
e.
Records of reactor tests and experiments.
f, Records of changes made to Operating Frocedures.
g.
Records of radioactive shipments.
h.
Records of sealed source and #ission detector leak tests and results.
1.
Records of annual physical inventory of all sealed source materia of record.
6.10.2 The following records shall be retained for the duration of the Facility Operating License:
a.
Records and drawing changes reflecting facility design modifica-tions made to systems and equipment described in the Final Safety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c.
Records of facility radiation and contamination surveys.
CRYSTAL RIVER - UNIT 3 6-23
ADMINISTRATIVE CONTROLS d.
Records of radiation exposure for all individuals entering radi-ation control areas.
e.
Records of gaseous and liquid. radioactive material released to the environs including monitoring instrumentation alarm / trip setpoints.
f.
Records of transient or operational cycles for those facility components identified in Table 5.7-1.
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 procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the PRC and the NGRC.
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 app:eved, maintained and adhered to for all operations involving personnel raviation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In liew 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 radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a Radiation Work Permit and any individual or group of individuals permitted to enter such areas shall be provided with radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A High Radiation Area in which the intensity of radiation 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 areas.
The keys shall be CRYSTAL RIVER - UNIT 3 6-24
ADMINISTRATIVE CONTROLS maintained under the administrative control of the Health Physics Supervisor with one key assigned to the administrative control of Shift Supervisor on duty.
6.13 RADWASTE SOLIDIFICATION PROGRAM 6.13.1 Procedures for radwaste solidification shall be prepared consistent with the process control parameters of the PCP and shall be approved, maintained and adhered to for all operations involving SOLIDIFICATION consistent with Specification 3.11.3.1.
6.13.2 Licensee initiated changes to the PCP shall be made by the following method:
1.
Shall be submitted to the Commission by inclusion in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made and shall contain:
a.
sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; b.
a determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c.
documentation of the fact that the change has been I
reviewed by the PRC and approved by the Plant Manager.
l l
2.
Shall become effective upon review by the PRC and approval by the Plant Manager.
i i
CRYSTAL RIVER - UNIT 3 6-25
ADMINISTRATIVE CONTROLS 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM)
FUNCTION 6.14.1 The ODCM shall describe the methodology and parameters to be used in the celculation of offsite doses due to radioactive gaseous and liquid effluentsand in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LC0's contained in these Technical Specifications.
6.14.2 Licensee initiated changes to the ODCM shall be made by the following method:
1.
Shall be submitted to the Commission by inclusion in the i
Monthly Operating Report within 90 days in which the j
change (s) was made effective and shall contain:
a.
sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.
Information submitted should consist of a package of those pages of ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);
b.
a determination that the charige will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and c.
documentation of the fact that the change has been reviewed by the PRC and approved by the Plant Manager.
2.
Shall become effective upon review by the PRC and approval l
by the Plant Manager.
1 i
l CRYSTAL RIVER - UNIT 3 6-26
ADMINISTRATIVE CONTROLS 6.15 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous and Solid FUNCTION 6.15.1 The radioactive waste treatment systems (liquid, gaseous and solid) are those systems described in the facility Final Safety Analysis Report or Hazards Summary Report, and amendments thereto, which are used to maintain that control over radioactive materials in gaseous and liquid effluents and in solid waste packaged for offsite shipment required to meet the LCO's set forth in Specifications 3.11.1.1, 3.11.1.2, 3.11.1.3, 3.11.1.4, 3.11.2.1, 3.11.2.3, 3.11.2.4, 3.11.2.5, 3.11.2.7 and 3.11.3.1.
6.16.2 Major changes to the radioactive waste systems (liquid, gaseous and solid) shall be made by either of the following methods.
For the purpose of this specification " major changes" is defined in Specification 6.15.3 below.
A.
Licensee initiated changes:
1.
The Commission shall be informed of any changes by the inclu-sion of a suitable discussion of each change in the Monthly Operating Report within 90 days in which the change was made.
The discussion of each change shall contain:
a summary of the evaluation that led to the determina-a.
tion that the change could be made (in accordance with 10 CFR 50.59);
b.
sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental infonnation; a detailed description of the equipment, components and c.
processes involved and the interfaces with other plant system; d.
an evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluent and/or quantity of solid waste from those previously predicted in the license application and amendments thereto:
CRYSTAL RIVER - UNIT 3 6-27
ADMINISTRATIVE CONTROLS e.
an evaluation of the change which shows the expected maximum exposures to individual in the unrestricted area and to the general population from those previously estimated in the license application and amendments thereto; f.
a comparison of the predicted releases of radioactive materials in liquid and gaseous effluents and in solid waste to the actual release for the period in which the changes were made; g.
an estimate of the exposure to plant operating personnel as a result of the change; and h.
documentation of the fact that the change was reviewed l
by the PRC and approved by the Plant Manager.
2.
The change shall become effective upon review by the PRC and approval by the Plant Manager.
6.15.3 Background and definition of what constitutes " major changes" So radioactive waste systems (liquid, gaseous and solid).
A.
Background.
1.
10 CFR Part 50, Section 50.34a(a) requires that each application to construct a nuclear power reactor provide a description of the equipment installed to maintain control over radioactive material in gaseous and liquid effluents producea during normal reactor operations including operational occurrences.
CRYSTAL RIVER - UNIT 3 6-28
ADMINISTRATIVE CONTROLS 2.
10 CFR Part 50, Section 50.34a(b)(2) requires that each ap-plication to construct a nuclear power reactor provide an estimate of the quantity of radionuclides expected to be re-leased annually to unrestricted areas in liquid and gaseous effluents produced during normal reactor operation.
3.
10 CFR Part 50, Section 50.34a(3) requires that each appli-cation to construct a nuclear power reactor provide a description of the provisions for packaging, storage and shipment offsite of solid waste containing radioactive materials resultine from treatment of gaseous and liquid effluents and from other sources.
4.
10 CFR Part 50, Section 50.34a(3)(c) requires that each application to operate a nuclear power reactor shall include
- 1) a description of the equipment and procedures for the control of gaseous and liquid effluents and for the mainte-nance and use of equipment installed in radioactive war e systems and 2) a revised estimate of the information in (b)(2) if the expected releases and exposures differ -ignif-icantly from the estimate submitted in the application for a construction permit.
5.
The Regulatory staff's Safety Evaluation Report and amend-ments thereto issued prior to the issuance of an operating license contains a description of the radioactive waste sys-tems installed in the nuclear power reactor and a detailed evaluation (including estimated releases of radioactive materials in iquid and gaseous waste and quantities of solid waste produced from normal operation, estimated annual maximum exposures to an individual in the unrestricted area and estimated exposures to the general population) which shows the capability of these systems to meet the appropri-ate regulat.ons.
6.
The Aegulator staff's Final Environmental Statement issued prior to tne issuance of an operating license contains a de-tailed evaluation as to the expected environmental impace from the estimated releases of radioactive material in liquid and gaseous effluents.
B.
Definition
" Major Changes" to radioactive waste systems (liquid, gaseous and solid) shall include the following:
1.
Major changes in process equipment, components, structures ano effluent monitoring instrumentation from those described in the Final Safety Analysis Report (FSAR) or the Hazards CRYSTAL RIVER - UNIT 3 6-29
ADMINISTRATIVE CONTROLS Summary Report and evaluated in the staff's Safety Evaluation Report (SER) (e.g., deletion of evaporators and installation of demineralizers; use of fluidized bed calciner/ incineration in place of cement solidification systems);.
2.
Major changes in the design of radwaste treatment systems (liquid, gaseous and solid) that could significantly alter the characteristics and/or quantities of effluents released or volumes of solid waste stored or shipped offsite from those previously considered in the FSAR and SER (e.g., use of asphalt systein in place of cement);
3.
Changes in system design which may invalidate the accident analysis as described in the SER (e.g., changes in tank capacity that would alter the curies released)_; and 4.
Changes in system design that could potentially result in a significant increase in occupational exposure of operating personnel (e.g., use of skid mounted equipment, use of mobile procesing equipment).
CRYSTAL RIVER - UNIT 3 6-30
TABLE OF CONTENTS Page No.
1.0 DEFINITIONS 1.1 Frequency 1-1 1.2 Point of Discharge (POD) 1-1 1.3 AT Across the Condenser 1-1 1.4 Unit 3 Mixing Zone 1-1 1.5 Emergency Need for Power 1-1 1.6 Abnormal Power Operation 1-1 1.7 Intake Area 1-3 1.8 Discharge Area 1-3 1.9 Inner Bay 1-3 1.10 Outer Bay 1-3 1.11 Channel Check 1-3 2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Thermal 2-1 2.1.1 Maximum AT Across Condenser 2-1 2.1.2 Maximum Discharge Temperature 2-2 2.2 Hydraulic 2-3 2.3 Chemical 2-3 2.3.1 Biocides 2-3 2.3.2 Corrosion Inhibitors 2-4 3.0 ENVIRONMENTAL SURVEILLANCE 3.1 Nonradiological Surveillance 3-1
11 TABLE OF CONTENTS (Cont'd)
Page No.
3.1.1 Benthos in Discharge Area 3-2 3.1.2 Marsh Grz3s 3-3 3.1.3 Impingement on Intake Screens 3-4 3.1.4 General Ecological Survey 3-4 3.1.5 Chemical-Industrial Waste Water Treatment System 3-5 4.0 SPECIAL SURVEILLANCE, RESEARCH, OR STUDY ACTIVITIES 4.1 Thermal Plume Determination During Unit 3 Operation 4-1 4.2 Intake Velocity Determination 4-2 4.3 Study of Erosion in the Discharge System 4-2 5.0 ADMINISTRATIVE CONTROLS 5.1 Organization 5-1 5.2 Res ponsibili ty 5-1 5.3 Review and Audit 5-3 5.4 Action to be Taken If Limiting Condition for Operation is Exceeded 5-5 5.5 Procedures 5-5 5.6 Plant Reporting Requirements 5-6 5.6.1 Routine Reports 5-6 5.6.2 Non-routine Reports 5-7 5.6.3 Changes 5-8 5.7 Records Retention 5-8 5.8 Special Requirements 5-8
iii List of Figures Page No.
No.
1.1-1 Point of Discharge 1-2 1.1-2 Inner and Outer Bays 1-4 3.1-1 Settling Ponds and Test Well Locations 3-8 5.1-1 Organization for Implementing Environmental Technical Specifications 5-2 5.3-1 Organization for Independent Review and Audit 5-4 5.8-1 Chemical-Industrial Waste Water Treatment System 5-11
1-1
/
1.0 Definitions The following terms are defined for uniform interpretation of the Environmental Technical Specifications for Crystal River Unit 3.
1.1 Frequency - Terms used to specify frequency are defined as follows:
One per shift - At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Daily - At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Weekly - At least once per 7 days.
Biweekly - At least once per 15 days.
Monthly - At least once per 31 days.
Quarterly - At least once per 92 days.
Semiannually - At least once per 6 months.
A maximum allowable extension for each surveillance requirement shall not exceed 25% of the surveillance interval.
1.2 Point of Discharge (P0D) - The intersection of the discharge canal and the original bulkhead line as shown on Figure 1.1-1.
1.3 AT Across the Condenser - The average temperature difference between the inlet and outlet of Unit 3.
1.4 Unit 3 Mixing Zone - The enclosed area of the discharge canal bounded by the eastern end of the canal and the calle chase from Units 1 and 2 by crossing the canal.
1.5 Emergency Need for Power - Any event causing authorized Federal offi-cials to require or request that the Florida Power Corporation supply electricity to points within or without the State or other emergencies declared by State, County, or Municipal authorities during which an uninterrupted supply of electric power is vital to public health and safety.
1.6 Abnormal Power Operation - The operation of Crystal River Unit 3 beyond these technical specificati9.1s due to the Emergency Need for Power.
1-3 1.7 Intake Area - The intake canal and all of the water area south of the north intake dike and within two miles of the west tip of the south intake dike.
1.8 Discharge Area - The discharge canal and all of the water area north of the south discharge dike and within two miles of the north dicharge dike.
1.9 Inner Bay - An area as shown in Figure 1.1-2 which is five feet or less in depth composed of a mixture of grassy bottoms, oyster associa-tions, algal bottoms and areas of sand and mud.
1.10 Outer Bay - The outer basin as shown in Figure 1.1-2 in which the planktonic ecosystem becomes as important as the bottom ecosystems.
1.11 Channel Check - The qualitative assessment of channel behavior during operation by observation.
This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
t
2-4 water box is being chlorinated, a sample is taken from the outlet water box, analyzed for residual chlorine (free and combined), and the results are recorded on a circular recorder.
Samples are automati-cally changed by solenoid valves in accordance with the sequence of the chlorine generation system. This system provides a continuous record of chlorine residual in each outlet water box.
2.3.2 Corrosion Inhibitors No chromates shall be used.
3-6 Reporting Requirements Reports shall be furnished in accordance with Section 5.6.1.
Basis Monitoring is performed to assure that all chemical-industrial waste water is controlled so as to not adversely affect public health or the natural aquatic environment.
5-5 5.4 ACTION TO BE TAKEN IF LIMITING CONDITION FOR OPERATION IS EXCEEDED 5.4.1 Immediate remedial actions as permitted by these environmental techni-cal specifications shall be implemented until such time as the limiting condition for operation is met.
5.4.2 The occurrence shall be promptly reported to the Chainnan of the Nuclear General Review Committee and investigated as specified in Section 5.3.
5.4.3 The Nuclear General Review Committee shall prepare and submit promptly a separate report for each occurrence in accordance with Section 5.3.10.
5.4.4 The Director, Power Production, shall report the occurrence to the NRC as specified in Section 5.6.2.
5.5 PROCEDURES 5.5.1 Explicit written procedures, including applicable check-off lists and instructions, shall be prepared for the implementation of the monitor-ing requirements described in Sections 2 and 3, approved as specified in Section 5.5.2, and adhered to for operation of all systems and com-ponents involved in carrying out the environmental monitoring pro-grams.
Procedures shall include samp!ing, instrument calibration, analysis, and action to be taken when limits are approached or exceeded.
Calibration frequencies and standards for instruments used in perfonning the measurements shall be included.
Testing frequency of alanns shall be included.
These frequencies shall be detennined from experience with similar instruments in similar environments and fran manufacturers' technical manuals.
5.5.2 All procedures implemented by plant staff personnel described in Sec-tion 5.5.1 above, and changes thereto, shall be reviewed as specified in Section 5.3 and approved by the Nuclear Plant Superintendent prior to implementation.
Temporary changes to procedures which do not change the intent of the original procedure may be made, p.ovided such changes are approved by tro members of the plant management staff, one of whom holds a senior operator's license. Such changes shall be docu-mented, subsequently reviewed and approved by the Plant and Nuclear General Review Committees. All procedures and changes to procedures utilized by contractors to implement the environmental monitoring pro-grams described in Section 3 shall be reviewed and approved by the Manager, Nuclear Support Services.
5-6 5.5.3 Prior to special tests or changes:
a.
If the Nuclear Plant Manager decides to make a change in the facility or Operating Procedures, or to conduct a test or experi-ment, and concludes that the proposed change, test, or experimant does not involve a change in the Environmental Technical Specifi-cations, or an unreviewed environmental impact questior., he may order the change, test, or experiment to be made, shall enter a description thereof in the operating records of the facility, and shall send a copy of the instructions pertinent thereto to the chairman of the Nuclear General Review Committee for review.
b.
If the Nuclear Plant Manager desires to make a change in the facility or Operating Procedures, or to conduct a test or experi-ment which in his opinion might involve a change in the Environ-mental Technical Specification or involve an unreviewed environ-mental impact question, he shall not
- er such change, test, or experiment until he has referred the matter to 9e Nuclear General Review Committee for review and report to the Senior Vice President - Engineering and Construction for resolution.
5.6 PLANT REPORTING REQUIREMENTS 5.6.1 Routine Reports A.
Annual Nonradiological Environmental Operating Report A report on the r.onradiological environmental surveillance programs for the previous 12 months of operation shall be submitted to the Director of Inspection and Enforcement (with copy to Director of Nuclear Reactor Regulation) within 90 days after January 1 of each year.
The report shall include summaries, interpretations, and statistical evaluation of the results of the nonradiological environmental surveillance activities (Section 3.0) and the environmental monitoring programs required by limiting condition for operation (Section 2.0) for the report period. A comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment shall be provided.
If harmful effects or evidence of irreversiole damage are detected by the monitoring, the licentre shall provide an ar.alysis of the problem and a proposed course of action to alleviate the problem.
b-7 5.6.2 Non-Routine Reports A.
Limiting Condition for Operation Exceeded In the event that:
(1) a limiting condition for operation is exceeded or (2) an event involving a significant adverse environ-mental impact occurs, a report will be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and telegraph to the Director of the Office of Inspec-tion and Enforcement followed by a written report with a copy to the Director, Office of Nuclear Reactor Regulation within 15 days.
The telegraph report will quantify the occurrence, its causes and, if aspects of the Crystal River Unit 3 operation are among the causes, planned remedial action to the extent possible.
The written report will fully describe the occurrence and will describe its causes and corrective action as fully as possible.
B.
Nonradiological Report Levels In tlie event that a nonradioactive reporting level is reached, a written report shall be made within 30 days to the Director of the Office of Inspection and Taforcement with a copy to the Director of the Office of Nuch.>r Reac'.or Regulation. The report shall describe, analyze and evaluate the occurrence, including extent and magnitude of impact; describe the cause of the occur-rence; and if aspects of the Crystal River Unit No. 3 operation are among the causes, indicate the correction action taken to preclude repetition of the o:currence.
5-8 5.6.3 Changes A.
A report shall be made to the Director of Office of Nuclear Reactor Regulation prior to implementation of a change in plant design, in plant operation, or in procedures described in Section 5.5 if the change would have, in the judgement of the applicant, a significant adverse effect on the environment or involves an environmental matter or question not previously reviewed and evaluated by the USNRC.
The report shall include a description and evaluation of the change and a supporting benefit-cost analysis.
B.
Request for changes in environmental technical specifications shall be suDmitted to the Director of Office of Nuclear Reactor Regulation for review and authorization.
The request shall include an evaluation of the impact on the change and a supporting benefit-cost analysis.
5.7 RECORDS RETENTION 5.7.1 Records and logs relative to the following areas shall be retained for the life of the plant:
a.
Records and drawing changes reflecting plant design modifications made to systems and equipment as described in Section 5.6.3.
b.
Records of environmental swveillance data.
c.
Records to demonstrate compliance with the limiting conditions for operation in Section 2.0.
5.7.2 All other records and logs relating to the environmental technical specifications shall be retained for five years.
5.8 SPECIAL REQUIREMENTS The chemical-industrial waste water treatment system shall collect and transport all water wastes to the percolation / evaporation ponds.
The system is shown diagramatically in Figure 5.8-1.
JABLE Of CONILNIS 1.0 Introduction 2.0 Liquid Ef fluent Instrumentation Setpoints (Speci fication 3.3.3.8) 3.0 Gaseous Effluent Instrumentation Setpoints (Specification 3.3.3.9) 4.0 Liquid Effluent Releases and Dose Calculations 4.1 Liquid E ffluent Concentration - Pre-release Calct.1ations (Speci fication 4.11.1.1.3) 4.2 Liquid Effluent Concentration - Post-releam Calculations (Speci fication 4.11.1.1.4) 4.3 Liquid Ef fluent Concentration - Projected Calculations (Speci fication 4.11.1.1.5) 4.4 Liquid E ffluent Cumulative Dose (Speci ficatinn 4.11.1.2) 4.5 Liquid Ef fluent Projected Dose (Specification 4.11.1.3) 4.6 Liquid Holdup Tank Quantities (Specification 3.11.1.4) 5.0 Gaseous Effluent Releases and Dose Calculations 5.1 Gaseous Effluent Noble Gas Dose Rate (Specification 4.11.2.1.1) 5.2 Gaseous Effluent Other Than Noble Gas Dose Rate (Specification 4.11.2.1.4) 5.3 Gaseous Effluent Noble Gas Cumulative Dose (Specification 4.11.2.2) 5.4 Gaseous Effuent Other Than Noble Cumulative Dose (Speci fication 4.11.2.3) 5.5 Gaseous Effluent Projected Dose (Specification 4.11.2.4.1) 5.6 Waste Gas Decay Tank Quantities (Specification 4.11.2.7) 6.0 Radiological Environmental Monitoring 6.1 Replacement of Sair?le Locations (Specification 3.12.1, Action c) 6.2 Census Results (Specification 3.12.2, Actions a and b) 7.0 Assessment of Dose for Semiannual Radioactive Effluent Release Reports (Specification 6.9.1.9) 8.0 Revisions to the ODCM (Spec'. iication 6.14.2)