ML20099K759
| ML20099K759 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/22/1985 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20099K761 | List: |
| References | |
| NUDOCS 8503200364 | |
| Download: ML20099K759 (75) | |
Text
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UNITED STATES y
p, NUCLEAR REGULATORY COMMISSION 5
- j WASHINGTON. D. C. 20555
%,...../
SALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amerdment No.100 License No. DPR-53 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (the licensee) dated October 11, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
8503200364 850222
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PDR ADOCK 05000317 P
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-53 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.100, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATC4Y COMMISSION b
James R. Miller Ch" f
Operating Reactors fir nch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 22, 1985 4
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ATTACHMENT TO LICENSE AMENDMENT N0.100 FACILTIY OPERATING LICENSE NO. DPR-53 DOCKET NO. 50-317 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are provided to maintain document completeness.
Appendix A Remove Pages Insert Pages I
I VIIIa XIII XIII XIV XIV 1-1 1-1 1-6 1-6 1-7 1-7 1-8 1-8 4
1-9(renumbered) 1-10 3/4 12-1 through 3/4 12-13 8 3/4 12-1 B 3/4 12-2 5-1 5-1 s
5-?
5-2 Appendix B Appendix B, Part I title pace Appendix B, Part I title page Table of Contents Table of Contents 3.1-1 3.1-1 3.2-1 3.2-1 3.2-2 Fioure 3.2-1 Table 3.2-1 (3 pages)
Table 3.2-2 v
INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS Defined Terms...............................................
1-1 Thermal Power...............................................
1-1 Rated Thermal Power.........................................
1-1 Ope ra t i o n a l Mo de............................................
1 - 1 Action......................................................
1-1 Opera bl e - Ope ra bi l i ty......................................
1 -1 Repo rta bl e Eve n t............................................
1 -2 Containment Integrity.......................................
1-2 Channel Calibration.........................................
1-2 Channel Check...............................................
1-3 Channel Functional Test..................................... 1-3 Co re Al te ra t i o n.............................................. 3 Shutdown Margin.............................................
1-3 Identified Leakage..........................................
1-4 Unidentified Leakage........................................
1-4 Pressure Bounda ry Lea kage...................................
1-4 Controlled Leakage..........................................
1-4 Az i mu t h a l Powe r T i l t........................................
1 -4 Dose Equivalent I-131.......................................
1-4 E-Average Disintegration Energy.............................
1-5 Staggered Test Basis........................................
1-5 Frequency Notation..........................................
1-5 Axi al S ha pe I ndex...........................................
1 -5 Unrodded Planar Radial Peaking Factor - F Reactor Trip System Response Tine........xy.................
1-5
................... 1-6 Engineered Safety Feature Response Time.....................
1-6 Physics Tests...............................................
1-6 Unrodded Integrated Radial Peaking Factor - F..............
1-6 r
Gaseous Radwaste Treatment System...........................
1-6 Membe r( s ) o f the Publ i c.....................................
1 - 6 Offsite Dose Calculation Manual (0DCM)......................
1-6 Process Control Program (PCP)...............................
1-7 Purge-Purging...............................................
1-7 S i t e B o u n d a ry...............................................
1 - 7 So l i d i fi ca t i on..............................................
1 - 7 Source Check................................................
1-7 Un re s t ri c ted Area...........................................
1 - 7 Ventilation Exhaust Treatment System........................
1-7 Venting.....................................................
1-8 CALVERT CLIFFS - UNIT 1 I
Amendment No. 21, 94, 100
INDEX SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION PAGE 2.1 SAFETY LIMITS Reactor Core................................................
2-1 Reactor Coolant System Pressure.............................
2-1 2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor Tri p Setpoi nts......................................
2-6 BASES SECTION PAGE 2.1 SAFETY LIMITS Reactor Core................................................
B 2-1 Reactor Cool ant System Pres sure.............................
B 2-3 2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor Tri p Se tpoi nts......................................
B 2-4 CALVERT CLIFFS - UNIT 1 II
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 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 12-12 3.4.12.3 INTERLABORATORY COMPARISON PR0 GRAM...................
3/4 12-13
^:
CALVERT CLIFFS - UNIT 1 VIIIa Amendment No. 100
c INDEX BASES SECTION PAGE 3/4.9.5 ' COMMUNICATIONS........................................... B 3/4 9-1 3/4.9.6 REFUELING MACHINE 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 SHUTDOWN COOLING AND COOLANT CIRCULATION................. B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM................. B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT FUEL POOL WATER LEVEL............................ B 3/4 9-3 3/4.9.12 SPENT FUEL POOL VENTILATION SYSTEM.......................
B 3/4 9-3 3/4.9.13 SPENT FUEL CASK HANDLING CRANE.........................
. B 3/4 9-3 3/4.9.14 CONTAINMENT VENT ISOLATION VALVES........................
B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN..........................................
B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS... B 3/410-1 3/4.10.3 NO FLOW TESTS............................................
B 3/4 10-1 3/4.10.4 CENTER CEA MISALIGNMENT.................................. B 3/4 10-1 3/4.10.5 COOLANT C I RCULAT ION...................................... B 3/4 10-1 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 INTERLABORATORY COMPARISON PR0 GRAM....................... B 3/4 12-2 Amendment No. 26, 55, A/8,10b CALVERT CLIFFS - UNIT 1 XIII
INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE Map Defining the Site Boundary and Effluent Re l e a s e Po i n ts..............................................
5-1 Low Pop u l a t i o n Zo ne...........................................
5-1 5.2 CONTAINMENT Co n f i gu ra t i on.................................................
5-1 Design Pressure and Temperature...............................
5-4 5.3 REACTOR CORE Fuel As sembl i e s...............................................
5-4 Control Element Assemblies........
5-4
~
5.4 REACTOR COOLANT SYSTEM Des i gr, Pressure and Temperature............................... 5-4 Volume........................................................
5-5 5.5 METEOROLOGICAL TOWER L0 CATION.................................
5-5 a
5.6 FUEL STORAGE C r i t i c a l i ty...................................................
5 - 5 Drainage......................................................
5-5 Capacity....................................................... 5-5 5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS..........................
5-5 9
CALVERT CLIFFS - UNIT 1 XIV Amendment No. 100
e 1.0 DEFINITIONS DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications.
THERMAL POWER 1.2 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
RATED THERMAL POWER 1.3 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2700 MWt.
OPERATIONAL MODE 1.4 An OPERATIONAL MODE shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.
ACTION
!1.5 ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions.
OPERABLE - OPERABILITY 1.6 A system, subsystem, ' train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s).
Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other required auxiliary equipment that are required for the system, sub-system, train, component or device to perform its function (s) are also capable of performing their related support function (s).
CALVERT CLIFFS-UNIT 1 1-1 Amendment No. 84 100
DEFINITIONS REPORTABLE EVENT 1.7 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:
1.8.1 All penetrations required to be closed during accident conditions are either:
a.
Capable of being closed by an OPERABLE containment automatic isolation valve system, or b.
Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-1 of Specification 3.6.4.1.
1.8.2 All equipment hatches are closed and sealed, 1.8.3 Each airlock is OPERABLE pursuant to Specification 3.6.1.3, 1.8.4 The containment leakage rates are within the limits of Specification 3.6.l.2, and 1.8.5 The sealing mechanism associated with each penetration (e.g., welds, bellows or 0-rings) is OPERABLE.
CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.
The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of 'sequen-tial, overlapping or total channel steps such that the entire channel is calibrated.
CALVERT CLIFFS-UNIT 1 1-2 Amendment No. e//, 94
DEFINITIONS E - AVERAGE DISINTEGRATION ENERGY 1.20 E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MEV) for isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.
STAGGERED TEST BASIS 1.21 A STAGGERED TEST BASIS shall consist of:
a.
A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals, and b.
The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
FREQUENCY NOTATION 1.22 The FREQUENCY NOTATION specified for.the perfomance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.
AXIAL SHAPE INDEX 1.23 The AXIAL SHAPE INDEX (Y ) is the power level detected by the lower r
excore nuclear instrument detectors (L) less the power level detected by the upper excore nuclear instrument detectors (U) divided by the sum of these power levels. The AXIAL SHAPE INDEX (Y,) used for the trip and pretrip signals in the reactor protection system is the above value (Y )r modified by an appropriate multiplier (A) and a constant (B) to detemine the true core axial power distribution for that channel.
YE" U
I"# E+B UNRODDED PLANAR RADIAL PEAKING FACTOR - Fxy 1.24 The UNRODDED PLANAR RADIAL PEAKING FACTOR is.the maximum ratio of the peak to average power density of the individual fuel rods in any of the unrodded horizontal planes, excluding tilt.
CALVERT CLIFFS - UNIT 1 1-5 Amendment No. 21
t DEFINITIONS' REACTOR TRIP SYSTEM RESPONSE TIME 1.25 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.
4 ENGINEERED SAFETY FEATURE RESPONSE TIME 1.26 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.
PHYSICS TESTS 1.27 PHYSICS TEST shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and
- 1) described in Chapter 13.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or -3) otherwise approved by the Commission.
UNRODDED INTEGRATED RADIAL PEAKING FACTOR - F, 1.28 The UNRODDED INTEGRATED RADIAL PEAKING FACTOR is the ratio of the peak pin power to the average pin power in an unrodded core, excluding tilt.
3ASEOUS RADWASTE TREATMENT SYSTE!1 l.29 A GASE0US 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 environ-ment.
MEMBER (S) 0F THE PUBLIC t
l.30 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupa-tionally associated with the plant. This category does not include employees of the utility, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipaent or to make deliveries.
OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.31 The OFFSITE DOSE CALCULATION MANUAL shall contain the current method-ology and parameters used in the calculation of offsite doses due to radio-active gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the environ-mental radiological monitoring program.
CALVERT CLIFFS - UNIT 1 1-6 Amendment No. 2J, 100
DEFINITIONS PROCESS CONTROL PROGRAM (PCP) 1.32 The PROCESS CONTROL PROGRAM shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing ud packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Part 20,10 CFR Part 71 and Federal and State and local regulations governing the disposal of the radioactive waste.
PURGE - PURGING 1.33 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
SITE BOUNDARY 1.34 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
SOLIDIFICATION 1.35 SOLIDIFICATION s' hall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.
SOURCE CHECK 1-36 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
UNRESTRICTED AREA 1.37 An UNRESTRICTED AREA shall be any area at or beyond the SITE B0UNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
VENTILATION EXHAUST TREATMENT SYSTEM 1.38 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through char-coal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents.
Engineered Safety Feature (ESF) atmosphdric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
CALVERT CLIFFS - UNIT 1 1-7 Amendment No.100
DEFINITIONS VENTING 1.39 VENTING is the controlled process of discharging air or gas from a confinement to mahtain temperature, pressure, humidity, concentration or other operating condition, in s,uch a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
CALVERT CLIFFS - UNIT 1 1-8 Amendment No.100
l TABLE 1.1 OPERATIONAL MODES REACTIVITY
% RATED AVERAGE COOLANT MODE CONDITION, K,ff THERMAL POWER
- TEMPERATURE 1.
POWER OPERATION
> 0.99
> 5%
> 300*F 2.
STARTUP
> 0.99 1 5%
> 300*F 3.
HOT STANDBY
< 0.99 0
> 300*F 4.
HOT SHUTDOWN
< 0.99 0
300*F> T
> 200*F avg 5.
COLD SHUTDOWN
< 0.99 0
1 200*F 6.
REFUELING **
< 0.95 0
< 140*F
- Excluding decay heat.
- Reactor vessel head unbolted or removed and fuel in the vessel.
100 CALVERT CLIFFS - UNIT 1 1-9 Amendment No.
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TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY S
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W-At least'once per 7 days.
M At least once per 31 days.
Q At least once per 92 days.
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.
CALVERT CLIFFS - UNIT 1 1-10 Amenoment No.
100
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.
APPLICABILITY: At all times.
ACTION:
a.
With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission in the Annual Radiological Environmental Operating Report a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
b.
With the level of radioactivity as the result of plant effluents in an environmental sample at a specified location exceeding the reporting levels of Table 3.12-2, prepare and submit to the Commission within 30 days after receiving the sample analysis, pursuant to Specification 6.9.2, a Special Report that identifies thecause(s)forexceedingthelimit(s)anddefinesthecorrective actions to be taken to reduce radioactive effluents. When more than one of the radionuclides in Table 3.12-2 are detected in the sample, this report shall be submitted if:
concentration (1)
+ concentration (2)
+.. > 1. 0 reportinglevel(1) re?orting level (2)
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 Radi-ological Environmental Operating Report.
c.
With fresh leafy vegetable samples unavailable from one or n. ore of the sample locations required by Table 3.12-1, identify loca-tions for obtaining replacement samples and add thetn to the radiological environmental monitoring program within 30 days.
The specific locations from which samples were unavailable may then be deleted from the monitoring program.
Identify the cause of the unavailability of samples and identify the new location (s) for obtaining the replacement samples in the next Annual Radiolog-ical Environmental Operating Report.
CALVERT CLIFFS - UNIT 1 3/4 12-1 Amendment No. 100
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING MONITORING PROGRAM LIMITING CONDITION FOR OPERATION d.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.
CALVERT CLIFFS - UNIT 1 3/4 12-2 Amendment No.
100
TABLE 3.12-1 g
RADIOLOGICAL ENVIRONMENTAL MONITOR'ING PROGRAM G9 Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locations, Collection Frequency of Analysis P
b h
- 1. DIRECT RADIATION 23 routine monitoring stations At least Quarterly Gamma dose at least (DRI-DR23) either with two or quarterly.
m more dosimeters or with one E
instrument for measuring and p
recording dose rate continuously, placed as follows:
an inner ring of stations, one in each meteorological sector in the general area of the SITE B0UNDARY (DR1-DR9);
R an outer ring of stations, one in C
each meteorological sector in the 4,
6-to 8-km range from the site (DR10-DR18);
the remaining stations (DR19-DR23) to be placed in special interest areas such as population centers, F
nearby residences, schools, and in l area te serve as a control station.
R
- 2. AIRBORNE a
Radioiodine and Samples from 5 locations (Al-A5):
Continuous sampler Radiciodine Cannister Particulates operation with sample I-131 analysis weekly.
E 3 samples (Al-A3) from close collection weekly, or to the 3 SITE B0UNDARY more frequently if Particulate Sampler:
locations, in different required by dust Gross beta radioactiv-sectors of the highest loading.
ity analysis following
TABLE 3.12-1 (Continued) h RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM in Q
Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locations Collection Frequency a
n of Analysis C
. ^
4 calculated annual average filter change;c ground-level D/Q.
Gammgisotopicanal-ysis of composite E
1 sample (A4) from the vicinity (by location) y of a community having the high-quarterly.
est calculated annual average m
ground-level D/Q.
I sample (AS) from a control location, as for example 15-30 km distant and in the least R
prevalent wind direction.
- 3. hitktsuid!E i
- a. Surface 1 sample at intake area (Wal)
Composite sample Gamma isotopic anal-1 sample at discharge area over 1-month period' ysisd monthly. Compos-(Wa2) ite for tritium anal-ysis quarterly.
p b., Sediment from I sample from downstream area Semiannually Gamg isotopic anal-g shoreline with existing or potential ysis semiannually.
R recreational value (Wb1).
a k
- 4. INGESTION 1
- a. Fish and 3 samples of commercially and/or Sample in season, or Gammaisgtopic Invertebrates recreationally important species semiannually if they analysis on edible 8
(2 fish species and 1 inverte-are not seasonal, portions.
brate species) in vicinity of plant discharge area (Ial-Ia3).
3 samples of same species in areas not influenced by plant discharge (Ia4-la6).
i l
l
TABLE 3.12-1 (Continued) 9 RADIOLOGICALENVIRONMENTALMONITORkNGPROGRAM k
Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locations, Collection Frequency of Analysis n
r-d
- b. Food Products Samples of 3 different kinds of Monthly during growing Gamma isotopic and broad leaf vegetation grown near season.
1-131 analysis.
m the site boundary at 2 different g
locations of highest predicted q
annual average groundlevel D/Q (Ibl-Ib6).
d I sample of each of the similar Monthly during growing Gamma isotopic and broad leaf vegetation grown 15-season.
I-131 analysis.
30 km distant in the least prevalent wind direction (Ib7-R.
I b9 )'.
a f
a it a
E O
_1
TABLE 3.12-1 (Continued) g TABLE NOTATION
~
r-
.g a
The code in parentheses, e.g., DR1, A1, defines generic sample locations in this specification that can be d
used to identify the specific locations in the map (s) and table in the ODCM.
Specific parameters of distance and direction sector from the central point between the two containment buildings and additional n
C description where pertinent is provided for each sample location in Table 3.12-1, and in a table and 7
figure (s) in the ODCM.
Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specifica-tions for Nuclear Pcwer Plants, October 1978", and to Radiological Assessment Branch Technical Position, Revision 1, November 1979.
Deviations are permitted from the required sampling schedule if specimens are E
unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction Q
of automatic sampling equipment.
If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report.
It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.
In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program.
Identify the W
cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining samples in the next Annual Radiological Environmental Operating Report and also include in the report a y
revised figure (s) and table for the ODCM reflecting the new location (s).
b One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate contin-uously may be used in placa of, or in addition to, integrating dosimeters.
For the purposes of this table, a thermoluminesccnt dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.
Film badges shall not be used as dosimeters for measur-ing direct radiation. The frequency of analysis or readout for TLD systems will depend upon the character-(
istics of the specific system used and should be selected to obtain optimum dose information with minimal fading. Due to the geographical-limitations, 9 sectors are monitored around the Calvert Cliffs Nuclear
=
Power Plant.
oo c
Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after E
sampling to allow for radon and thoron daughter decay.
If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed y
on the individual samples.
TABLE 3.12-1 (Continued)
'y TABLE NOTATION (Continued)
N
- =
d Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that g
may be attributable to the effluents from the facility.
8 A composite sample.is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is e
representative of the liquid flow. -In this program, composite sample aliquots shall be collected at e
time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.
R.
N a
it a
E L8
2 TAllLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES
.9 r-M REPORTING LEVELS Hi b
Airborne Particulg)te Water Fish & Invertebrates Milk Food Products or Gases (pCi/m (pC1/kg, wet)
(pCl/l)
(pCi/kg, wet)
Q Analysis (pCi/l)
H-3 20,000*
2 Q
Mn-54 1,000 30,000 l
Fe-59 400 10,000
.l Co-58 1,000 30,000 W
Co-60 300 10,000 z-M Zn-65 300 20,000 b
Zr-Nb-95 400 1-131 2
0.9 3
100 Cs-134 30 10 1,000 60 1,000 Cs-137,
30 20 2,000 70 2,000
'[
Ba-La-140 200 300 5
{
'For drinking water samples. This is a 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/l g
may be used.
L ___
TABLE 4.12-1 o
$p DETECTION CAPABILITIES FOR ENVIILONMENTAL SAMPLE ANALYSISa,b a
LOWER LIMIT OF DETECTION (LLD)c
.I Airborne Particulg)te Fish & Invertebrates Milk Food Products Sediment Water or Gases (pCi/m (pCi/kg, wet)
(pCi/l)
(pCi/kg, wet)
(pCi/kg, dry)
Analysis (pCi/l).
Gross Beta 4
0.01 H-3 2000*
Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 d
1-131 I
0.07 1
60 Cs-13's 15 0.05 130 15 60 150 Cs-137, 18 0.06 150 18 80 180 Ba-La-140 15 15 alf no drinking water pathway exists, a value of 3000 pCi/l may be used.
a o
TABLE 4.12-1 (Continued)
TABLE NOTATION a This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the. Annual Radiological Environmental Operating Report, i
b Required detection capabilities for thermoluminescent dosimeters used for I-environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.
c The LLD is defined, for purposes of these specifications, as the smallest concentration
- of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
LLD=
E*
V 2.22 Y
exp (-A At)
Where:
LLD is the "A priori" lower limit of detection as defined above, as picocuries per unit mass or volume, i
sb s the standard deviation of the background counting rate or of the counting rate of a blan < sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, Y is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, i
Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and at for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Typical values of E, V, Y and at should be used in the calculation.
CALVERT CLIFFS UNIT 1 3/4 12-10 Amendment No.100
TABLE 4.12-1 (Continued)
TABLE NOTATION It should be recognized that the LLD is defined as an a priori (before the. fact) limit representing the capability of a measurement system and not as an a posteriori(after
~
the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report, d LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.
CALVERT CLIFFS UNIT 1 3/412-11 Amendment No.100
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify within a dis-tance of 8 km (5 miles) the location in each of the 9 meteorological sectors ofthenearestmi}kanimal l the nearest residence and the nearest garden
- of (500 ft ) producing broad leaf vegetation. (For elevated greater than 50 m releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify within a distance of 5 km (3 miles) the locations in each of the 9 meteorological sectors of all milk animals and all gardens of greater than 50 m2 producingbroadleafvegetation.)
APPLICABI! ! T,Y.,:
At all times.
ACTICM:
With a land use census identifying a location (s) that yields a a.
. calculated dose or dose commitment greater than the values currently being calculated, identify the new location (s) in the next Annual Radiological Environmental Operating Report.
b.
With a land use census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) to the radiological environmental monitoring program within 30 days. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.
Identify the new location (s) in the next Annual Radiological Environmental Operating Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.12.2 The land census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agri-cultural authorities.
The results of the land use census shall be included in the Annual Radiological Environmental Operating Report.
- Broad leaf vegetation sampling of at least three dif-ferent kinds of vegetation may be performed at the site boundary in each of two different direction sec-tors with the highest predicted D/Qs in lieu of the garden census.
Specifica-tions for broad leaf vegetation sampling in Table 3.12.1.4b shall be followed, including analysis of control samples.
CALVERT CLIFFS - UNIT 1 3/4 12-12 Amendment No. 100
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING INTERLABORATORY COMPARIS0N PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by Table 3.12-1.
APPLICABILITY:
At all times.
ACTION:
a.
With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM.
A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.
CALVERT CLIFFS - UNIT 1 3/4 12-13 mendment No. 100
l 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological environmental monitoring program required by this speci-fication provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures to MEMBERS OF THE PUBLIC resulting from the plant operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.
Program changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are
. tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 4.12-1 are considered optimum for routine environmental measurements in industrial laboratories.
It shotid be recognized that the LLD is defined as an a_ priori (before the fact) limit representing the capability of a measurement system and not as an a_ posteriori (after the fact) limit for a particular measurement.
Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manual HASL-300 (revised annually), Currie, L.
A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radio-chemistry," anal. Chem. 40,586-93(1968), and Hartwell, J. K., " Detection Limits for RadioanalyticaT Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of areas at and beyond the SITE B0UNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.
Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made:
- 1) 20% of the garden was used for growing broad leaf vegetatiog (i.e., similar to lettuce and cabbage), and 2) a vegeta-tion yield of 2 kg/m'.
CALVERT CLIFFS - UNIT 1 B 3/4 12-1 Amendment No.100
}
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Compari-son Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environ-mental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
Il CALVERT CLIFFS - UNIT 1 B 3/4 12-2 Amendment No. 100
5.0 DESIGN FEATURES 5.1 SITE MAP DEFINING THE SITE B0UNDARY AND EFFLUENT RELEASE POINTS 5.1.1 A map of the Calvert Cliffs Nuclear Power Plant site identifying the major plant structures as well as defining the radioactive effluent release points and the SITE B0UNDARY is shown in Figure 5.1-1.
LOW POPULATION ZONE 5.1.2 The low population zone shall be as shown in Figure 5.1-2.
5.2 CONTAINMENT CONFIGURATION 5.2.1 The reactor containment building is a steel lined, reinforced concrete
' building of cylindrical shape, with a dome roof and having the following design features:
a.
Nominal inside diameter = 130 feet.
b.
Nominal inside height = 181 2/3 feet, c.
Minimum thickness of concrete walls = 3 3/4 feet, d.
Minimum thickness of concrete roof = 31/4 feet.
e.
Minimum thickness of concrete floor pad = 10 feet.
f.
Nominal thickness of steel liner = 1/4 inches.
6 g.
Net free volume = 2 x 10 cubic feet.
CALVERT CLIFFS - UNIT 1 5-1 Amendment No. 100
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CALVERT CLIFFS NUCLEAR POWER PLANT UNIT N05. 1 AND 2 APPENDIX B PART I ENVIRONMENTAL TECHNICAL SPECIFICATIONS
' FACILITY OPERATING LICENSE NOS. DPR-53 AND DPR-69 NOTE
-Section 3.0, Environmental Surveillance and Monitoring, has been deleted. Any other portion of the Appendix B Part I Environ-mental Technical Specifications dealing with Environmental Nonitoring is hereby super-seded by Appendix A Technical Specification Section 3/4.12.
When the Radiological Effluent Technical Specifications (RETS) are fully implemented, Appendix B, Part I, will be deleted in its entirety.
i ISSUED BY THE U. S. NUCLEAR REGULATORY COMMISSION l
Calvert Cliffs Unit 1 Amendment No. 23, /$,100 D
TABLE OF CONTENTS Section DESCRIPTION Page 1.0 Definitions 1.0 2.0 Limiting Conditions for Operation 2.1-1 2.2 Chemical Limitations 2.2-1 2.3 Radioactive Effluents 2.3-1 3.0 Deleted 3.1 -1 l
3.2 Deleted 3.2-1 l
4.0 Special Surveillance and Study Activities 4.1 -1 5.0 Administrative Controls 5.0 5.1 Responsibility 5.1-1 5.2 Organization 5.2-1 5.3 Review and Audit 5.3-1 5.4 Action to be Taken if a Limiting Condition for Operation is Exceeded 5.4-1 5.5 Operating Procedures 5.5-1 5.6 Plant Reporting Requirements 5.6-1 5.7 Records Retention 5.7-1 CALVERT CLIFFS - UNIT 1 Amendment No. 57. Jo,100
3.0 ENVIRONMENTAL SURVEILLANCE AND MONITORING l
i DELETED 4
i L
l i
f l
CALVERT CLIFFS - UNIT 1 3.1-1 Amendment No. 49,79.100 L
3.2 RADIOLOGICAL ENVIRONMENTAL MONITORING DELETED I
l CALVERT CLIFFS - UNIT I 3.2-1 Amendment No.
100 (nextpageis4.11) g L
+f g
UNITED STATES 8
NUCLEAR REGULATORY COMMISSION g
f E WASHINGTON, D. C. 20655
%,...../
BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 License No. DPR-69 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (thelicensee)datedOctober 11, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
k
.t
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Facility Operating License No. DPR-69 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised throuch Amendment No. 82, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION N h_=[er'
{
James R. Mil 7
ief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 22, 1985 l
L
ATTACHMENT TO LICENSE AMENDMENT NO. 82 FACILTIY OPERATING LICENSE NO. DPR-69 DOCKET NO. 50-318 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are provided to maintain document completeness.
Appendix A Remove Pages Insert Pages I
VIIIa XIII XIII XIV XIV 1-1 1-1 1-6 1-6 1-7 1-7 1-8 1-8 1-9(renumbered) 1-10 3/4 12-1 through 3/4 12-13 8 3/4 9-3 8 3/4 9-3 B 3/4 12-1 B 3/4 12-2 5-1 5-1 5-2 5-2 Appendix B Appendix B, Part I title page Appendix B, Part I title page Table of Contents Table of Contents 3.1-1 3.1-1 3.2-1 3.2-1 3.2-2 Figure 3.2-1 Table 3.2-1 (3 pages)
Table 3.2-2 Y
l INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS Defined Terms...............................................
1-1 Thermal Power...............................................
1-1 Rated Thermal Power.........................................
1-1 Operational Mode............................................
1-1 Action......................................................
1-1 Operable - Operability......................................
1-1 Reportable Event............................................
1-2 Con tai nmen t I n teg ri ty.......................................
1 -2 Channel Ca l i bra t ion.........................................
1 -2 Channel Check...............................................
1-3 Channel Functional Test.....................................
1-3 Core Alteration.............................................
1-3 Shutdown Margin.............................................
1-3 Iden ti fi ed Lea ka ge.......................................... 1 -4 Unidentified Leakage........................................
1-4 Pres sure Boundary Lea kage................................... 1 -4 Controlled Leakage..........................................
1-4 Az i mu tha l Powe r T i l t........................................ 1 -4 pose Equivalent 1-131.......................................
1-4 E-Average Di si ntegra tion Ene rgy............................. 1 -5 Staggered Test Basis........................................
1-5 Frequency Notation..........................................
1-5 Axial Shape Index...........................................
1-5 Unrodded Planar Radial Peaking Factor - F Reactor Trip Sys tem Response Time.........y.................
1-5 x
1-6 Engineered Safety Fea ture Response Time.....................
1-6 P hy s i c s T e s t s...............................................
1 - 6 Unrodded Integrated Radial Peaking Factor - Fr.............. 1-6 Gaseous Radwaste Treatment System...........................
1-6 Member (s) of the Public.....................................
1-6 Offsite Dose Calculation Manual (0DCM)......................
1-6 Process Control Program (PCP)...............................
1 -7 P u rg e - P u rg i n g...............................................
1 - 7 S i t e B o u n d a ry...............................................
1 - 7 So l i d i f i c a t i o n..............................................
1 - 7 S o u rc e C h e c k................................................
1 - 7 Unrestricted Area...........................................
1-7 Ventilation Exhaust Treatment System........................
1-7 Venting.....................................................
1-8 CALVERT CLIFFS - UNIT 2 1
Amendment No.9,JB,U,75 82
INDEX SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION PAGE 2.1 SAFETY LIMITS Reactor Core................................................
2-1 Reactor Coolant System Pressure.............................
2-1 2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor T ri p Se tpoi nts......................................
2-6 BASES SECTION PAGE 2.1 SAFETY LIMITS R ea c to r C o r e................................................
B 2-1 Reactor Coola nt Sys tem Pres sure.............................
B 2-3 2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor Trip Setpoints......................................
B 2-4 CALVERT CLIFFS - UNIT 2
,I!
i l
j INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.12 RADIGLOGICAL ENVIRONMENTAL MON!TORING 3/4.12.1 MONITORING PR0 GRAM...................................
3/4 12-1 3/4.12.2 LAND USE CENSUS.......................................
3/4 12-12 3.4.12.3 II:TERLABORATORY COMPARISON PROGRAM.................... 3/4 12-13 I
4 e
l i
l 82 CALVERT CLIFFS - UNIT 2 yggga Amendment No.
r I
f
INDEX BASES SECTION PAGE 3/4.9.5 C OMMU N I C AT I ONS........................................... B 3/ 4 9 - 1 3/4.9.6 REFUELING MACHINE OPE RABILITY............................ B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING............... B 3/4 9-2 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION................. B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM................. B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT FUEL POOL WATER LEVEL............................ B 3/4 9-3 3/4.9.12 SPENT FUEL POOL VENTILATION SYSTEM.......................
B 3/4 9-3 3/4.9.13 SPENT FUEL CASK HANDLING CRANE...........................
B 3/4 9-3 3/4.9.14 CONTAINMENT VENT ISOLATION VALVES........................
B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN..........................................
B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION. AND POWER DISTRIBUTION LIMITS... B 3/4 10-1 3/4.10.3 NO FLOW TESTS............................................
B 3/4 10-1 3/4.10.4 CENTER CEA MISALIGNMENT..................................
B 3/4 10-1 l
3/4.10.5 COOLANT CIRCULATION...................................... B 3/4 10-1 3/4.12 RADIOLOGICAL ENVIRONMENTAL t10NITORING 3/4.12.1 HONITORING PR0 GRAM....................................... B 3/4 12-1 3/4.12.2 LAND USE CENSUS.......................................... B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARISON PROGRA'4....................... B 3/4 12-2 CALVERT CLIFFS - LNIT 2 XIII Amendment No. 6. JJ. 38.82
z.
INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE Map Defining the Site Boundary and Effluent Release Points..............................................
5-1 Low Population Zone...........................................
5-1 5.2 CONTAINMENT Configuration.................................................
5-1 Design Pressure and Temperature...............................
5-4
- 5. 3 REACTOR CORE Fuel Assemb11es...............................................
5-4 Control El ement As sembl i es.................................... 5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature...............................
5-4 Vo1ume........................................................
5-5 5.5 METEOROLOGICAL TOWER LOCAT!0N.................................
5-5 5.6 FUEL STORAGE Criticality...................................................
5-5 Drainage......................................................
5-5 Capacity....................................................... 5-5 5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS..........................
5-5 CALVERT CLIFFS - UNIT 2 XIV Amendment No. 82
r 1.0 DEFINITIONS DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications.
THERMAL POWER 1.2 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
RATED THERMAL POWER 1.3 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2700 MWt.
OPERATIONAL MODE 1.4 An OPERATIONAL MODE shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.
ACTION 1.5 ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions.
OPERABLE - OPERABILITY 1.6 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),
implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other required auxiliary equipment that are required for the system, sub-system, train, component or device to perform its function (s) are also capableofperformingtheirrelatedsupportfunction(s).
CALVERT CLIFFS-UNIT 2 1-1 Amendment No.
p, 82
DEFINITIONS REPORTABLE EVENT 1.7 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:
- 1. 8.1 All penetrations required to be closed during accident conditions are either:
a.
Capable of being closed by an OPERABLE containment automatic isolation valve system, or b.
Closed by manual valves, blind flanges, or deactivated
. automatic valves secured in their closed positions.
except as provided in Table 3.6-1 of Specification 3.6.4.1.
1.8.2 All equipment hatches are closed and sealed, 1.8.3 Each airlock is OPERABLE pursuant to Specification 3.6.1.3, 1.8.4 The containment leakage rates are within the limits of Specification 3.6.1.2, and 1.8.5 The sealing mechanism associated with each penetration (e.g., welds, bellows or 0-rings) is OPERABLE.
CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequen-tial, overlapping or total channel steps such that the entire channel is calibrated.
CALVERT CLIFFS-UNIT 2 1-2 Amendment No. ft, 75 humummesmusums d ur mi s-m is i
ii, i,,,memmmeimmmm.immi
4 DEFINITIONS T - AVERAGE DISINTEGRATION ENERGY 1.20 f shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MEV) for isotopes, other than iodines, with half lives greater than 15 1
minutes, making up at least 95% of the total non-iodine activity in the coolant.
STAGGERED TEST BASIS 1.21 A STAGGERED TEST BASIS shall consist of:
a.
A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals, and b.
The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
FREQUENCY NOTATION 1.22 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.
AXIAL SHAPE INDEX 1.23 The AXIAL SHAPE INDEX (Y,) is the power level detected by the lower excore nuclear instrument detectors (L) less the power level detected by the upper excore nuclear instrument detectors (U) divided by the sum of these power _ levels. The AXIAL SHAPE INDEX (Y,) used for the trip and I
pretrip signals in the reactor protection system is the above value (Y )
p l
modified by an appropriate multiplier (A) and a constant -($) to determine the true core axial power distribution for that channel.
YI
- AYE+B YE*
UNRODDED PLANAR RADIAL PEAKING FACTOR - F,y 5
the peak to average power density of the individual,the maximum rat 1.24 The UNRODDED PLANAR RADIAL PEAKING FACTOR is e
fuel rods in any of the j ij unrodded horizontal planes, excluding tilt.
CALVERT CLIFFS-UNIT 2 1-5 Amendment No. 9
DEFINITIONS REACTOR TRIP SYSTEM RESPONSE TIME 1.25 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel senso/
until electrical power is interrupted to the CEA drive mechanism.
ENGINEERED SAFETY FEATURE RESPONSE TIME 1.26 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall.be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.
PHYSICS TESTS 1.27 PHYSICS TEST shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and
- 1) described in Chapter 13.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.
UUR00DED INTEGRATED RADIAL PEAKING FACTOR - Fr 1.28 The UNRODDED INTEGRATED RADIAL PEAKING FACTOR is the ratio of the peak pin power to the average pin po.rer in an unrodded core, excluding tilt.
SASEQUS RADWASTE TREATMENT SYSTE!1 1.29 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 environ-ment.
MEMBER (S) 0F THE PUBLIC 1.30 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupa-tionally associated with the plant. This category does not include employees of the utility, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
OFFSITE DOSE CALCULATION MANUAL (0DCM) 1.31 The 0FFSITE DOSE CALCULATION MANUAL shall contain the current method-ology and parameters used in the calculation of offsite doses due to radio-active gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the environ-mental radiological monitoring program.
CALVERT CLIFFS - UNIT 2 1-6 Amendment No. 6,18 2, 82
DEFINITIONS PROCESS CONTROL PROGRAM (PCP) 1.32 The PROCESS CONTROL PROGRAM shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Part 20,10 CFR Part 71 and Federal and State and local regulations governing the disposal of the radioactive waste.
PURGE - PURGING 1.33 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
SITE BOUNDARY 1.34 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
SOLIDIFICATION 1.35 SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.
SOURCE CHECK 1.36 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
UNRESTRICTED AREA 1.37 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
VENTILATION EXHAUST TREATMENT SYSTEM i
1.38 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through char-coal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
CALVERT CLIFFS - UNIT 2 1-7 Amendment No. 82
DEFINITIONS VENTING 1.39 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
1
.1 CALVERT CLIFFS - UNIT 2 1-8 Amendment No.
82
, _.. ~.... _ _ _,. - _,
TABLE 1.1 OPERATIONAL MODES REACTIVITY
% RATED AVERAGE COOLANT MODE CONDITION, K THERMAL POWER
- TEMPERATURE eff 1.
POWER OPERATION
> 0.99
> 5%
> 300*F 2.
STARTUP
> 0.99
< 5%
> 300*F 3.
HOT STANDBY
< 0.99 0
> 300'F 4.
HOT SHUTOOWN
< 0.99 0
300'F> T
> 200*F avg 5.
COLD SHUTDOWN
< 0.99 0
< 200*F 6.
REFUELING **
< 0.95 0
< 140*F Excluding decay heat.
Reactor vessel head unbolted or removed and fuel in the vessel.
CALVERT CLIFFS - UNIT 2 1-9 Amendment No. 82 l
-r-r
v c-e n
s ----
e--
TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY S
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W At least once per 7 days.
M At least once per 31 days.
Q At least once per 92 days.
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.
J l
- CALVERT CLIFFS - UNIT 2 1-10
. Amendment No.
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.
APPLICABILITY: At all times.
ACTION:
a.
With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission in the Annual Radiological Environmental Operating Report a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
b.
With the level of radioactivity as the result of plant effluents in an environmental sample at a specified location exceeding the reporting levels of Table 3.12-2, prepare and submit to the Commission within 30 days after receiving the sample analysis, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents. When more than one of the radionuclides in Table 3.12-2 are detected in the sample, this report shall be submitted if:
concentration (1)
+ concentration (2)
+.. > 1. 0 reporting level (1) rew rtinn level (2)
This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, l
the condition shall be reported and described in the Annual Radi-l ological Environmental Operating Report.
c.
With fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1, identify loca-tions for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.
i l
The specific locations from which samples were unavailable may then be deleted from the monitoring program.
Identify the cause of the unavailability of samples and identify the new location (s) for obtaining the replacement samples in the next Annual Radiolog-ical Environmental Operating Report.
i I
CALVERT CLIFFS - UNIT 2 3/4 12-1 Amendment No. 82 l
i 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING MONITORING PROGRAM LIMITING CONDITION FOR OPERATION d.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.
CALVERT CLIFFS - UNIT 2 3/4 12-2 Amendment No. 82
i TABLE 3.12-1 g
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM G
Q Exposure Pathway flumber of Representative Sampling and Type and Frequency and/or Sample Samples and Sample locations, Collection Frequency of Analysis P
~
b 4
- 1. DIRECT RADIATION 23 routine monitoring stations At least Quarterly Gamma dose at least (DRI-DR23) either with two or quarterly.
more dosimeters or with one E
instrument for measuring and
~
recording dose rate continuously, placed as follows:
m an inner ring of stations, one in each meteorological sector in the general area of the SITE B0UNDARY (DRI-DR9);
M
^
an outer ring of stations, one in C
each meteorological sector in the L,
6-to 8-km range from the site (DR10-DRl8);
the remaining stations (DR19-DR23) to be placed in special interest areas such as population centers,
{
nearby residences, schools, and in 1 area to serve as a control station.
a
- 2. AIRBORNE o
Radioiodine and Samples from 5 locations (Al-AS):
Continuous sampler Radiciodine Cannister Particulates operation with sample I-131 analysis weekly.
g 3 samples (Al-A3) from close collection weekly, or to the 3 SITE BOUNDARY more frequently if Particulate Sampler:
locations, in different required by dust Gross beta radioactiv-sectors of the highest loading.
ity analysis following
TABLE 3.12-1 (Continued) h RADIOLOGICAL ENVIRONMENTAL M_ONITORING PROGRAM Exposure Pathway Humber of Representative Sampling and Type and Frequency and/or Sample __
Samples and Sample Locations, Collection Frequency of Analysis n
Cq calculated annual average filter change;c m
ground-level D/Q.
Gamg isotopic anal-ysis of composite E
1 sample (A4) from the vicinity (by location) y of a coninunity having the high-quarterly.
est calculated annual average m
ground-level D/Q.
I sample (A5) from a control location, as for example 15-30 km distant and in the least R
prevalent wind direction.
C
- 3. WATERBORNE L.
- a. Surface 1 sample at intake area (Wai)
Composite sample Gamna isotopic anal-1 sample at discharge area over 1-month period' ysisd monthly. Compos-(Wa2) ite for tritium anal-ysis quarterly.
b.. Sediment from I sample from downstream area Semiannually Gamm isotopic anal-k shoreline with existing or potential ysis semiannually.
R recreational value (Wb1).
?,
- 4. INGESTION P
- a. Fish and 3 samples of commercially and/or Sample in season, or Gammaisgtopic Invertebrates recreationally important species semiannually if they analysis on edible (2 fish species and 1 inverte-are not seasonal.
portions.
N brate species) in vicinity of plant discharge area (Ial-la3).
3 samples of same species in areas not influenced by plant discharge (la4-la6).
TABLE 3.12-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locations, Collection Frequency of Analysis c3 r-kj
- b. Food Products Samples of 3 different kinds of Monthly during growing Gamma isotopic and d
broad leaf vegetation grown near season.
1-131 analysis.
v5 the site boundary at 2 different g
locations of highest predicted annual average groundlevel D/Q (Ibl-Ib6).
n, d
I sample of each of the similar Monthly during growing Gamma isotopic and broad leaf vegetation grown 15-season.
I-131 analysis.
30 km distant in the least prevalent wind direction (Ib7-se Ib9).
m R
a n
E
T_ABLE 3.12-1 (Continued) n TABLE NOTATION
?
ig a
The code in parentheses, e.g., DR1, A1, defines generic sample 1ccations in this specification that can be used to identify the specific locations in the map (s) and table in the 00CM.
Specific parameters of distance and direction sector from the central point between the two containment buildings and additional n
C description where pertinent is provided for each sample location in Table 3.12-1, and in a table and 5
figure (s) in the ODCM.
Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specifica-tions for Nuclear Power Plants, October 1978", and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are E
unobtainable due to ci'cumstances such as hazardous conditions, seasonal unavailability, and malfunction G
of automatic sampling squipment.
If specimens are unobtainable due to sampling equipment malfunction, effort shall be made 20 complete corrective action prior to the end of the next sampling period. All to deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report.
It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.
In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program.
Identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining samples in the next Annual Radiological Environmental Operating Report and also include in the report a y
revised figure (s) and table for the ODCM reflecting the new location (s).
b One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate contin-i uously may be used in place of, or in addition to, integrating dosimeters.
For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.
Film badges shall not be used as dosimeters for measur-2 ing direct radiation. The frequency of analysis or readout for TLD systems will depend upon the character-T istics of the specific system used and should be selected to obtain optimum dose information with minimal E
fading. Due to the geographical limitations, 9 sectors are monitored around the Calvert Cliffs Muclear
{
Power Plant.
1
- s o
c Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more af ter 5
sampling to allow for radon and thoron daughter decay.
If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gansna isotopic analysis shall be performed g
on the individual samples.
TABLE 3.12-1 (Continued) j[
TABLE NOTATION (Continued)
N
- o
-4 d
Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
r-8 A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is e
representative of the liquid flow.
In this program, composite sample aliquots shall be collected at c:
${
time intervals that are very short (e.g., hotriy) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.
s, M
u a
f l
1 2
P.
E
TABLE 3.12-2 IIEPoltTING LEVELS Folt itAD10 ACTIVITY CONCENTilATIONS IN ENVitt0NMENTAL SAMPLES
.9 r-M ItEPORTING LEVELS 5
b Water Airborne Particulg)te Fish & Invertebrates Milk Food Products
]
Analysis (pCi/l) or Gases (pCi/in (pCi/kg, wet)
(pCi/l)
(pCi/kg, wet)
H-3 20,000*
z Q
Mn-54 1,000 30,000 ro Fe-59 400 10,000 Co-58 1,000 30,000 W
Co-60 300 10,000 M
Zn-65 300 20,000 Ex>
Zr-Nb-95 400 1-131 2
0.9 3
100 Cs-134 30 10 1,000 60 1,000
(
50 20 2,000 70 2,000
- s k
Ba-La-140 200 300 5
'For drinking water sarnples. This is a 40 CFil Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/l rnay be used.
to O
I g
TABLE 4.12-1 o
h DETECilON cal' ABILITIES FOR ENVillONMENTAL SAMPLE ANALYSISa,b fi p
LOWE'll LIMIT OF DETECTION (LLD)c Airborne Particulg)te Water Fish & Invertebrates Milk Food Products Sediment Analysis (pCi/l) or Cases (pCi/m (pCi/kg, wet)
(pCl/l)
(pCi/kg, wet)
(pCi/kg. dry)
Gross Beta 4
-l Fe-59 30 260 Co-58,60 15 130 ei Zn-65 30 260 m
Zr-Nb-95 15 d
I-131 I
0.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs-137, la 0.06 150 18 80 180 Ba-La-140 15 15 l
?I l
ti 1
'If no drinking water pathway exists, a value of 3000 pCi/l may be used.
a l
if l
l 0
1 5
l
TABLE 4.12-1 (Continued)
TABLE NOTATION
)
a This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.
b Required detection. capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.
c The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
LLD=
E*
V 2.22 Y
exp (- A at)
Where:
LLD is the "A priori" lower limit of detection as defined above, as picocuries per unit mass or volume, i
sb s the standard deviation of the background counting rate or of the counting rate of a blaw sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picoeurie, Y is the fractional radiochemical yield, when applicable, 1 is the radioactive decay constant for the particular radionuclide, and at for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Typical values of E, V, Y and at should be used in the calculation.
CALVERT CLIFFS UNIT 2 3/4 12-10 Amendment No. 82
TABLE 4.12-1 (Continued)
TABLE NOTATION It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori(af ter the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.
d LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.
i l
i l
l CALVERT CLIFFS UNIT 2 3/4 12-11 Amendment No. 82 l
l l
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING i
LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify within a dis-tance of 8 km (5 miles) the location in each of the 9 meteorological sectors ofthenearestmi}kanimal the nearest residence and the nearest garden
- of 2
(500 ft ) producing broad leaf vegetation. (For elevated greater than 50 m releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify within a distance of 5 km (3 miles) the locations in each of the 9 meteorological sectors of all milk animals and all gardens of greater than 50 m2 producing broad leaf vegetation.)
APPLICABILITY: At all times.
ACTION:
a.
With a land use census identifying a location (s) that yields a calculated dose or dose comitment greater than the values currently being calculated, identify the new location (s) in the next Annual Radiological Environmental Operating Report.
b.
With a land use census identifying a location (s) that yields a calculated dose or dose comitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) to the radiological environmental monitoring program within 30 days.
The sampling location (s), excluding the control station location, having the lowest calculated dose or dose l
comitment(s), via the same exposure pathway, may be deleted from l
this monitoring program after October 31 of the year in which this land use census was conducted.
Identify the new location (s) in the next Annual Radiological Environmental Operating Report and also include in the report a revised figure (s) and table for the ODCM j
reflecting the new location (s).
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
lSURVEILLANCEREQUIREMENTS 4.12.2 The land census shall be conducted during the growing season at least once per 12 months using that infomation that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agri-cultural authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report.
I
- Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sec-tors with the highest predicted D/Qs in lieu of the garden census. Specifica-tions for broad leaf vegetation sampling in Table 3.12.1.4b shall be followed, including analysis of control samples.
CALVERT CLIFFS - UNIT 2 3/4 12-12 Amendment No. 82
e 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING e
INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the g
Commission, that correspond to samples required by Table 3.12-1.
APPLICABILITY: At all times.
ACTION:
a.
With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the' ODCM.
A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.
CALVERT CLIFFS - UNIT 2 3/4 12-13 Amendment No. 82
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological environmental monitoring program required by this speci-fication provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures to MEMBERS OF THE PUBLIC resulting from the plant operation. This monitoring program implementsSection IV.B.2 of A,,,*ndix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.
Program changes may be initiated based on operational experience.
~
The required detection capabilities for environmental sample analyses are
. tabulated in terms of the lower limits of detection (LLDs). The LLDs required b) Table 4.12-1 are considered optimum for routine environmental measurements in industrial laboratories.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a_ posteriori (after the fact) limit for a particular measurement.
Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radio-chemistry," anal. Chem. 40, 586-93 (1960), and Hartwell, J. K., " Detection Limits for Radioanalyticai Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census.
The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50 Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for ansumption by a child.
To determine this minimum garden size, the following assumptions were made:
- 1) 20% of the garden was used for growing broad leaf vege;ation (i.e., similar to lettuce and cabbage), and 2) a veoeta-tion yield of 2.kg/m2 l
CALVERT CLIFFS - UNIT 2 B 3/4 12-1 Amendment No. 82
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Compari-son Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environ-mental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
s x
.c I
l l CALVERT CLIFFS - UNIT 2B 3/4 12-2 Amendment No. 82
REFUELING OPERATIONS BASES 3/4.9.10 and 3/4.9.11 WATER LEVEL-REACTOR VESSEL AND SPENT FUEL P0OL WATER LEVEL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly.
The minimum water depth is consistent with the assumptions of the accident analysis.
3/4.9.12 SPEllT FUEL POOL VENTILATION SYSTEM The limitations on the spent fuel pool ventilation system ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.
3/4.9.13 SPENT FUEL CASK HANDLING CRANE The restriction on movement of the spent fuel shipping cask within one cask length of any fuel assembly ensures that in the event this load is dropped (1) the stored spent fuel assemblies will not be damaged, and (2) any possible distortion of fuel in the storage racks will not result is a critical array.
3/4.9.14 CONTAINMENT VENT ISOLATION VALVES The OPERABILITY and closure restrictions on the containment vent isolation valves are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressuriza-tion potential while in the REFUELING MODE.
~
CALVERT CLIFFS - UNIT 2 B 3/4 9-3 Amendment No. 82
5.0 DESIGN FEATURES 5.1 SITE MAPDEFININGTHESITEB0UNDARYANDEFFLUENTRELEASEPdINTS 5.1.1 A map of the Calvert Cliffs Nuclear Power Plant site identifying the major plant structures as well as defining the radioactive effluent release points and the SITE BOUNDARY is shown in Figure 5.1-1.
LOW POPULATION ZONE 5.1.2 The low population zone shall be as shown in Figure 5.1-2.
5.2 CONTAINMENT CONFIGURATION 5.2.1 The reactor containment building is a steel lined, reinforced concrete building of cylindrical shape, with a dome roof and having the following design features:
a.
Nominal inside diameter = 130 feet.
b.
Nominal inside height = 181 2/3 feet.
c.
Minimum thickness of concrete walls = 3 3/4 feet.
d.
Minimum thickness of concrete roof = 31/4 feet, e.
Minimum thickness of concrete floor pad = 10 feet.
f.
Nominal thickness of steel liner = 1/4 inches.
6 g.
Net free volume = 2 x 10 cubic feet.
CALVERT CLIFFS - UNIT 2 5-1
- Amendment No. 82
.c RELEASE / s.
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CALVERT CLIFFS SITE BOtjNCARY MAP y
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CALVERT CLIFFS NUCLEAR POWER PLANT UNIT N05. 1 AND 2 APPENDIX B PART I ENVIRONMENTAL TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSE NOS. OPR-53 AND DPR-69 a
NOTE Section 3.0, Environmental Surveillance and Monitoring, has been deleted. Any other portion of the Appendix 8 Part ! Environ-mental Technical Specifications dealing with Environmental fionitoring is hereby super-seded by Appendix A Technical Specification Section 3/4.12.
When the Radiological Effluent Technical Specifications (RETS) are fully implemented, Appendix B, Part I, will be deleted in its entirety.
ISSUED BY THE U. S. t;UCLEAR REGULATORY COW 11SSION Calvert Cliffs Unit 2 Amendment No. 7, 33,82
TABLE OF CONTENTS Section DESCRIPTION Page 1.0 Definitions 1.0 2.0 Limiting Conditions for Operation 2.1-1 2.2 Chemical Limitations 2.2-1 2.3 Radioactive Effluents 2.3-1 3.0 Deleted 3.1-1 l
3.2 Deleted 3.2-1 l
4.0 Special Surveillance and Study Activities 4.1-1 5.0 Administrative Controls 5.0
.5.1 Responsibility 5.1-1 5.2 Organization 5.2-1 5.3 Review and Audit 5.3-1 5.4 Action to te Taken if a Limiting Condition for Operatior is Exceeded 5.4-1 5.5 Operating F rocedures 5.5-1 5.6 Plant Repor ti ig Requirements 5.6-1 5.7 Records Reter.: ion 5.7-1 CALVERT CLIFFS - UNIT 2 Amendment No. }J, 3). 82
i 3.0 ENVIRONMENTAL SURVEILLANCE AND MONITORING 4
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i CALVERT CLIFFS - UNIT 2 3.1-1 Amendment No. 33 53/,82 1
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3.2 RADIOLOGICAL ENVIRONMENTAL MONITORING 4
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J CALVERT CLIFFS - UNIT 2 3.2-1 Amendment No. 82 (nextpageis4.1-1)
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