ML20117L344
| ML20117L344 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/04/1996 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20117L328 | List: |
| References | |
| GL-89-01, GL-89-1, NUDOCS 9609130119 | |
| Download: ML20117L344 (145) | |
Text
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ATTACHMENT (2) l l
l UNIT 1 TECHNICAL SPECIFICATIONS MARKED-UP PAGES l
i I, IV, VIII, IX, XIII, XIV 1-4 -- 1-8 3/43-42--3/43-51 1
3/4 11-1 --3/4 11-19 l
3/4 12 3/4 12-15 i
l B 3/4 3-3 B 3/411-1 -- B 3/411-6 B 3/412-1 B 3/412-2 6-6 -- 6-9 I
l i
Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant 9609130119 960904 PDR ADOCK 05000317 P
I TABLE OF CONTENTS DEFINITIONS l
SECTION PAGE m
1.0 DEFINITIONS De fi ned Terms....................
1-1 Action 1-1 Axial Shape Index..................
1-1 Azimuthal Power Til t - T,..............
1-1 l
Channel Calibration.................
1-1 Channel check....................
1-2 Channel Functional Test...............
1-2 Containment Integrity................
1-2 Controlled Leakage 1-3 Core Alteration...................
1-3 Core Operating Limits Report (COLR).........
1-3 l
Dose Equivalent I-131................
1-3 E-Average Disintegration Energy...........
1-3 Engineered Safety Feature Response Time.......
1-3 Frequency Notation 1-4 l
Gaseous Radwaste Treatment System..........
1-4 Identified Lea.kage 1-4 Member (s) Of The Public...............
1-4 Offsite Dose Calculation Manual (ODCM) 1-4 Operable - Operability 1-5 Operational Mode.......;..........
1-5 Physics Tests................_....
1-5 Pressure Boundarv Leakage..............
1-5 (PFo&ess Cbntroh Pkodran\\ (RCN \\.\\.\\. \\.\\.\\.\\.\\.\\.\\.\\ \\ \\ h!D l
Purge-Purging....................
1-6 y
Rated Thermal Power.................
1-6 L.
Reactor Trip System Response Time..........
1-6 Reportable Event 1-6 l
(j Shutdown Margin...................
1-6 l
g Site Boundary.
1-6 (S411bi hicatidn \\. 1.\\. \\..\\. \\. \\.1.\\. \\..\\. \\. \\ A.\\ \\ \\ \\1-TL)
Source Check 1-7 Staggered Test Basis 1-7 Thermal Power....................
1-7 Total Integrated Radial Peaking Factor - P,.....
1-7 Total Planar Radial Peaking Factor - FI,.......
1-7 Unidentified Leakage 1-7 Unrestricted Area..................
1-8 l
Ventilation Exhaust Treatment System 1-8 Venting.......................
1-8 l
4 CALVERT CLIFFS - UNIT 1 I
Amendment No. 186 i
TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 1
SECTION f_AGI t
A 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION........ '.
3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION...................
3/4 3-9 i
3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3-23 N
Meteorological Instrumentation 3/4 3-27 b
Remote Shutdown Instrumentation...........
3/4 3-30 Post-Accident Instrumentation............
3/4 3-33 N
Eire Detection Inrtrlnentation 3/4 3-37 l
N 5
Gayeot s Wfl n Mo it in i
f od
/4 3-2 D i
Q c id Ef ue t ni or g
)
3/4.4 REACTOR C0OLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION STARTUP And POWER OPERATION.............
3/4 4-1 HOT STANDBY.....................
3/4 4-2 Shutdown 3/4 4-4 3/4.4.2 SAFETY VALVES....................
3/4 4-6 3/4.4.3 RELIEF VALVES....................
3/4 4-7 3/4.4.4 PRESSURIZER.....................
3/4 4-9 3/4.4.5 STEAM GENERATORS 3/4 4-10 l
3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems..............
3/4 4-17 l
Reactor Coolant System Leakage 3/4 4-19 3/4.4.7 CHEMISTRY......................
3/4 4-21 3/4.4.8 SPECIFIC ACTIVITY..................
3/4 4-24 CALVERT CLIFFS - UNIT 1 IV Amendment No. 199
l l
l TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILMNCE REQUIREMENTS l
SECTION PAGE l
3/4.9.13 SPENT FUEL CASK HANDLING CRANE 3/4 9-18 l
3/4.9.14 CONTAINMENT VENT IS01.ATION VALVES..........
3/4 9-19 3/4.10 SPECIAL TEST EXCDTIONS 3/4.10.1 SHUTDOWN MARGIN...................
3/4 10-1 l
3/4.10.2 MODERATOR TEMPERATURE COEFFICIENT, CEA INSERTION i
AND POWER DISTRIBUTION LIMITS............
3/4 10-2 3/4.10.3 NO FLOW TESTS....................
3/4 10-3 3/4.10.4 CENTER CEA MISALIGNMENT...............
3/4 10-4 3/4.10.5 COOLANT CIRCULATION.................
3/4 10-5 3/4.11 RADI0 ACTIVE EFFLUENTS
( /.1 1 LIUIDEFILU TS on en ation 3
1-os
...\\.
/ 1 -5 g
qu d dw(stet at en S st m 4 16 i
(g 3/y.11MGASEOUSEFFLUENTS 4
l 4 17 o
te
. s...
ob Ghse 3
os W
8 s
odi 1, an R io u i s
N-P rti ul e
V4 1 (.3 g
l h\\
l W S...DWAST TR N SY T 3X4.J-:M>
Q4 Exp'osive Gas Mixture................
3/4
.1 1
Gas Storage Tanks..................
3/4 11
- 4. 1.
1 -1 3 4.1.4 T TA 00 E
/4 1-8 CALVERT CLIFFS - UNIT 1 VIII Amendment No. 169
TABLE OF CONTENTS i
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l
(SEChION
_PhGE }
4.1 I OG L
VIR E TAL N OR G 3/.12.
ITO ING ROG 3/ 12-l
/4. 2.2 LAN US CEN US.........
4 1 -13 1
3
.1 3
TE B0 TO C0 PAR SON R0 3/ 12-l C
l l.
02LETE l
i i
CALVERT CLIFFS - UNIT 1 IX Amendment No. 169 l
l
TABLE OF CONTENTS i
BASES i
SECTION PAGE l
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 9-3 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 9-4 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTD0WN 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 l
3/4.10.4 CENTER CEA MISALIGNMENT............... B 3/4 10-1 3/4.10.5 COOLANT CIRCULATION................. B 3/4 10-1 l
3/4.11 RADI0 ACTIVE EFFLUENTS g
j I4(
3k.1k.1\\LkQU$EIFLd(N%k.\\.\\..\\.k.k.k.\\.\\..\\Bk/4k1V 3/4.11 HSE 0VS EFFLUENTS.................. B 3/4 11h Q
- 4. 1.
B
'4 1-
% l
.1.4 T AL DO E 3
1 5 l
l i
CALVERT CLIFFS - UNIT 1 XIII Amendment No. 169
l TABLE OF CONTENTS BASES kEch0N P
1' 3 4.1 L
CAL ENV 0 TAL M0 TOR G bg 3/.12.
...B
/4
-1 N
/4. 2.2 LA US CE US 3
12 3 4.1.3 NTE B0 TO Y C PAR ON OG
...B
/4
-2 l
1 l
l l
CALVERT CLIFFS - UNIT 1 XIV Amendment No. 169
4 1.0 DEFINITIONS FREQUENCY NOTATION 1.15 The FREI)UENCY NOTATION specified for the.'perfonnance of Surveillance l
Requirements shall correspond to the intervals defined in Tahle 1.2.
GASE0US RADWASTE TREATMENT SYSTEM 1.16 A GASE0US RADWASTE TREATMENT SYSTEM is any system designed and l
installed to reduce radioactive gaseous effluent 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.
IDENTIFIED LEAKAGE 4
1.17 IDENTIFIED LEAKAGE shall be:
l 4
i a.
Leakage. (except CONTROLLED LEAKAGE) into closed systems, such as d
pump seal or valve packing leaks that are captured, and conducted to a sump or collecting tank, or b.
Leakage into the containment atmosphere from sources that are i
both specifically located and'known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE B0UNDARY LEAKAGE, or c.
Reactor Coolant System leakage through a steam generator to the Secondary System.
4 MEMBER (S) 0F THE PUBLIC i
1.18 MEMBER (S) 0F THE PUBLIC shall include all persons who are not l
occupationally 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.
0FFSITE D0SE CALCULATION MANUAL (0DCM)
II.1 Th 0FF TE SE ALC TI UAL hal co ain he urr t j
met odol gy dp ame ers sed n ec cul tio of fsi e de es ue o ra ioa ive ase s a d li uid ff ent in e
leu tio of ase s d
1 uid eff1 ent ni rin ala
/
p s tpo ts, and nt co duc of p vir en 1 r dio gic mofit ng rog m.
$EPL))cE wirH h SE W.l Y CALVERT CLIFFS - UNIT 1 1-4 Amendment No. 186
INSERT "1.19" OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.19 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain the radioactive effluent controls, radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report, required by Specifications 6.6.2 and 6.6.3, respectively.
1 I
I 1.0 DEFINITIONS OPERABLE - OPERABILITY 1.20 A system, subsystem, train, component or device shall be OPERABLE or l
l i
have OPERABILITY when it is capable of perfoming its specified l
function (s).
Implicit in this definition shall be the assenption that all l
necessary attendant instrumentation, controls, normal and emergency l
electrical power sources, cooling or seal water, lubrication or other required auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of l
perfoming their related support function (s).
OPERATIONAL M0DE 1.21 An OPERATIONAL MODE shall correspond to any one inclusive combinatien l
of core reactivity condition, power level and average reactor coolant l
temperature specified in Table 1.1.
PHYSICS TESTS 1.22 PHYSICS TESTS shall be those tests perfomed to measure the l
fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 13.0 of the FSAR, 2) authorized l
under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.
~
~
PRESSURE B0UNDARY LEAKAGE 1.23 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator l
tube leakage) through a non-isolable fault in a Reactor Coolant System l
component body, pipe wall or vessel wall.
PS[CES[C0 R0l[ ROG b CP
.2 T
PR ESS ONT L P OG sh 1c tai the urr nt m
a, l
sa pli
,a lys, t sts, and ete ina ons ob ma to ns e at he p oce ing nd ck ing fs id r dio tiv was s sed n mo tr ed roc sin of ctu or imu' ted et lid ast w 1b ac omp sh d i suc a w y as to sur com ian wi 10 FR art 0,
OC1P t d
Fe ral and tat and oca. reg ati sg er ng e
sp 1
te r toa tive was
/
~
DELETE
~
s CALVERT CLIFFS - UNIT 1 1-5 Amendment No. 186
1.0 DEFINITIONS PURGE - PURGING f,gz/
- r.
a confinement to maintain temperature, humidity, concentration or PURGE or PURGING is the controlled process of discharging air or gas l
other operating condition, in such a manner that replacement air or gas is i
required to purify the confinement.
RATED THERMAL POWER Of.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate i
s he reactor coolant of 2700 MWt.
i REACTOR TRIP SYSTEM RESPONSE TIME f,2(,
The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from l
- wKLrn the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.
REPORTABLE EVENT
.27 A REPORTABLE EVENT shall be any of those conditions specified in l
a e ion 50.73 to 10 CFR Part 50.
SHUTDOWN MARGIN f,fg SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by l
1 ch the reactor is subcritical or would be subcritical from its present w
condition assuming all full length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully withdrawn.
SITE B0UNDARY f,f9 The SITE BOUNDARY shall be that line beyond which the land is neither l
I d, nor leased, nor otherwise controlled by the licensee.
k.IDdIchI0
.3 S
ID I TIO s 1 be he co e io o w w st i to a th l
spiip n and bu al gr nd re ir me s me DELE TE I
CALVERT CLIFFS - UNIT 1 1-6 Amendment No. 186
1.0 DEFINITIONS SOURCE CHECK I.30 A SOURCE CHECK shall be the qualitative assessment of channel l
D ponse when the channel sensor is exposed to a source of increased radioactivity.
t STAGGERED TEST BASIS l
j,3j A STAGGERED TEST BASIS shall consist of:
l l
y F
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.
THERMAL POWER I.32
.4 THERMAL POWER shall be the total reactor core heat transfer rate to l
TOTAL INTEGRATED RADIAL PEAKING FACTOR - FI l
.I.33 The TOTAL INTEGRATED RADIAL PEAKING FACTOR is the ratio of the peak if power to the average pin power in an unrodded core.
TOTAL PLANAR RADIAL PEAKING FACTOR - FT, l
l.3Y The TOTAL PLANAR RADIAL PEAKING FACTOR is the maximum ratio of the l
to average power density of the individual fuel rods in any of the U
unrodded horizontal planes.
l l
.36 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED l
l GE or CONTROLLED LEAKAGE.
CALVERT CLIFFS - UNIT 1 1-7 Amendment No. 186 l
\\
\\
I 1.0 DEFINITIONS UNRESTRICTED AREA
} %l An UNRESTRICTED AREA shall be any area at or beyond the SITE B0UNDARY l
s to which is not controlled by the licensee for purposes of l
i d
protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE B0UNDARY used for residential quarters or for industrial, connercial, institutional, and/or recreational purposes.
l VENTILATION EXHAUST TREATMENT SYSTEM 1.37
$.AVENTILATIONEXHAUSTTREATMENTSYSTEMisanys l
vl alled to reduce gaseous radioiodine or radioactive material in particulate form in effluent by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any affect on noble gas effluent.
Engineered Safety Feature (ESF) Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
VENTING f,%
VENTING is the controlled process of discharging air or gas from a l
l l
inement 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 l
l l
CALVERT CLIFFS - UNIT 1 1-8 Amendment No. 186
h 3/4.3 INSTRUMENTATION
/4.3.3
_ MONITORING INSTRUMENTATION
_ Radioactive Gaseous Effluent Monitorina Instrumenta on LIMITI CONDITION FOR OPERATION 3.3.3.9 radioactive gaseous effluent monitoring inst channels sh mentation n in Table 3.3-12 shall be OPERABLE with t r alam/ trip setpoints set o ensure that the limits of Specificati 3.11.2.1 are not exceeded. The lam / trip setpoints of these channels hall be detemined and adjusted in, cordance with the methodology and arameters in the ODCM.
[
APPLICABILITY: As own in Table 3.3-12.
ACTION:
a.
With a radioac ve gaseous efflue monitoring instrumentation channel alam/tr setpoint less onservative than required by the above Specift tion, withou delay suspend the release of radioactive gaseous ffluents onttored by the affected channel, or declare the chann inope ble, or change the setpoint so it is acceptably conserva ve.
C b.
With less than the minim number of radioactive gaseous effluent g-monitoring instrumentat' n hannels OPERABLE, take the ACTION H
shown in Table 3.3-12.
Exer best efforts to return the instruments to OPERA E statu within 30 days and, if unsuccessful, ex)la in the ne Semiannual Radioactive Effluent f
Release Report w1y the inoperabi' ty was not corrected in a timely manner.
H c.
The provision of Specifications 3.0.
and 3.0.4 are not 1
applicable.
s m
SURVEILLANCE RE REMENTS 4.3.3.9 Eac radioactive gaseous effluent monitoring instr channel sha entation be demonstrated OPERABLE by performance of the SOURCE CHE
, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST ANNEL CHEC the freq erations at ncies shown in Table 4.3-11.
N CALVERT CLIFFS - UNIT 1 3/4 3-42 Amendment No. 199 l
1 DELETE THIS PAGE I
s i
L Q*
r TABLE 3.3-12
'/
G R
i RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION l
w n
C l
MINIMUM CHANNELS x
7 INSTRUMENT OPERABLE APPLICABILITY ACTION E
Q m
i 1.
WASTE GAS HOLDUP STEM x
>g.
c l
5 a.
Noble Gas Activity nitor - Providing 1
35 d
Alarm and Automatic T ination of Release E
j b.
Effluent System Flow Rate Meas ng 1
Device 36 2.
MAIN VENT SYSTEM R
a.
Noble Gas Activity Monitor Y
1 37 0
b.
Iodine Sampler 1
38 c.
Particulate Sampler 1
'38 a
an
@w m
l l
3/4.3 INSTRUMENTATION 7
1 TABLE 3.3-12 (Continued)
TABLE NOTATION At 1 times.
i l
ACTION STATEMENTS ACTION 35 -
With the number of channels OPERABLE ss than required by
[
the M imum Channels 0PERABLE requir ent, the contents of the ta (s) may be released to the nvironment:
a.
Using he main vent monitor a backup and recording RMS reading every 15 minutes ring the release, or b.
Provided t t prior to i tiating the release, at least two indepen nt sample of the tank's contents are Z
analyzed, an t leas two technically qualified members of the Facilit Staf independently verify the release rate calculation d two qualified operators verify the discharge valve 1 eup.
i Otherwise, suspend elea of radioactive effluents via this pathway.
g ACTION 36 -
With the numbe of channels ERABLE less than required by the Minimum C annels 0PERABLE quirement, effluent releases H
via this pa way may continue p vided the flow rate is i
estimated least once per 4 hou 1
l ACTION 37 -
With th number of channels 0PERABL less than required by s
H<
the Mi mum Channels OPERABLE require nt, effluent releases via is pathway may continue provided ither (1) grab 1
es are taken and anal sam per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or (2) yzed for gross ctivity at least m
o an equivalent mo itor is provided.
ACTION 38 -
ith the number of channels OPERABLE less tha required by the Minimum Channels OPERABLE requirement, ef ent releases via the affected pathway may continue provided mples are l
continuously collected as required in Table 4.11-with auxiliary sampling equipment.
I i
CALVERT CLIFFS - UNIT 1 3/4 3-44 Amendment No. 199 l
DELETE THIS PAGE G
J F
TABLE 4.3-11
't TDI0 ACTIVE GASEGUS EFFLUENT MONITORING INSTRUMENTATION SUR r
b
- 7 ES IN h
CHANNEL WHICN CHANNEL SOURCE CHANNEL FUNCTI SURVEILLANCE k
IPSTRUMENT E
_ CHECK
_ CHECK CALIBRATION T
_ REQUIRED 5
1.
WASTE GAS HOLDUP SYSTEM E
I a.
Noble Gas Activity Monitor -
P P
R(3)
SA )
U Providing Alam and Automatic Temination of Release w
b.
Effluent System Flow Rate D *)
NA R
NA I
2, Measuring Device Y
2.
MAIN VENT SYSTEM a.
Noble Gas Activity Monitor D
M (3)
SA(2) b.
Iodine Sampler W
NA NA NA c.
Particulate Sampler W
NA NA NA kl EF w
3/4.3 INSTRUMENTATION TABLE 4.3-11 (Continued)
TABLE NOTATION At 1 times other than when the line'is valved out a locked.
(1)
The EL FUNCTIONAL TEST shall also demonstrate e automatic isolatio of this pathway and/or Control Room ala annunciation occurs i he appropriate following condition (s) exists:
,s 1.
Instrume indicates measure levels above he alam/ trip 1
setpoint.
2.
Circuit fail e.
3.
Instrument indi tes a downscale f lure.
1 (2)
The CHANNEL FUNCTIONAL EST shall a o demonstrate that Control Ro i
alann annunciation occu if any o the following conditions exists:
1.
Instrument indicates m sur levels above the alarm setpoint.
2.
Circuit failure, H"
l q
3.
Instrument indicates downs le failure.
(3)
The initial CHANNEL CAL RATION sha be erformed using one or more
[
of the reference stan rds traceable o t e National Bureau of Standards or using s ndards that have een obtained from suppliers H
that participate in asurement assuran activities with NBS.
These
- s standards shall p it calibrating the sy em within its intended l'
range of energy d measurement range.
Fo subsequent CHANNEL w.
CALIBRATION, so ces that have been related the initial H
calibration c be used.
1 (4)
The CNANNE HECK shall consist of verifying ind ation of flow A
during pe ods of release and shall be made at lea l
hours on ays on which effluent releases are made.
once per 24 m
I i
i CALVERT CLIFFS - UNIT 1 3/4 3-46 Amendment No. 199 l
~ _ _ _ _
3
.3 INSTRUMENTATION 3/4. 3
_ MONITORING INSTRUMENTATION
_ Radioactive Liould Effluent Monitoring instrumentation LIMITING C ITION FOR OPERATION l
3.3.3.10 The dioactive liquid effluent monitcring instrumen ion channels shown Table 3.3-13 shall'be OPERABLE with their a rm/ trip setpoints set to sure that the limits of Specification 3.1.1.1 are not exceeded. The ala
/ trip setpoints of these channels shall e detemined and adjusted in acco 'ance with the methodology and param ers in the 0FFSITE DOSE CALCULAT N MANUAL (0DCM).
APPLICABILITY: At all t es.
ACTIGX:
a.
With a radioactive 1 uid effluent mo toring instrumentation channel alam/ trip w;aint less con rvative than required by the above Specificana without de y suspend the release of radioactive liqu'id efflu ts mont red by the affected channel, or declare the channel in erabl, or change the setpoint so it is acceptably conservative.
w j
b.
b With less than the minimum n r of radioactive liquid effluent H
monitoringinstrumentation/1an is OPERABLE, take the ACTION shown in Table 3.3-13.
E:pert bes efforts to return the instruments to OPERABLE
- atus wit n 30 days and, if 1'
unsuccessful, explain the next Se f annual Radioactive Effluent r
Release Report why th inoperability s not corrected in a "q
timely manner.
.f c.
The provisions of pecifications 3.0.3 an 3.0.4 are not applicable.
&f SURVEILLANCE REQUI ENTS 4.3.3.10 Each r dioactive liquid effluent monitoring instrumen tion channel shall 4 demonstrated OPERABLE by perfomance of the CH SOURCE CHECK,
- HANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST o7er L CHECK, the frequen es shown in Table 4.3-12.
ions at CALYERT CLIFFS - UNIT 1 3/4 3-47 Amendment No. 199 l
i N/4.3 INSTRUMENTATION
/
TABLE 3.3-13
_RADI0 ACTIVE LIOUID EFFLUENT N0NITORING INSTRUNENTATION MININUM CHANNELS INSTRUMENT OPERABLE ACTION 1.
GROSS RADI CTIVITY MONITORS PROVIDING ALARM AND At TIC TERM: NATION OF RELEASE g
a.
Liquid Radwa.s e Effluent Line 1
28 b.
Steam Generator lowdown Effluent 1
29 Line i,
4 2.
FLOW RATE MEASUREMENT DE CES h
a.
Liquid Radwaste Effluen Line 1
30 b.
Steam Generator Blowdown E lu t 1
30
)
Line bH H
[
H L
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&1 m
4 CALVERT CLIFFS - UNIT 1 3/4 3-48 Amendment No. 199 l
4
i 1
y/4.3 INSTRUMENTATION l
TABLE 3.3-13 (Continued) l ACTION STATENENTS i
i 1
l ACTION 28 -'.
l With the number of channels OkERABLE less than r quired by d
the Minimum Channels OPERABLE requirement, eff ent releases y continue provided that prior to initiatin a release:
a.
t least two independent s lesaita lyzed in 1
- cordance with Specificat 4.11.1.
1, and 1'
b.
At ast two technically qualified embers of the Faci
'ty Staff independently vert the release rate i
calcui tions and two qualified erators verify the j
dischar valve line up.
ACTION 29 -
With the numbe of channels OPE LE less than required by 1
the Minimum Cha els 0PERABLE quirement, effluent releases via this pathway y continue
)rovided grab samples are analyzed for gross adioact ity (beta or gamma) at the lower limit of detec on d ined in Table 4.11-1:
[
a.
At-least once per I hours when the specific activity of M
the secondary cool is greater than 0.01 microcurie / gram D E IVALENT I-131.
H b.
At least once r 48 hou when the specific activity of Iw.
the secondar microcurfe/ y coolant is 1 s than or equal to 0.01 am DOSE EQUIVA NT I-131.
ACTION 30 -
With the num r of channels 0PERAB less than required by g'
the Minimum hannels 0PERABLE requir ent, effluent releases via this p thway may continue provide the flow rate is j
s estimate at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> dur g actual releases.
)
N Pump pe ormance curves may be used to e imate flow.
A m
CALVERT CLIFFS - UNIT 1 3/4 3-49 Amendment No. 199 l
DELETE THIS PAGE g
G
_ TABLE 4.3-12
'g g
.RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUNENTATION SU P
w b
o.
a ANNEL h
INSTRUMENT CHANNEL SOURCE CHANNEL FUNCTIONAL b
CHECK CHECK CALIBRA TEST 1.
GROSS RADI0 ACTIVITY ITORS PROVIDING ALARM 5
AND AUTOMATIC TERMINAT OF RELEASE 5
-4 d
a.
Liquid Radwaste Effluent o
e D
P R(r)
SA )
fl b.
Steam Generator Blowdown Efflue Line D
P f8 R)
SA(1) 2.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line DW NA R
NA h;
b.
Steam Generator Blowdown Effluent Line I
D NA R
NA i
k s
3
?
D I
y/4.3 INSTRUNENTATION
[
TABLE 4.3-11 (Continued)
TABLE NOTATION (1)
The C NEL FUNCTIONAL TEST shall also demonstrate that a omatic isolat of this pathway and/or Control Room alarm ann ciation occur if he appropriate following condition (s) exists-1.
Inst t indicates measured levels above the am/ trip setpoint.
s 2.
Circuit fat re.
L 3.
Instrument ind ates a downscale failure.
(2)
The initial CHANNEL IBRATION shall be p fomed using one or more of the reference standa ds traceable to t e National Bureau of Standards or using stand ds that have en obtained from suppliers h
that participate in measu dent assura e activities with NBS. These standards shall pemit cali ating t system within its intended y
range of energy and measurem t ran For subsequent CHANNEL CALIBRATION, sources that have ee related to the initial calibration can be used.
M I3)
CHANNEL CHECK shall consist of ying indication of flow during er g
periods of release.
CHANNEL ECK s all be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which e luent re ases are made.
H
'f
&1 O
l I
i CALYERT CLIFFS - UNIT 1 3/4 3-51 Amendment No. 199 l
=.
. =.
=.
}
3/4.11 RADI0 ACTIVE EFFLUENTS l
3
.11.1 LIOUID EFFLUENTS Concentration i
LIMITING ONDITION FOR OPERATION t
3.11.1.1 T concentration of radioactive material releas in liquid effluents to MiRESTRICTED AREAS shall be limited to the c centrations specified.in l' CFR Part 20, Appendix 8. Table II, Colu 2 for radionuclides ot er than dissolved or entrained noble ses.
APPLICABILITY:.At 11 times.
1s j
ACTION:
)
a.
With the conce ration of radioactiv material released in liquid 3
effluents to UN TRICTED AREAS exc eding the above limits, i
without delay res re the concentr tion to within the above 4
limits.
b.
Z The provisions of Spe 'ficati s 3.0.3 and 3.0.4 are not applicable.
Was ume D%
SURVEILLANCE REQUIREMENTS 1
4.11.1.1.1 Radioactive liqu wastes shall e sampled and analyzed i
+
H according to the sampling d analysis progra of Table 4.11-1.
E['
4.11.1.1.2 The results the radioactivity ana ses shall be used in accordance with the me odology and parameters in he ODCH to assure that
-u S
the concentrations at he point of release are main ined within the limits H
of Specification 3.1.1.1.
m
=
CALVERT CLIFFS - UNIT 1 3/4 11-1 Amendment No. IM
. - = _
\\3/4.11 RADI0 ACTIVE EFFLUENTS TABLE 4.11-1 i
RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT OF MINIMUM DETECTION LIQUID RELEAS SAMPLING ANALYSIS TYPE OF ACTI TY (LLD)*
TYPE REQUENCY FREQUENCY ANALYS (pCi/al)
A.
BatchWagte P
P Principa/Gama 5x10-'
Releases Eac Batch Each Batch Emitterf I-13][
1x104 Mo/9,Ce-144 2x104 P
M
[3 1x10-5 Each Batch Composite
/GrossAlpha 1x10-'
d Each Batch C
sit Sr-89,Sr-90 5x10d B.
Turbine M
M Principal Gamma 5x10-'
~
Building Emitters
- M Sump N
I-131 1x10d g-Mo-99, Ce-144 2x10" H
g
&1Q i
4 CALVERT CLIFFS - UNIT 1 3/4 11-2 Amendment No. 169
/4.11 RADI0 ACTIVE EFFLUENTS TABLE 4.11-1 (Continued)
TABLE NOTATION The LD is defined, for purposes of these specification, as the smal' st concentration of radioactive material in a sa le that will yield net count, above system background, that will se detected 1
i with 95 robability with only 5% probability of fa that a bl k observation represents a "real" signa. ely concluding j
For a parti lar measurement system, which may clude radiochemical separation:
,I,.
4 4.66s*
LLD =
EY-2 x 10' Y exp(-M Where:
i LLD is the "a priori lower lim of detection as defined above, as microcuries per uni mass o volume.
~
s, is the standard deviat of the background counting rate or w==
of the counting rate of a ank sample as appropriate, as counts pH per minute, E is the counting eff1 fency, a counts per disintegration.
'[
V is the sample siz in units of ss or volume, M
2.22 x 10' is th number of disintegr tions per minute per
- Is' microcurie, Y is the fra ional radiochemical yield, en applicable, s
i 1.s.
A is the ' dioactive decay constant for the articular radionuc de, and A
At is he e, lapsed time between sample collection or end of the samp collection period, and time of counting.
T ical values of E V Y, and At should be used in lculation.
e should be reco I
efore the fact)gnized that the LLD is defined as an a prio limit representing the capabilit ystem and not as an a posteriori (after the fact)y of a measu ment limit for a particular measurement.
CALVERT CLIFFS - UNIT 1 3/4 11-3 Amendment No. 169
4.11 RADI0 ACTIVE EFFLUENTS TABLE 4.11-1 (Continued)
TABLE NOTATION b
Pri to sampling Reactor Coolant Waste and Miscellaneou Waste for anal es, each batch shall be isolated, and then thoro ly mixed to assure representative sampling.
C The prin al gamma emitters for which the LLD spe fication applies exclusivel are the following radionuclides: Mn-
, Fe-59, Co-58, i
Co-60, Zn-6 Cs-134. Cs-137 and Ce-141.
This st does not mean that only th e nuclides are to be considered. Other gamma peaks
,,1 that are ident table, together with those of he above nuclides, shall also be a lyzed and reported in the f annual Radioactive Effluent Release port pursuant to Specif ation 6.9.1.8.
d A composite sample one in which the antity of liquid sampled is proportional to the q ntity of liquid aste discharged in which the method of sampling emp ed results a specimen that is 1
3 l
representative of the li ids relea d.
l l
MM L~
H 1
e:
I i
l CALVERT CLIFFS - UNIT 1 3/4 11-4 Amendment No. 169 l
3 3/4.11 RADI0 ACTIVE EFFLUENTS i
4.11.1 LIOUID EFFLUENTS i
i
_ Dose 1
LIMITIN ONDITION FOR OPERATION 3.11.1.2 T dose or dose commitment to a MEM8ER 0F THE P LIC from radioactive terials in liquid effluents released to UN RICTED AREAS j
shall be limit i
a.
During.
y calendar quarter to less than o equal to 3.0 mrems to j
the tota body and to less than or equal 10 mrems to any 1s organ, an
)
b.
During any ca endar year to less than r equal to 6 mrems to the total body and o less than or equa to 20 mrems to any organ.
APPLICABILITY: At all time i
4 ACTION:
a.
With the calculated dos fr the release of radioactive i
l materials in liquid eff1 s exceeding any of the above limits.
prepare and submit to th omission within 30 days, pursuant to
>-H Specification 6.9.2, a ec 1 Report that identifies the cause(s) for exceeding he 1 it(s) and defines the corrective actions that have be taken t reduce the releases and the proposed corrective etions to taken to assure that subsequent s
,1 releases will be i compliance w the above limits.
7 M
b.
The provisions Specifications 3.
3 and 3.0.4 are not applicable.
s i
1 s
i d
k-y SURVEILLANCE REQU EMENTS R
4.11.1.2 Mont y cumulative dose contributions from liqui effluents fo'r#
the current endar quarter and the current calendar year all be determined accordance with the methodology and parameters '
the ODCH at
]
least once er 60 days.
l 1,
i a
1 CALVERT CLIFFS - UNIT 1 3/4 11-5 Auendment No. 169 1
4
1
/4.11 _RADI0 ACTIVE EFFLUENTS j
3
.11.1 LIOUID EFFLUENTS i
Liouid Radwaste Treatment System LIMITING ONDITION FOR OPERATION 2
3.11.1.3 Th Liquid Radwaste Treatment System shall be us radioactive to reduce the erfals in liquid wastes p'-?sr to their dis darge when the calculated dose due to the liquid effluent to UNRESTRI JD AREAS exceeds 0.36 mrem to the otal body or 1.20 mrem to any organ a 92 day period.
APPLICABILITY: At I times.
s 1
ACTION:
a.
With radioactiv liquid waste being scharged without treatment and in excess of he above limits, epare and. submit to the Commission within 0 days pursuan to Specification 6.9.2 a h
Special Report that neludes the ollowing information:
I 1.
Explanation of why liquid adwaste was being discharged i
without treatment, ent ication of any inoperable equipment or subsyst and the reason for the inoperability, i
H"q i
2.
Action (s) taken to estor the inoperable equipment to j
i OPERABLE status, d
i
[
t 3.
Summary descri ion of action taken to prevent a
'r recurrence.
t i
- 1y b.
The provisions f Specifications 3.0.3 nd 3.0.4 are not applicable.
A SURVEILLANCE RE RENENTS 4.11.1.3 Mor ly doses du to liquid releases to UNRESTRI AREAS shall be calculat at least once per 60 days in accordance with th and parame methodology rs in the ODCM.
^
CALVERT CLIFFS - UNIT 1 3/4 11-6 Amendment No. 169
/4.11.RADI0 ACTIVE EFFLUENTS 3
.11.2 GASEOUS EFFLUENTS _
Dose Rate i
LIMITING NDITION FOR OPERATION 3.11.2.1 Th dose rate due to radioactive materials releas in gaseous effluents fr the site to areas at and beyond the SITE B JDARY (see j
Figure 5.1-1) s 11 be limited to the following:
a.
For nobl gases: Less than or equal to 500 rems /yr to the total 4
i body and ss than or equal to 3000 mrems/
to the skin, and t
1,,
b.
For iodine-1 and for all radionuclide in particulate form with half lives gre ter than 8 days:
Less an or equal to 1500 mrems/yr to any rgan.
APPLICABILITY:
At all times.
ACTION:
a.
With the dose rate (s) ex tedi the above limits, without delay a
restore the release rate ithin the above limit (s).
)y b.
The provisions of Specifi t ns 3.0.3 and 3.0.4 are not applicable.
M SURVEILLANCE REQUIREMENTS s
1 4.11.2.1.1 The dose ra due to noble gases in ga ous effluents shall be determined to be withi the above limits in accordan e with the methodology H
and parameters in th ODCM.
1 4.11.2.1.2 The do rate due to iodine-131 and all radi uclides in A
particulate form ith half lives greater than 8 days in g eous effluents shall be determ ed to be within the above limits in accor ce with the methodology an parameters in the CDCM by obtaining represen tive samples and performi analyses in accordance with the sampling and a lysis program spe fied in lable 4.11-2.
CALVERT CLIFFS - UNIT 1 3/4 11-7 Amendment No. 169
DELETE THIS PAGE g
TABLE 4.11-2 r-w h
RADI0 ACTIVE GASEQUS WASTE SAMPLING AND ANALYSIS PROGRAM a
h
-1 P
M LOWER T OF g
SAMPLING MINIMUM ANALYSIS Q
GASEOUS RELEASE TYPE FREQUENCY FREQUENCY TYPE OF ACTIVITY ANALYSIS pC1/al)
R DETE (LLD)*
~
rg *' Tank Tank Each Tank h
pal h
ama Emi ers 1x104 B.
Containment Purge P
P and Vent Each Batch
- Each Batche b
5 hal son $y a
1x104 Grab Sample C.
Main Vent M
pj Principal ma Emitters Grab Sample *
(Gaseo issionsOnly) 1x104 w
Continuous
- M
\\ H-3 /
1x10*
Continuousd Charcoal Sampl 1x10-"
Continuousd Parti te Princip Gama Emittersh (I-131,et s) 1x10-"
e S
le l
M Pfr$$
Gross Alpha 1x10-"
Continuousd e
R-Sample g
h i
tinuousd Co t
Sr-89, Sr-90 x10-"
pr ae E,
Sample z:
Continuousd Noble Gas Noble Gases Monitor Gross Beta or Gama 1x10 D.
Incin ted 011" P
P Principal Gama Emitters 8
Each Batch' Each Batcht Sx107 h
\\ 3/4.11 RADI0 ACTIVE EFFLUENTS
,/
TABLE 4.11-2 (Continued).
TABLE NOTATION i
Th LLD is defined, for purposes of these specifications, as the i
smal st concentration of radioactive material in a sam e that will yield net count, above system background, that will detected l
with 9 probability with only 5% probability of fal y concluding l
that a b nk observation represents a "real" signal For a parti lar measurement system, which may i ude radiochemical separation:
i i
LLD =
4.'66s" EV-22 x 10' Y exp (4A Where:
h LLD is the "a priort lower limi of detection as defined above, as microcuries per un mass or olume, s, is the standard devia on f the background counting rate or
[
of the counting rate of a ank sample as appropriate, as counts per minute,
~
E is the counting effi ency, counts per disintegration, V is the sample size n units of ass or volume, t
2.22 x 10' is the umb' r of disinteg tions per minute per microcurie, e
Y is the frac onal radiochemical yield, hen applicable, H
% is the r loactive decay constant for the articular
['
radionuci e, and O
At for flant effluents,isa the elapsed time bet n sample colle on or end of the sample collection perto and time of l
cou ing.
T ~ical values of E, V, Y, and At should be used in e
alculation.
I should be reco before the fact)gnized that the LLD is defined as an a orfor limit representing the capabilit system and not as an a posteriori (afte'r the fact)y of a measu ent limit for a j
particular measurement.
CALVERT CLIFFS - UNIT 1 3/4 11-9 Amendment No.'169
i 1
i N
3/4.11 RADI0 ACTIVE EFFLUENTS
/
1 TABLE 4.11-2 (Continued)
TABLE NOTATION b
principal gama emitters for which the LLD specifi tion applies usively are the following radionuclides: Kr-87
-88, Xe-133, ex j-Xe-
, Xe-135, and Xe-138 for gast.ous emissions an. Mn-54 Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134. Cs-137 Ce-141 nd Ce-144 for partic ate emissions. This list does not mean t t only these i
nuclides re to be considered. Other gama peak that are 4
identifia e, together with those of the above clides, shall also be analyze nd reported in the Semiannual Ra oactive Effluent j
Release Repo pursuant to Specification 6.9
.8.
r C
Sampling and an ysis shall also be perfo ed following shutdown, i
STARTUP, or a TH L POWER change excee ng 15 percent of RATED THERMAL P0WER with one hour unless (1 analysis shows that the DOSE EQUIVALENT I-131 con entration in the rimary coolant has not h
increased more than a " actor of 5. a (2) the noble gas activity i
j monitor shows that eff' ent activit has not increased by more than a factor of 5.
d The ratio of the samale flo shall be known for t.1e time to the sampled stream flow rate ra i
calculation made in accordan fod covered by each dose or dose rate f th Specifications 3.11.2.1, 3.11.2.2
)==4 and 3.11.2.3.
I Samples shall be changed t least.
ce per 7 days and analyses shall be completed within 48 ours after c nging, or after removal from
,. s i
,,J,,
sampler. When sample ollection time s less than seven days, the r
==4 corresponding LLDs m be increased by pro)ortional factor.
This requirement does no apply if (1) analys slows that the Dost I*
EQUIVALENT I-131 ncentration in the pri ry coolant has not increased more t n a factor of 5, and (2)
F---
shows that effl ent activity has not increas e noble gas monitor 5.
more than a factor of I
8 Waste Gas D cay Tank samples shall be collected a analyzed for oxygen on per week on the in-service tank and fo owing tank isolatio.
Waste Gas Surge Tank samples shall be co lected and analyze daily during power escalation from M0DE 6 th ugh MODE 3, and o e per week at all other times.
9 Col et sample and analyze daily for total Curie content S
cification 3.11.2.6 when the Reactor Coolant System spec r
ic tivity of Xe-133 is greater than 150 pCf/ml.
CALVERT CLIFFS UNIT 1 3/4 11-10 Amendment No. 169
13/4.11 RADI0 ACTIVE EFFLUENTS
[
TABLE 4.11-2 (Continued)
TABLE NOTATION h
In nerated oil may be discharged via points other than e main vent (e.g Auxiliary Boiler). Releases 'shall be accounted or based on pre-r ease grab sample data.
I Samples r incinerated oil. releases shall be co11 ed from and i
represent ive of filtered oil in liquid form.
i D
<da l
\\
DM i H g-Ny C
CALVERT CLIFFS - UNIT 1 3/4 11-11 Amendment No. 169
3/4.11 _RADI0 ACTIVE EFFLUENTS l
l 4.11.2
_ GASEOUS EFFLUENTS Dose - Noble Gases LIMITIN ONDITION FOR OPERATION eyond the SITE B0UNDARY (see Figure 5.1-3.11.2.2 T air dose due to noble gases released in gaseot effluents to areas at and to the followl l
a.
- During, y calendar quarter:
Less than or e al to 10 mrads for gamma ra ation and less than or equal to mrads for beta g
radiation d,
b.
During any c endar year: Less than or equal to 20 mrads for gamma radiatio and less than or equa to 40 mrads for beta radiation.
APPLICABILITY: At all times.
l ACTION:
w a.
With the calculated air-se rom radioactive noble gases in o
gaseous effluents exceedi M
submit to the Commission any of the above Ifmits, prepare and in 30. days, pursuant to Specification 6.9.2, a S eci Rep) ort that identifies the H
cause(s) for exceeding he li t(s and defines the corrective actions that have bee taken to educe the releases and the l
I.s proposed corrective ctions to b taken to assure that subsequent releases will be i compliance wit the above limits.
N b.
The provisions Specifications 3.0.
and 3.0.4 are not g
applicable.
l
&1 SURVEILLANCE REQU EMENTS 4.1.1.2.2 Mont y cumulative dose contributions for the cu ent calendar l
quarter and rrent calendar year for noble gases shall be d emined in i
accordance th the methodology and parameters in the ODCH at per 60 day.
east once t
4 1
CALVERT CLIFFS - UNIT 1 3/4 11-12 Amendment No. 169
l
/4.11 _RADI0 ACTIVE EFFLUENTS 3
.11.2
_ GASEOUS EFFLUENTS Dose - Iodfrie-131 and Radionuclides in Particulate Fo LIMITING ONDITION FOR OPERATION 3.11.2.3 Th dose to a MEMBER OF THE PUBLIC from iodine-131 nd all l
radionuclides n particulate form with half itves greater an 8 days in gaseous effluen released to areas at and beyond the SIT B0UNDARY (see Figure 5.1-1) sh 1 be limited to'the following:
a.
During an calendar quarter:
Less than or ual to 15 mrems to
['
any organ a d.
b.
During any ca ndar year:
Less than or equal to 30 mrems to any organ.
i c.
Less than 0.1% of he limits of 3.1.2.3(a) and (b) as a result of-burning contamin ed oil.
APPLICABILITY: At all times.
i w
ACTION:
g a.
With the calculated dose the release of iodine-131 and H
radionuclides in particu ate rm with half lives greater than 8 r
days, in gaseous efflu ts exc ding any of the above limits, prepare and submit to he Commis ion within 30 days, pursuant to h-'
Specification 6.9.2, a Special Re rt that identifies the cause(s) for excee ng the Ifmit a defines the corrective "q
actions that have een taken to redu the releases and the proposed correc ve actions to be tak to assure that subsequent 1,
releases will in compliance with the above limits.
b.
The'provisi s of Specifications 3.0.3 an 3.0.4 are not applicable r sh s
m 28 SURVEILLANCE QUIREMENTS 4.11.2.3 nthly cumulative' dose contributions for the current alendar quarter d the current calendar year for iodine-131 and radionuc des in particu te fonn with half lives greater.than 8 days shall be dete ined in nce with the methodology and parameters in the ODCM at least accorc 4
days.
i per ce 1
CALVERT CLIFFS - UNIT 1 3/4 11-13 Amendment No. 169 w
__ _.~. _ _ _. _ _.
i
}
3/4.11 RADI0 ACTIVE EFFLUENTS l
3
.11.2 GASEOUS EFFLUENTS
]
GASE0US RADWASTE TREATMENT SYSTEM 1
LIMITING ONDITION FOR OPERATION j
I Th GASE0US RADWASTE TREATMENT SYSTEM and the VENT 3.11.2.4 i
TREATMENT SYS shall be used to reduce radioactive materi TION EXNAUST i
waste prior to s in gaseous eir discharge when the gaseous effluent 1
{
Figure 5.1-1) exceeleases, to. areas at and beyond the SI r doses due to gaseous effluent B0UNDARY (see radiation in a 92 d s 1.20 mrad for ganna radiation and
.4 mrad for beta period. The VENTILATION EXNAUS REATMENT SYSTEM
,g shall be used to red i
their discharge when t e radioactive materials in gas us waste prior to calculated doses due to g eous effluent releases,
[%
to areas at and beyond e SITE SOUNDARY (see Fig e 5.1-1) exceeds 1.8 Nor mrem to any organ in a 92. ay period.
APPLICABILITY: At all times j
_ ACTION:
! Z a.
With gaseous waste bein disc i
w excess of the above limit ged without treatment and in within 30 days, pursuant t epare and submit to the Commission j
g that includes the followi pecification 6.9.2, a Special Report formation:
k 1.
Explanation of why seous
'dwaste was being discharged j'
without treatment identific ion of any inoperable
{ g equipment or sub stems, and t reason for the inoperability, 2.
Action (s) ta n to restore the ino rable equipment to "1
OPERABLE s tus, and
[
3.
Summary escription of action (s) taken o prevent a
-s recurr ce.
..L g
b.
The prov sions of Specifications 3.0.3 and 3.0.
applic le.
are not SURVEIL E REQUIREMENTS 4.11.2 Monthly doses due to gaseous rele~ases shall be calculated a least nce per 60 days in accordance with the methodology and paramete the CM.
in CALVERT CLIFFS - UNIT 1 3/4 11-14 Amendment No. 169
3/4.11 _RADI0 ACTIVE EFFLU5NTS
' 3/4/. f].1 MFM
_ GASEOUS EFFLUENTS L
Explosive Gas Mixture (Hydrogen rich systems not desi withstand a hydrogen explosion)gned to LIMITING CONDITION FOR OPERATION l
lgf],j, f"'W@ The concentration of oxygen in the Waste Gas Holdup System shall 1mited to less than or equal to 4% by volume.
ba APPLICABILITY: At all times.
I ACTION:
With the concentration of oxygen in a waste gas decay tank a.
greater than 4% by volume immediately suspend all additions of waste gases to that tank and reduce the concentration of oxygen to less than or equal to 4% by volume without delay.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS f 1.
5 Tec cen ti so ox en t
Wa eG H duysy al e
term ed be it '
t ab e mi by e
mp1 g yro I
d rib in abl 4.1 2.
I
)
<l EPLACE WIT'll $NSERY " Y. )). }. $ "
l l
CALVERT CLIFFS - UNIT 1 3/4 11-15 Amendment No. 169
i l
i INSERT "4.11.1.1" 4.11.1.1 The concentration of oxygen in the Waste Gas Holdup System shall be determined to be within the above limit by collecting and analy r.ing a sample from the Waste Gas Decay Tank once per week on the in-service tank and following tank isolation. Waste Gas Surge Tank samples shall be collected and analyzed daily during power escalation from MODE 6 through MODE 3, and once per week at all other times.
4 I
i l
l i
3/4.11 RADIOACTIVE EFFLUENTS 3/4.11 GASE0US EFFLUENTS Gas Storace Tanks l
l LIMITING CONDITION FOR OPERATION l
4 p-3.11h. The quantity of radioactivity contained in each gas storage tank i
4 shall be limited to less than or equal to 58,500 curies noble gases (considered as Xe-133).
APPLICABILITY: At all times.
ACTION:
With the quantity of radioactive material in any gas storage tank a.
l exceeding the above limit, immediately suspend all additions of l
radioactive material to that tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
l l
SURVEILLANCE REQUIREMENTS
- 1. 2 -
4.1M The quantity of radioactive material contained in the in-service i
gas storage tank shall be determined to be within the above limit at least l
once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the Reactor Coolant System specific activity of Xe-133 is greater than 150 pCi/ml.
l l
CALVERT CLIFFS - UNIT 1 3/4 11-16 Amendinent No.169
l
/4.11 RADI0 ACTIVE EFFLUEN'TS 3
.11.3
_ SOLID RADIOACTIVE WASTE
' LIMIT CONDITION FOR OPERATION l
3.11.3 T solid radwaste program shall be used in accordan with a
. PROCESS C0 OL PROGRAM to process wet radi'oactive wastes t and burial g und requirements.
meet shipping APPLICABILITY:
t all times.
ACTION:
1 a.
With the visions of the PROCESS CONTR PROGRAM not satisfied, suspend s i nts of defectively proce ed or defectively packaged so i radioactive wastes f the site.
b.
The provision of pecifications 3.
and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS.
=
D 4.11.3 The PROCESS CONTROL PROG sh 1 be used to verify the H
SOLIDIFICATION of at leas' t one r resent ".ive test specimen from at least every tenth batch of each type f wet rad: active waste (e.g., filter g
sludges, spent resins, evapor or bottoms, ric acid solutions, and sodium l
sulfate solutions).
1 H
3 I
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1 CALVERT CLIFFS - UNIT.1 3/4 11-17 i
Amendment No. 169
4.11 j @ I0 ACTIVE EFFLUENTS 3/ 11.'4 TOTAL D0'SE LIMITI CONDITION FOR OPERATION 3.11.4 Th annual (calendar year) dose or dose commitment to ny MEM8ER OF THE PUBLIC e to releases of radioactivity and to radiation rom uranium fuel cycle so ces shall be limited to less than or equal 25 mrems to the total body r any organ, except the thyroid, which sh I be limited to less than or eq 1 to 75 mrems.
APPLICABILITY: At 11 times.
ACTION:
a.
With the calcu ted doses from the rel ase of radioactive materials in 11 id or gaseous efflu ts exceeding twice the limits of Specifi tion 3.11.1.2.a.
.11.1.2.b, 3.11.2.2.a.
h 3.11.2.2.b, 3.11.2.1.a. or 3.11.2..b. calculations shall be made including direct rat tion cont'r utions from the reactor units and outside storage t ks to d mine whether the above Ifmits of Specification 3.11.
have en exceeded.
If such is the case, prepare and submit to th C ission within 30 days, pursuant to Specification 6.9.2, a Sp al Report that defines the corrective action to be taken to red subsequent releases to prevent M
recurrence of exceeding e
ove limits and includes the H
schedule for achieving onfo ice with the above limits.
This Special Report, as de ned in l' CFR 20.405c, shall include an Is analysis that estima s the radi ion exposure (dose) to a MEMBER OF THE PUBLIC from ranium fuel cy ' e sources, including all effluent pathways nd direct radiat' n, for the calendar year that includes t release (s) covered this report.
It shall 1
1 also describe ' vels of radiation and ncentrations of radioactive m ;erial involved, and the c se of the exposure levels or c centrations.
If the estimat dose (s) exceeds the M
above limi
, and if the release condition esulting in violation
[
of 40 CFR art 190 has not already been corr ted, the Special Report all include a request for a variance n accordance with O
the pr isions of 40 CFR Part 190. Submittal o the report i.s consi red a timely request, and a variance is g nted until staf action on the request is complete.
b.
T provisions of Specifications 3.0.3 and 3.0.4 are ot pplicable.
l I
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CALVERT CLIFFS - UNIT 1 3/4 11-18 Amendment No. 169 l
L
s 4
4.11.RADI0 ACTIVE EFFLUENTS SUR ILLANCE REQUIREMENTS i
4.11.4.
Cumulative dose contributions from liquid and gaseous e uents shall be etermined in accordance with Specifications 4.11.1.2
.11.2.2 and 4.11.
3, and.in accordance with the methodology and param ers in the j
1 ODCM.
4.11.4.2 Cum ative dose contributions from direct radiat n from the i
reactor units a outside storage tanks shall be detemin in accordance i
with the methodo gy and parameters in the ODCM. This r uirement is j
applicable only u, er conditions set forth in Specific fon 3.11.4.a.
b i
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i s
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8 CALVERT CLIFFS - UNIT 1 3/4 11-19 Amendment No. 169
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3
.12.1 MONITORING PROGRAM
]
LIMIT G CONDITION FOR OPERATION 3.12.1 radiological environmental monitoring program sh I be conducted specified in Table 3.12-1.
APPLICABILI At all times.
ACTION:
I s
a.
With the diological environmental mont ring program not being 1
conducted specified in Table 3.12-1, repare and submit to the Commission, n the Annual Radiological nyironmental Operating Report requir by Specification 6.9.
7, a description of the for preventing a ecurrence.
reasons for no conducting the prog as required and the plans l
j b.
With the level of toactivity s the result of plant effluents in an environmental le at specified location exceeding the reporting levels of T le 3.
-2, prepare and submit to the Connission within 30 da a
pursuant to S er receiving the sample analysis,
=
the cause(s) pecificatio
.9.2, a Sp(ecial Report that identifies for exceedt he limit s) and defines the HH corrective actions to b ta n q
that the potential ann 1 dos,to reduce radioactive effluents so to a MEMBER OF THE PUBLIC is less than the calend year li ts of Specifications 3.11.1.2, 3.11.2.2, and 3.11.
3.
,s1 in Table 3.12-2 ar detected in tWhen mo e than one of the ra submitted if:
sample this report shall be
-H conc tration(1) conce ration (2)
+..i>1.0 rep ting level (1) reportin, level (2)
N When radi uclides other than those in Tab 3.12-2 are detected 1
and are e result of plant effluents.
d if the potential annual dose,this port shall be m
submit to a BER OF THE PUBLIC is eq 1 to or greater than the calendar year 1 its of Spec ications 3.11.1.2, 3.11.2.2 and 3.11.2.3.
his report is required if the measured level of radioactivit no was not the ult.of plant effluents; however, in such an even r
the ndition shall be reported and described in the Annu 1 Radiological Environmental Operating Report.
9
[
The methodology and parameters used to estimate the potential annual dose to a MEMBER 0F THE PUBLIC shall be indicated in this report.
CALVERT CLIFFS - UNIT 1
~
3/4 12-1 Amendment No. 169
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING L
.ITING CONDITION FOR OPERATION (Continued)
With fresh leafy vegetable samples unavailable from on of the sample locations required by. Table 3.12-1, ide r more locations f or obtaining replacement samples and add ify adiological environmental monitoring program withi em to the 30 days.
e saccific locations from which samples were un atlable may th ae deleted from the monitoring program.
Pu uant to Spe fication 6.9.1.7, ioentify the cause of t unavailability
. of s les and identify the new location (s) f obtaining the replac nt samples in the next Annual Radio Operatin Report.
gical Environmental
[
d.
The provis s of Specifications 3.0.3 s 3.0.4 are not applicable.
4 SURVEILLANCE REQUIREMENTS y
4.12.1 The radiological enviro tal nitoring samples shall be collected pursuant to Table 3.12-1 table and figure (s) in the ODCM, an the specific locations given in the r
requirements of Table 3.12-1 and th hall be analyzed pursuant to the M
Table 4.12-1.-
tection capabilities required by 1
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CALVERT CLIFFS - UNIT 1 3/4 12-2 Arnendment No.169
DELETE THIS P GE jE d
TABLE 3.12-1
'}
l RADIOLOGICAL CNVIRONMENTAL MONITORING PROGRAM P
.M EXPOSURE PATHWAY NUMBER 0F REPRESENTATIVE SAMPLING AND TYPE EQUENCY g
3 AND/OR SAMPLE AMPLES AND SAMPLE LOCATIONS
- COLLECTION FREQUENCY 0
LYSIS E
[
1.
DIRECT RADIATIONb 23 k ne monitoring stations At least Quarterly G
dose at least
~
z
.(DR1-DRe.
either with two or M
more dosime s or with one arterly.
9 instrument for easuring and recording dose ra continuously, h
placed as follows:
g o5 an inner ring of stat s,
t' one in'each meteoralogic i
sector in the general area the SITE BOUNDARY (DRI-DR9);
Ma an outer ring of station Q
i one in each meteorolo al g
sector in the 6-to -km E
range from the s e (DR10-DR18);
1 the rem ng stations g
(DR19
- 3) to be placed in a
sp al interest areas such h
population centers, nearby g
residences, schools, and in
~1 area to serve as a control p.
station.
l E
e
DELETE THIS PAGE TABLE 3.12-1 (Continued)
. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM N
P4 EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE REQUENCY E
Q AND/0R SAMPLE SAMPLES AND SAMPLE LOCATIONS
- Col.LECTION FREQUENCY 0
LYSIS S
~
2.
AIRBORNE
=
U Radiciodine and Samples m S locations Continuous sampler
_Radioiodine Canister
[
9 Particulates (Al-AS):
~
operation with sam I-131 analysis weekly.
g collection weki, or 3 samples (A
) from more frequent if Particulate Sampler:
E close to the 3 required b ust Gross beta E
BOUNDARY locations, loading R
different sectors of radioactivity analysis followin highest calculated change;*g filter Gama isotopic M
annual average ground-i level D/Q.
analysis' of composite l
(bylocation)
I sample (A4) fr he quarterly.
p o
vicinity of a unity having the est a
calculate annual averag round-level D/Q Rg sample (AS) from a g-control location, as for g
example 15-30 km distant-and in the least g
prevalent wind direction.
E e
, s
DELETE THIS PAGE h
TABLE 3.12-1 (Continued)
RADIOLOGICAL ENVIRONNENTAL MONITORING PROGRAM P
E M
EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND ENCY G
AND/OR SAMPLE PLES AND SAMPLE LOCATIONS
- COLLECTION FREQUENCY OF LYSIS g
~
[
3.
WATERBORNE E
2 9
Z a.
Surface 1 sample a intake area (Wal) Composite samp'le over ma isotopic analysisd
~
1 sample at charge area 1-month period monthly. Composite for (Wa2) tritium analysis g
quarterly.
o E
b.
Sediment from I sample from downstream ea Semiannual 1 Gama isotopic analysisd shoreline with existing or potential semiannually.
R' recreational value (Wb1).
5
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=
4 "2
E o
a an
=
i DELETE THIS PAGE TABLE 3.12-1 (Continued) k
'y i
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM E
P4 EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND ENCY l
G AND/0R SAMPLE SAMPLES AND SAMPLE LOCATIONS
- COLLECTION FREQUENCY OF SIS S
I
=
4.
INGESTION R
cz
~
9 a.
Fish and 3 samples f commercially Sample in season, or isgtopic Invertebrates and/or recr ionally semiannually if they analysis on edible g
important spec (2 fish are not seasonal, portions.
i species and 1 iny ebrate g
species) in vicinity plant o
discharge area (Ial-Ia3 l
3 samples of same species in g
~
t' M
areas not influciiced by plant discharge (Ia4-Ic6).
l ei y
b.
Food Products Samples of 3 different ki Monthly ng growing Gama isotopic and o
d of broad leaf vegetati grown ' season.
I-131 analysis.
near the site bound at 2 m
different locatio of highest predicted annu average groundlevel Q (Ibl-Ib6).
Ng 1 sam) of each of the Monthly during growing Gamma otopic and d
a-sim ar broad leaf vegetation season.
I-131 an sis.
A wn 15-30 km distant in the east prevalent wind direction g:
(Ib7-Ib9).
I
=
=
/4.12 RADIOLOGICAL ENVIR0NNENTAL h0NITORING d
TABLE 3.12-1 (Continued) l TABLE NOTATION l
The ode in parenthesis, e.g., DR1, A1, defines generic ample locat ns in this specification that can be used to id tify the 1
specif locations in the map (s) and table in the 0D Specific paramete of distance and direction sector from th< central point between t two containment buildings and additto description where pert ent, is provided for each sample loc fon in Table 3.12-1 and in a table and figure (s) in t ODCM. Refer to 1s NUREG-0133 " eparation of Radiological Effl at Technical Specifications r Nuclear Power Plants, Oct er 1978", and to i
Radiological Ass sment Branch Technical Po tion, Revision 1 November 1979.
De f ations are permitted f om the required sampling schedule if specime are unobtainable di to circumstances such as hazardous conditions, seasonal unavaila lity, and malfunction of automatic sampling equ ent. If spe mens are unobtainable due to h
sampling equipment malf etion, effo shall be 'made to complete j
corrective action prior t the end f the next sampling period. All j
deviations from the sampli sche le shall be documented in the Annual Radiological Environn. ta Operating Report pursuant to i
Specification 6.9.1.7.
It is cognized that, at times, it may not be possible or practicable to ntinue to obtain samples of the media l
MH of choice at the most desire lo tion or time.
In these instances i
4 suitable alternative media nd lo tions may be chosen for the particular pathway in que ion and propriate substitutions made within 30 days in the ra ological e
,,1 Pursuant to Specificati n 6.9.1.7, ideironmental monitoring program.
ify the cause of the unavailability of sam es for that path y and identify the new H
location (s for obt ing samples in the ext Annual Radiological Environmen)tal Op)er 1*
ing Report and also in 'ude in the report a revised figure (s nd table for the ODCM rei ecting the new w
location (s).
i 1
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i CALVERT CLIFFS - UNIT 1 3/4 12-7 Amendment No. 169
i
)
\\3/4.12 RADIOLOGICAL ENVIR0lOIENTAL MONITORING 3
2 TABLE 3.12-1 (Continued)
)
TABLE NOTATION b
One r more ihstruments, such as a pressurized ion ch er, for meas ing and recording dose rate continuously may be sed in place i
of, o in addition to, integrating dosimeters. For e purposes of t
1 this ta e, a thermoluminescent dosimeter (TLD) is onsidered to be one phos or; two or more phosphors in a packet a considered as two 1
i or more do ' meters. Film badges shall not be us as dosimeters for i
measuring di ect radiation. The frequency of alysis or readout for t
TLD Systems 1 depend upon the characterist s of the specific
,s1 system used an should be selected to obtain ptimum dose infomation with minimal fa ig. Due to the geographi limitations, 9 sectors j
are monitored arol d the Calvert Cliffs N 1 ear Power Plant.
1 I*
C
)
Airborne particulate ample filters sh be analyzed for gross beta radioactivity 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after pling to allow for radon and 1
i thoron daughter decay, f gross bet activity in air particulate samples is greater than n times e yearly mean of control samples, ganna isotopic analysis sh 1 be rformed on the individual samples.
d Ganma isotopic analysis means of gamma-emitting radionuclid e identification and quantification, i
=
i Hy effluents fr.om the facility.
that may be attributable to the A composite sample is one n which e quantity (aliquot) of liquid j
sampled is proportional o the quant y of flowing liquid and in 1
l which the method of s ling employed esults in a specimen that is j
representative of the iquid flow.
In is program, composite sample j
==H aliquots shall be co ected at time inte als that are very short i
- 1 (e.g., hourly rel ive to the compositing eriod (e.g., monthly) in order to assu)re o s
(
aining a representative ple.
b
}
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CALVERT CLIFFS - UNIT 1 3/4 12-8 Amendment No. 169
DELETE THIS PAGE g
TABLE 3.12-2 r-h REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLE h
a N
REPORTING LEVELS ca.
E nn s
WATER B0RNE PARTICULATE FISH & INVERTEBRATES MILK PRODUCTS E
i r-g ANALYSIS (pC1/1)
ES (pC1/m')
(pC1/kg, wet)
(pC1/1)*
(pC1/kg, wet) y U
H-3 20,000' k
Mn-54 1,000 30,000 g
Fe-59 400 o
10,000 l
Co-58 1,000 30,000 Co-60 300 00 l
~6 Zn-65 300 20,000 ng Zr-Nb-95 400 E
I-131 2
0.9 3
100 Cs-134 30 E
1,000 60 1,000 g
Cs-137 50 20 2,000 70 2,000
&g Ba-La-140 200 300 g#
For drinking er samples.
This is a 40 CFR Part 141 value.
If no drinking water pathway e ts, a value of 30 0 pCi/1 may be used.
E
=
DELETE THIS PAGE g
TABLE 4.12-1 r-g DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS..b g
a p
LOWER LIMIT OF DETECTION (LLD)*
h E
E
.E WATER AIRB0 PARTICULATE FISH & INVERTEBRATES MILK F000 PR0 S
SEDIMENT E
ANALYSIS (pC1/1)
OR GAS (pci/af)
(pC1/kg, wet)
-(pC1/1)
(pC1/, wet)
(pC1/kg. dry) 9
[
Gross Beta 4
0.01 H-3 2,000' g
Mn-54 15 y
130 g
- Fe-59 30 0
r-q Co-58,60 15 130 I
E5 Zn-65 30 g
-4 0
Zr-Nb-95 15 m:
d I-131 I
0.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 6
150 18 80 180 k
Ba-La-140 15 15
[#
If no drinki ater pathway exists, a value of 3000 pC1/1 may be used.
5
4 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING TABLE 4.12-1 (Continued)
TABLE NOTATION Th list does not mean that only these nuclides are t be con dered. Other' peaks that are identifiable, toget r with those of th above nuclides, shall also be analyzed and r orted in the Annual adiological Environmental Operating Report ursuant to Specifi tion 6.9.1.7.
b Requir-d d ection capabilities for thennolumi scent dosimeters used for enviro tal measurements shall be in ac ordance with the
[
recontendatio of Regulatory Guide 4.13.
c The LLD is defin, for purposes of these pecifications, as the smallest concentra ion of radioactive m erf al in a sample that will yield a net count, ove system backgr nd, that will be detected with 95% probability 4
that a blank observati ith only 5% pro ability of falsely concluding represents "real" signal.
For a particular measur t syst
, which'may include. radiochemical separation:
4.66 M
E V
2.22 -
e
(-Mt)
H Where:
LLD is the "A pri 1" lower limit f detection as defined above, y
as picocuries p unit mass or volu
[
s is the sta ard deviation of the ba ground counting rate or o'f the coun ng rate of a blank sample appropriate, as counts s
g per minute 1
E is th counting efficiency, as counts per isintegration, V is e sample size in units of mass or volume 2.
is the number of disintegrations per minute p r picocurie, is the fractional radiochemical yield, when applica le, A. is the radioactive decay constant for the particular radionuclide, and CALVERT CLIFFS
. UNIT 1 3/4 12-11 Amendment No. 169
3/4.12 RADIOLOGICAL ENVIRONNENTAL HONITORING TABLE 4.12-1 (Continued)
TABLE NOTATION
'At for environmental samples is the elapsed time 11ection, or end of the sample collection peri tween sample nting.
, and time of c
Typi 1 values of E', V, Y and At should be u tion.
d in the calcu It should be s
ecognized that the LLD is defir d as an a oriori 1
(before the fa
) limit representing the ca bilit system and not an a posteriori (after t e fact)y of a measurement limit for a particular measur nent.
Analyses shall perfomed in such a manner that the stated LL will be achieved u er routine conditions.
Occasionally backgro d. fluctuations, avoidable small sample sizes, the presence of inter ring nuclides or other uncontrollable h
circumstances may rende these LLDs nachievable.
In such cases, the contributing factors sha be ide ified and described in the Annual Radiological Environmenta' Opera ng Report pursuant to Specification 6.9.1.7.
d LLD for drinking water samp1 If no drinking water pathway exists, the LLD of gamma isotopic a ly s may be used.
~C
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4 CALVERT CLIFFS - UNIT 1 3/4 12-12 Amendment No. 169
1 l
4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/
2.2 LAND USE CENSUS LIMITI 4
-CONDITION FOR OPERATION l
3.12.2 A nd use census shall be conducted and shall identif within a distance of km (5 miles) the location in 'each of the 9 met rological sectory of th nearest milk animal, the nearest residence a the nearest i
garden of gre er than 50 m' (500 ft ) producing broad le vegetation.
(For elevated re ases as defined in Regulatory Guide 1.
- 1. Revision 1, July 1977, the la use census shall also identify with a distance of i
5 km (3 miles) the ocations in each of the 9 meteorol gical sectors of all
{
1 milk animals and all ardens of greater than S0 m* pr ducing broad leaf vegetation).
APPLICABILITY: At all t es.
]'
ACTION:
h a.
With a land use cens identifyi a location (s) that yields a i
calculated dose or do comitm. t greater than the values currently being calcula ed in ecification 4.11.2.3, identify the new location (s) in t n t Annual Radiological Environmental i
j y
Operating Report, pursuan Specification 6.9.1.7.
M b.
With a land use ce'nsus i nt ing-a location (s) that yields a H
calculated dose or dose omit nt (via the same exposure 1
pathway) 20 ercent gr ater tha at a location from which samples Ts are current 1 being tained in a cordance with Specification s
3.12.1, add the new ocation(s) to he radiological environmental monitoring progra within 30 days.
hesamplinglocation(s),
excluding the co rol station locatio having the lowest 1- '
calculated dos or dose comitment(s),
ia the same exposure pathway, may deleted from this monito ing program after October 31 o the year in which this land se census was H
conducted. Pursuant to Specification 6.9.
7, identify the new
["
location (
in the next Annual Radiological vironmental O
Operati Report and also include in the repo a revised figure and table for the ODCM reflecting the ew location (s).
m i
c.
The rovisions of Specifications 3.0.3 and 3.0.4 a e not ap icable.
i 1
Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two i
different direction sectors with the highest predicted D/Qs in lie of the garden census.
Specifications for broad leaf vegetation sampling in Table 3.12-1.4b shall be followed, including analysis of control samples.
i CALVERT CLIFFS - UNIT 1 3/4 12-13 Amendment No. 169
4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING SU EILLANCE REQUIREMENTS l
4.12.
The land census shall be conducted during the growing seas n at least o e per 12 months using that infomation that will provid the best results, uch as by a door-to-door survey, aerial survey, or by onsulting 1
local agri 1ture authorities. The results of the land use c sus shall be included in he Annual Radiological Environmental Operating port pursuant to Specificat on 6.9.1.7.
C<
m Cn
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y.
H 1
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.w l
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CALVERT CLIFFS - UNIT 1 3/4 12-14 Amendment No. 169
i 4
4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/
2.3 INTERLABORATORY COMPARISON PROGRAM LIMITI CONDITION FOR OPERATION i
l i
3.12.3 An yses shall be performed on all radioactive materia, supplied as part of Interlaboratory Comparison Program that has be approved by the Comissio that correspond to samples required by Tabl 3.12-1.
APPLICABILITY:
t all times.
ACTION:
i a.
With analys not being perfonned as requ ed above, report the i
corrective ac tons taken to prevent a r rrence to the Commission in e Annual Radiological vironmental Operating Report pursuant o Specification 6.9.
7.
l b.
The provisions of ecifications 3
.3 and 3.0.4 are not j
h applicable.
"5
$URVEILLANCE REQUIREMENTS bH H
4.12.3 The Interlaboratory Comp ison P gram shall be described in the 0DCM. A sumary of the results btained a part of the above required 1
Interlaboratory Comparison Pro am shall be neluded in the Annual i
Radiological Environmental 0 rating Report p rsuant to "q
Specification 6.9.1.7.
R CALVERT CLIFFS - UNIT 1 3/4 12-15 Amendment No. 169
. ~ _ _ -
3/4.11 RADI0 ACTIVE EFFLUENTS i
BASES Nirameters for calculating the doses due to the actual release rates of the f
i s%ect materials are consistent with the methodology provided in.
Regt tory Guide 1.109, " Calculation of Annual Doses to Man from Routi l
Relea of Reactor Effluents for the Purpose of Evaluating Complian with 10 CFR t 50, Appendix I," Revision 1, October'1977. Regulatory i
Guide 1.1
" Methods for Estimating Atmospheric Transport and D ersion of Gaseous uents in Routine Releases from Light-Water-Cool Reactors,"'
Revision 1. J 1977, and NUREG-0133, " Preparation of Radio ical Effluent Techni Specifications for Nuclear Power Plants".
These equations also p de for detenntning the actual doses sed upon the 3
i "T' historical annual a age atmospheric conditions. Th elease rate andamm specifications for to e-131 and, radionuclides in ticulate fonn with r
hsif lives greater than days are' dependent upon le existing radionuclide i H pathways to man, in the a s at and beyond the TE B0UNDARY. The p)athways that were examinedthe developmen of these calculations were:
i "T 1 individual inhalation of a orne radio ides, 2) deposition of i
sedum radionuclides onto green leafy y etatio ith subsequent consumption by i
4 man, 3) deposition onto grassy are e milk animals and meat producing w
lg animals graze with consumption of th 11k and meat by man, and
- 4) deposition on the ground with s se ent exposure of man.
7 3
i 3/4.11.2.4 GASE0US RADWASTE T ATMENT SYS The requirement that the ropriate portions these systems be used, when specified, provide reasonable assurance th the releases of i-=====
radioactive materials n gaseous effluents 'will be pt "as low as is j
reasonably achievab This specifica n implements the requirements of 10 CFR
.36a, j
10 CFR Part.
, Appendix A. General Design Criterion 60 an he design 1
objectives tven in 10 CFR Part 50, Appendix I, Section II.D.
The j
specifie imits governing the use of appropriate portions of t systems cified as a suitable fraction of the dose design objectiv set were fort in 10 CFR Part 50, Appendix I, Sections II.B and II.C for gas us ey uents.
The dose limits apply to the combined effluent of the pla Ee.g.. two units).
1.1 3M. fi.hi GAssous EFFLUEN w
3/4.11. % Explosive Gas Mixture v
g This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the Waste Gas Holdup System l
is maintained below the flammability limit of oxygen. Maintaining the concentration of oxygen below its flaninability limit provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of 10 CFR Part 50, Appendix A, General Design Criterion 60.
3 l
Ch:r.ged by T C ictter dated L a 20.1;;;
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CALVERT CLIFFS - UNIT 1 B 3/4 11-4
3/4.11 RADI0 ACTIVE EFFLUENTS ^
BASES 12 e
3/4.11.1%@( Gas Storace Tanks The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification to a quantity that is less than the yg quantity that provides assurance that in the event of an uncontrolled g
release of the tank's contents, the resulting total body exposure to a g
MEMBER OF THE PUBLIC at the nearest SITE B0UNDARY will not exceed 3
10 CFR Part 100 limits.
Restricting the quantity of radioactivity contained in each gas storage g
tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE B0UNDARY will not exceed accident guidelines.
4.11.3 SOLID RADI0 ACTIVE WASTE This acification implements the requirements of 10 CFR 50.36a and 10 CFR>
t 50, Appendix A, General design Criterion 60. The pro ss parameters e included in the PROCESS CONTROL PROGRAM.
3/4.11.4 TOTAL SE "r'
This specification is rovided to meet the dose li ations of 40 CFR m Lam Part 190 that have been
- corporated into 10 CF art 20 by 46 FR 18525.
.f The specification requires e preparation a submittal of a Special jH Report whenever the calculat doses from ant generated radioactive L
effluents. and direct radiation eed mrems to the total body or any 1
r' i[&==
organ, except the thyroid, which s be limited to less than or equal to 75 mrems. The Special Report wi d
ribe a course of action that should i
w result in the limitation of t annual e to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 mits.
For th urpo'ses of the Special Report, i"
it may be assumed that dose comitment t he MEMBER OF THE PUBLIC from other uranium fuel c e sources is negligible.
1g If the dose to y MEMBER OF.THE PUBLIC is estimated exceed the requirement 40 CFR Part 190, the Special Report wit request for a
==
variance rovided the release conditions resulting in vio tion of 40 CF art 190 have not already been corrected), in accorda with the pro sions of 40 CFR Part 190.11 and 10 CFR Part 20.405c, is co dered to a timely request and fulfills the requirements of 40 CFR Part :
~
i s
i CAf. VERT CLIFFS - UNIT 1 B 3/4 11-5 Amendment No. 169 4
l
l 3/4.11 RADI0 ACTIVE EFFLUENTS
~
h.Es
./
unti NRC staff action is completed.
The variance only relates to the limits f 40 CFR Part 190, and does not apply in any way to the other requir nts for dose limitation of 10 CFR Part 20, as addressed in l
Specifica ions 3.11.1.1 and 3.11.2.1.
An individual is not consider d a l
MEMBER 0F IE PUBLIC during any period in which he/she is engaged carrying ou'. any operation that is part of the nuclear fuel cycle I
t 1
C
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mm
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+
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k CALVERT CLIFFS - UNIT 1 B 3/4 11-6 Amendment No. 169 i
3/4.12. liADIOLOGICAL ENVIRONMENTAL" MONITORING
~
i kS
/
3/4.
.1 MONITORING PROGRAM The rad logical environmental monitoring program required by this specifica ton provides representative measurements of radiation and f
radicactiv materials in those exposure pathways and for those -
radionuclid that lead to the highest potential radiation exposu es to MEMBERS OF PUBLIC resulting from the plant operation. This onitoring program impi ts 10 CFR Part 50, Appendix I Section IV.B.2 d thereby supplements the adiological effluent monitoring program by v rifying that the measurable co entrations of radioactive materials and vels.of radiation are not gher than expected on the basis of the ffluent measurements and the deling of the environmental expos e pathways.
Guidance for this mon oring progfam is provided by the adiological y,
Assessment Branch Tech cal Position on Environmental nitoring.
Program changes may be initiated ased on operational experi ce.
The required detection capa 111 ties for environmen 1 sample analyses are tabulated in terms of the lo r limits of detecti n (LLDs).
The LLDs required by Table 4.12-1 are c nsidered optimum or routine environmental measurements in industrial labo tories.
It s uld be recognized that the
)
LLD is defined as an a orfori (b ore the fa limit representing the capability of a measurement system nd not an a posteriori (after the i
fact) limit for a particular measur ent.
W Detailed discussion of the LLD and oth
-p HASL Procedures Manual, HASL-300 (revi detection limits can~ be found in annually), Currie, L. A., " Limits i
for Qualitative Detection and Quanti tiv Detennination - Application to r%
Radiochemistry," Anal. Chem. 40, 5 -93 (1 8), and Hartwell, J.K.,
" Detection Limits for Radioanalyt al Count Techniques," Atlantic g
Richff=1d Hanford Company Report RH-SA-215 ( ne1975).
3/4.12.2 LAND USE CENSUS
[
This specification is prov ed to ensure that chan s in the use of areas at and beyond the SITE B DARY are identified and t t modifications to y
the radiological enviro ental monitoring program are ade if required by 15 the results of this c sus. The best information from he door-to-door survey, from aerial rvey or from consulting with local gricultural authorities shall b used. This census satisfies the req rements of 10 CFR Part 50,'Appe ix I,Section IV.B.3.
Restricting the nsus to gardens i
of greater than m provides assurance that significant ex 2
via leafy vege les will be identified and monitored since a sure-pathways this size is " e minimum required to produce the quantity (26 arden of
/ year) of leafy veget les assumed in Regulatory Guide 1.109 for consumpti by a child.
To etennine this minimum garden size, the CALVERT CLIFFS - UNIT 1 B 3/4 12-1 Amendment No. 169 i
l l
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING
~
%ES i
foll ing assumptions were made: 1) 20% of the garden was used for broad af vegetation (i.e., similar to lettuce and cabbage), and 2)growi vegetat n yield of 2 kg/m'.
a 3/4.12.3 TERLABORATORY COMPARISON PROGRAM The requireme for participation in an approved Interlaboratory omparison Program is pro ded to ensure that independent checks on the pr 1sion and accuracy of the asurements of radioactive material in enviro ental sample matrices a perfomed as part of the quality assuran program for environmental mont ring in order to demonstrate that the r ults are valid for the purposes of CFR Part 50, Appendix I,Section IV
.2.
!C Nm a
"9 M
E-re ensmann W
e e.
h
- CALVERT CLIFFS - UNIT 1 B 3/4 12-2 Amendment No. 169 l
i
. -. ~ - - - -. - _. - - - - - -
l 1
3/4.3 INSTRUMENTATION BASES l
j In the event more than four sensors in a Reactor Vessel Level channel are
- inoperable, repairs may only be possible during an extended C013 SHUTDOWN.
I This is because the sensors are accessible only after the plant has been cooled down and drained, and the missile shield has been moved. If only one channel is inoperable, it should be restored to 0PERABLE status in accordance with the schedule outlined in a Special Report.
If both j
channels are inoperable, the system shall be restored to OPERABLE status in j
the next refueling outage.
l 3/4.3.3.7 Fire Detection Instrumentation i
j OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is. required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to i.
l safety related equipment and is an integral element in the overall facility j
i In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to 0PERABILITY.
i
.3.3.9 Radioactive Gaseous Effluent Monitorina Instrumentation The ra ctive gaseous effluent instrumentation is provided to or and j
- control, pp11 cable, the releases of radioactive materials aseous i
effluents du actual or potential releases of gaseous ef ents. 1The l
'T' alarm / trip setpo s for these instruments shall be calc ted and adjusted j-A in accordance with methodology and parameters in e ODCM to ensure that. tiie alam/ trip wi ccur prior to exceedin e limits of r
i M Specification 3.11.2.1.a a d on average ann
/Q. The OPERABILITY and l-use of this instrumentation onsistent the requirements of General Design Criteria 60, 63, and 64 o pen A to 10 CFR Part 50.
3/4.3.3.10 Radioactive Liaufd E en nitorina Instrumentation The radioactive liquid eff nt instrumentati is provided to monitor and
{
control, as applicable e releases of radioact materials in liquid i
effluents during ac or potential releases of liq effluents. The j*
J &
alam/ trip setpo s for these instruments shall be cal ated and adjusted in accordanc th the methodology and parameters in the 0 to ensure that the m/ trip will occur prior to exceeding the limits o 10 CF rt 20. The OPERABILITY and use of this instrumentation co tent with the requirements of General Design Criteria 60, 63, 64 j
Appendix A to 10 CFR Part 50.
I; I
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1 1
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CALVERT CLIFFS - UNIT 1 B 3/4 3-3 Amendment No. 199 l
I
3/4.11 RADI0 ACTIVE EFFLUENTS
~
ES 3/4.
.1 LIOUID EFFLUENTS 3/4.11.
1 Concentration This speci cation is provided to ensure that the concentration of radioactive terials released in liquid waste effluents to UNR ICTED AREAS will be ess than the concentration levels specified in i
10 CFR Part 20, ppendix B. Table II, Column 2.
This limitati provides additional assur ice that the levels of radioactive material in bodies of water in UNRESTRI)
AREAS will result in exposures wi_ thin 1) the Section II.A desig pbjectives of 10 CFR Part 50, Appendix to a MEMBER OF THE PUBLIC and (2) limits of 10 CFR 20.106(e) to the opulation.
[
The required detection pabilities for radioactive ma rials in liquid waste samples are tabula d in tenns of the lower li ts of detection (LLDs). Detailed discussi of the LLD, and other tection limits can be found in HASL Procedures Ma al, HASL-300, Currie
..A., " Limits for Qualitative Detection and Qua titative Determina on - Application to Radiochemistry," Anal. Chem. 4 586-93 (1968), nd Hartwell, J.K.,
" Detection Limits for Radioanal ical Countin echniques " Atlantic Richfield Hanford Company Report H-SA-215 une1975).
3/4.11.1.2 Dose m
=
This specification is provided to impi nt the requirements of H.H 10 CFR Part 50, Appendix I, Sections III.A and IV.A. The Limiting Condition for Operation implements t e gu es set forth in Appendix I, N
Section II.A. The ACTION statemen provi the required operating v
flexibility and at the same time plement t guides set forth in
[
Appendix I,Section IV.A to ass e that the re ases of radioactive material in liquid effluents t UNRESTRICTED AR will be kept "as low as
--(
is reasonably achievable." T e dose calculation thodology and parameters
- Is in the ODCM implement the r utrements in Appendix,Section III.A that conformance with the guid of Appendix I be shown calculational procedures based on mode and data, such that the ac al exposure of a s
p MEMBER 0F THE PUBLIC th ugh. appropriate pathways is u 'ikely to be dw substantially underes mated. The equations specified 1 the CDCM for i
calculating the dose due to the actual release rates of dioactive A
materials in. liqui effluents are consistent with the meth ology provided 3
in Regulatory Gui 1.109, " Calculation of Annual Doses to P from Routine Releases of Rea r Effluents for the Purpose of Evaluating C pliance with 10 CFR Part 50 Appendix I," Revision 1, October 1977. Regulat Guide 1.113 stimating Aquatic Dispersion of Effluents from Ac idental and Routine eactor Releases for the Purpose of Implementing Appe fx I,"
April 1977 and NUREG-0133. " Preparation of Radiological Effluent chnical Specific ons for Nuclear Power Plants".
CALVERT CLIFFS - UNIT 1 B 3/4 11-1 Amendment No. 169 i
3/4.11 _RADI0 ACTIVE EFFLUENTS
~
ES 3/ 11.1.3 Liouid Radwaste Treatment System The re f rement that the appropriate portions of this system be use, when specifi
, provides assurance that the releases of radioactive mat liquid e tals in uents will be kept "as low as is reasonably achievabl This specificat n implements the requirements of 10 CFR 50.36a, of e
i 10 CFR Part 0, Appendix A. General Design Criterion 60 and t design objective giv in 10 CFR Part 50, Appendix I, Section II.D.
The specified limits governi the use of appropriate portions of the Li d Radwaste l
Treatment System ere specified as a suitable fraction of le dose design l
objectives set fo h in 10 CFR Part 50, Appendix I, Sect n II.A for liquid l
effluents. The dos limits apply-to the combined efflu t of the plant l
(e.g., two units).
3/4.11.2 _GASE0US EFFLU TS 3/4.11.2.1 Dose Rate This specification is provide to ensure that he dose at any time at and beyond the SITE B0UNDARY from seous efflue s from all units on the site will be within the annual dose 1 its of I CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits at the do s associated with the concentrations of 10 CFR Part 20, en x B. Table II, Column 1.
These
~
limits provide reasonable assurance gaseous effluents will not result in radioactive material discharged in
>=H in an UNRESTRICTED AREA, exceeding e exposure of a MEMBER OF THE PUBLIC q
Appendix B. Table II (10 CFR 20.10' b)). mits specified in 10 CFR Part 20 e
For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUN tY, the cupancy of that MEMBER OF THE P
Pl!BLIC will be sufficiently low o compensa for any increase in the i
.T.s atnospheric diffusion factor a ve that for t e SITE BOUNDARY.
H The required detection capa lities for radioac 've materials in gaseous l
?s waste samples are tabulat in terms of the lower imits of detection l 1 (LLDs). Detailed discus on of the LLD, and other etection limits can be F--1 found in HASL Procedur Manual, HASL-300, Currie, L
" Limits for Qualitative Detection nd Quantitative Detennination Application to
-9 Radiochemistry," Ana. Chem. 40, 586-93 (1968), and Ha well, J.K.,
" Detection Limits r Radioanalytical Counting Technique " Atlantic lA Richfield Hanford ompany Report ARH-SA-215 (June 1975).
L Cha ed by NRC letter dated April 26. 1993 l
t CALVERT CLIFFS - UNIT 1 B 3/4 11-2
- i
3/4.11 _RADI0 ACTIVE EFFLUENTS ~
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^
3/4.1 2.2 Dose - Noble Gases This spe fication is provided to implement the requirements of 10 CF Part 50, pendix I, Sections II.B. III.A and IV.A. The Limiting Co ition for Operat implements the guides set forth in Appendix I, Sectio II.B.
The ACTION s tements provide the required operating flexibility d at the i
same time imp nt the guides set forth in Appendix I, Section
.A to i
assure that the mleases of radioactive material in gaseous ef uents to UNRESTRICTED ARE, will be kept "as low as reasonably achieva e."
The Surveillance Requ ements implement the requirements in App ix I,Section III.A that nformance with the guides of Appendix be shown by calculational proced es based on models and data such th the actual y
exposure of a MEMBER THE PUBLIC through appropriate thways is unlikely r
I to be substantially und estimated. The dose calculat n methodology and parameters established i the ODCM for calculating th doses due to the actual release rates of ra 'ioactive noble gases in <
seous effluents are consistent with the methodo gy provided in Regula ry Guide 1.109,
" Calculation of Annual Doses Man from Routine eleases of Reactor Effluents for the Purpose of E luating Complia e with 10 CFR Part 50, h
Appendix I," Revision 1. Octobe 1977 and Reg atory Guide 1.111. " Methods for Est111ating Atmospheric Transp t and Dis rsion of Gaseous Effluents in y
Routine Teleases fonn Light-Water-oled Re : tors," Revision 1. July 1977, and NUREl-0133 " Preparation of Radio ogic Effluent Technical Specifications for Nuclear Power Plan W4 The ODCM equations provided for dete n g the air doses at and beyond the q
SITE BOUNDARY are based upon the hi oric annual average atmospheric conditions, s
r
[
3/4.11.2.3 Dose - Iodine-131 A Radionuclid In Particulate Form
"""""i This specification is provid to implement the quirements of 10 CFR I.3 Part 50, Appendix I, Sectio s II.C. III.A and IV.
The Limiting Conditions for Operation e the guides set forth i Appendix I, F-- $
Section II.C. The ACTIO statements provide the reg red operating flexibility and at the ame time implement the guides et forth in
{
Appendix I,Section I.A to assure that the releases of adioactive materials in gaseou effluents to UNRESTRICTED AREAS wil be kept "as low as is reasonably a ievable." The ODCM calculational meth ds specified in the Surveillance equirements implement the requirements in ppendix I,Section III.A t t conformance with the guides of Appendix I e shown by calculational rocedures based on models and data, such that t e actual exposure of MEMBER OF THE PUBLIC through appropriate pathways s unlikely to be subst tially underestimated. The ODCM calculational meth ology and CALVERT CLIFFS - UNIT 1 B 3/4 11-3 Amendment No. 169 i
4 6.0 ADMINISTRATIVE CONTROLS The Bases Control Program shall contain provisions to ensure that c.
the Bases are maintained consistent with the UFSAR.
d.
Proposed changes to the Technical Specifications incorporated in the license or proposed changes to the UFSAR or Bases that involve an unreviewed safety question shall be reviewed and approved by the NRC prior to implementation. Changes to the
(
Bases implemented without prior NRC a) proval shall be provided to N
the NRC on a frequency consistent witi 10 CFR 50.71(e).
6.
5 Radioactive Effluent Controls Program (
This rogram conforms to 10 CFR 50.36a for the control of radioactive efflue s and for maintaining the doses to members of the public fro.
i radioact e effluents as low as reasonably achievable. The program hall
{becontai d in the ODCM, shall be implemented by procedures, and all
' include rem tal actions to be taken whenever the program limits re i
exceeded. Th program shall include the following elements:
i
)
i' I
j a.
Limita ons on the functional capability of radio tive liquid i
and gas us monitoring instrumentation, includi surveillance 4
tests and etpoint determination, in accordanc with the methodolog in the ODCM; S
b.
Limitations on he concentrations of radi ctive material released in lig d effluents to unrestr ted areas, conforming to 4
10 CFR Part 20, A endix B, Table II, lumn 2; Y
a c.
Monitoring, sampling, and analysis radioactive liquid and g
gaseous effluents, in cordance th 10 CFR 20.1302, and with the methodology and para eters the ODCM; z
d.
Limitations on the annual a quarterly doses or dose commitment k
to a member of the public radioactive materials in liquid g
effluents released from e h u t to unrestricted areas, conforming to 10 CFR Pa 50, A endix I; M
e.
Determination of cum ative and pro' cted dose contributions from Q
radioactive efflue s for the curren calendar quarter and q
current calendar ear, in accordance w h the methodology and parameters in t CDCM. at least every days;
\\
f.
Limitations the functional capability an use of the liquid 5
and gaseou effluent treatment systems to en re that appropriate portions f these systems are used to reduce r ' eases of radioac vity when the projected doses in a per' d of 31 days
(
would xceed 2% of the guidelines for the annual se or dose
)
co
' ment, confonning to 10 CFR Part 50, Appendix
/
g.
itations on the dose rate resulting from radioactiv material eleased in gaseous effluents to areas beyond the site undary conforming to the dose associated with 10 CFR Part 20, Appendix B, Table II, Column 1; I
-s CALVERT CLIFFS - UNIT 1 6-6 Amendment No. 216
r I
INSERT "6.5.5" 6.5.5 Radioactive Effluent Controls Program l
This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the l
l doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable.
l l
The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
Limitations on the functional capability of radioactive liquid and gaseous monitoring a.
instrumentation, including surveillance tests and setpoint detennination, in accordance with the methodology in the ODCM; b.
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2; c.
Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302, and with the methodology and parameters in the ODCM; d.
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF TIIE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS to be limited:
1.
During any calendar quarter: Less than or equal to 3 mrems to the total body, and to less than or equal to 10 mrems to any organ; and 2.
During any calendar year: Less than or equal to 6 mrems to the total body, and to less than or equal to 20 mrems to any organ; i
l l
i
I l
l l
INSERT "6.5.5" (continued)
Determination of cumulative and projected dose contributions from radioactive effluents e.
for the current calendar quarter and current calendar year, in accordance with the methodology and parameters in the ODCM, at least every 31 days; f.
Limitations on the ftmetional capability and use of the Liquid Radwaste Treatment System to ensure that appropriate portions of this system are used to reduce releases of radioactivity when the projected doses to UNRESTRICTED AREAS exceeds 0.36 mrem to the total body, or 1.20 mrem to any organ in a 92-day period; g.
Limitations on the functional capability and use of the Gaseous Radwaste Treatment l
System and the Ventilation Exhaust Treatment System to ensure that appropriate l
1 l
portions of these systems are used to reduce releases of radioactivity when the calculated doses to UNRESTRICTED AREAS exceeds 1.20 mrad for gamma radiation, and l
2.40 mrad for beta radiation in a 92-day period; h.
Limitations on the functional capability and use of the Ventilation Exhaust Treatment l
System to ensure that appropriate portions of this system are used to reduce releases of l
l radioactivity when the calculated doses due to gaseous releases to UNRESTRICTED AREAS exceeds 1.8 mrem to any organ in a 92-day period; l
i.
Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY, to be limited:
l I
1.
For noble gases: Less than or equal to 500 mrems/yr to the total body, and less than or equal to 3000 mrems/yr to the skin; and 2.
For iodine-131 and for all radionuclides in particulate form with half lives i
greater than 8 days: Less than or equal to 1500 mrems/yr to any organ; i
INSERT "6.5.5" (continued) j.
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the SITE BOUNDARY, to be limited:
l 1.
During any calendar quarter: Less than or equal to 10 mrads for gamma radiation, and less than or equal to 20 mrads for beta radiation; and l
2.
During any calendar year: Less than or equal to 20 mrads for gamma radiation, and less than or equal to 40 mrads for beta radiation; l
k.
Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from iodine-131, and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released to areas beyond the SITE BOUNDARY, to be limited:
I 1.
During any calendar quarter: Less than or equal to 15 mrems to any organ; 2.
During any calendar year: Less than or equal to 30 mrems to any organ; and 3.
Less than 0.1% of the limits of 6.5.5.k(l) and (2) as a result of burning contaminated oil; and 1.
Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity, and to radiation from uranium fuel cycle sources to be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
l l
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i
6.0 ADMINISTRATIVE CONTROLS 4
Limitations on th[ annual and quarte.rly air doses resulting from y-ioble gases released in gaseous effluents from each unit to are b
the site boundary, conforming to 10 CFR Part 50, k
Appen A
1.
Limitations on t, nual and quarterly as to a member of the public from iodine-13,
dine-133 um, and all radionuclides in particula with half lives > 8 days in N
gaseous effluents relea rom unit to areas beyond the 14 site boundary, co ing to 10 CFR 0, Appendix I; and h
j.
Limit on the annual dose or dose commitmen any member e public due to releases to radioactivity and to iation i
v from uranium fuel cycle sources, conforming to 40 CFR Part w
A 6.5.6 Containment Leakaae Rate Testina Proaram l
A program shall be established to implement the leakage testing of the t
containment as required by 10 CFR 50.54(o) and 10 CFR Part 50, Appendix J, l
Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, l
l
" Performance-Based Containment Leak-Test Program," dated September 1995, as I
modified by approved exceptions.
The peak calculated containment internal pressure for the design basis loss-of-coolant accident, P., is 49.4 psig. The containment design pressure is 50 psig.
The maximum allowable containment leakage rate, L., shall be 0.20 percent of containment air weight per day at P,.
Containment leakage rate acceptance criterion is 51.0 L. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria is 5 0.75 L, for Type A tests.
The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.
The provisions of Specification 4.0.3 are applicable to the Contair. ment l
Leakage Rate Testing Program, i
l I
l CALVERT CLIFFS - UNIT 1 6-7 Amendment No. 216
6.0 ADMINISTRATIVE CONTROLS 6.6 REPORTING RE0VIREMENTS The following reports shall be submitted in accordance with 10 CFR 50.4.
6.6.1 Occupational Radiation Exposure Report
- A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures > 100 mrem /yr and their associated man rem exposure according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance [ describe maintenance], waste processing, and refueling).
This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignment to various duty functions may be i
estimates based on pocket dosimeter, electronic personal dosimeter or l
thermoluminescent dosimeter.
Small exposures totalling < 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources i
should be assigned to specific major work functions.
The report shall be j
submitted prior to March 31 of each year.
l l
6.6.2 Annual Radiological Environmental Operatina Report The Annual Radiological Environmental Operating Report covering the o e_ ratio f he unit during the previous calendar year shall be submitted P Y tl 1 1 4 each year..g g
f Cube Thereportshallincludesummaries, interpretations,andanalysesoftrends of the results of the Radiological Environmental Monitoring Program for the wd.5 prevl'u84 reporting period. The material provided shall be consistent with the Pdfd$r,PA objectives outlined in the ODCM, and in 10 CFR Part 50, Appendix I, Qections B.2, IV.B.3 and IV.C. __
l
'vGrA[hoUeloyaf Envicen enfal Opedin])
The eport'shall include the results of'Hnalyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and i
figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. gin the event that some individual results are not available for inclusio 1 with the report, the report shall be submitted noting and explaining the roasons for the missin results.
The missin data shall be submitted as soon as
~
P possible in a supplementaryfrepor.
i l
ott s allidenlif $e TLD renHs Aat npresenf collocoled dosimefees y
f)e A)?C 72D program,and tbe exposure period agociafeof in re/affen to I
l 8 each resull.
- ^
^
A single submittal may be made for Calvert Cliffs. The submittal should combine those sections that are common to both units.
Occupational dose from the Independent Spent Fuel Storage Installation will be reported separately.
CALVERT CLIFFS - UNIT 1 6-8 Amendment No. 216 l
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1 i
l 6.0 ADMINISTRATIVE CONTROLS 6.6.3 Radioactive Effluent Release Report
- j' The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a (i.e.,
e between submittal of the reports must be no longer than 12. months) **
P C.,.4",'8 The report shall include a summary of the quantities of radioactive liquid d ' di'"3 and gaseous effluents and solid waste released from the units. The t
t
( material provided shall be consistent with the objectives outlined in the
)
Br9,y 00CM and Process Control Program and in conformance with 10 CFR 50.36a and (10CFRPart50,AppendixI,SectionIV.B.1.
Licensee initiated major changes to the Radioactive Waste Systems (liquid, gaseous and solid) shall be reported to the Commission in the Radioactive Effluent Release Report for the period in which the modification to the waste system is completed. The discussion of each change shall contain:
a.
A description of the equipment, components and processes involved; and g
b.
Documentation of the fact that the changeVincluding the safety 1
analysis was reviewed and found acceptable by the onsite review i
function.
The report shall also include changes to the ODCM, in accordance with Specification 6.5.1.c.
4 i
6.6.4 Monthly Operating Report Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis, no later than the 15th of each month following the calendar month covered by the report.
-h 7
- In lieu of submissien u;ik the Radioaahve EHluenf & lease &parf Sr
I and Se'* analyses results may be submi%l in.n supplementary repor,t within 120 days a% submiHal of de bdicacke Ef//ues,t brease & pert.
/
A
-w e
i A single submittal may be made for Calvert Cliffs, since the Radwaste i
Systems are comon to both units.
Y CALVERT CLIFFS - UNIT 1 6-9 Amendment No. 216
l 4
ATTACHMENT (3)
J i
UNIT 2 TECIINICAL SPECIFICATIONS MARKED-UP PAGES I, IV, VII, IX, XIII, XIV 1-4 -- 1-8 3/43-41-3/43-50 3/4 11-1 --3/4 11-19 3/4 12-1 --3/4 12-15 B 3/4 3-3 B 3/411-1 -- B 3/411-5 B 3/412-1 B 3/412-2 6-6 -- 6-9 Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant September 4,1996
TABLE OF CONTENTS DEFINITIONS l
SECTION PAGE 1.0 DEFINITIONS l
l Defined Terms...................
1-1 Action 1-1 Axial Shape Index.................
1-1 l
Azimuthal Power Til t - T,.............
1-1 Channel Calibration................
1-1 Channel Check...................
1-2 Channel Functional Test..............
1-2 Containment Integrity...............
1-2 Controlled Leakage 1-3 Core Al te rati on..................
1-3 Core Operating Limits Report (COLR)........
1-3 l
Dose Equivalent I-131...............
1-3 E-Average Disintegration Energy..........
1-3 Engineered Safety Feature Response Time......
1-3 l
Frequency Notation 1-4 l
Gaseous Radwaste Treatment System.........
1-4 Identified Leakage 1-4 Member (s) of the Public..............
1-4 Offsite Dose Calculation Manual (0DCM) 1-4 Operable - Operability 1-5 l
Operational Mode 1-5 Physics Tests....................
1-5 Preisure Boundary Leakage.............
6dds4 CMn r 1 Yrigrlm \\(P[PX L A.\\.i.x....
~_
1 Purge-P~ urging...................
Rated Thermal Power................
1-6 Nk Reactor Trip System Response Time.........
1-6 Reportable Event 1-6 Shutdown Margin..................
1-6 W
Si Boundary.
1-6 9
luf W.': M :t:T.S:\\:9:':M Staggered Test Basis 1-7 Thermal Power...................
1-7 Total Integrated Radial Peaking Factor - F,....
1-7 Total Planar Radial Peaking Factor - P......
1-7 y
Unidentified Leakage 1-7 Unrestricted Area.................
1-8 l
Ventilation Exhaust Treatment System 1-8 Venting......................
1-8 I
i l
i CA', VERT CLIFFS - UNIT 2 I
Amendment No. 163
TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAG $
3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION..................
3/4 3-9 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3-23 Meteorological Instrumentation 3/4 3-27 Remote Shutdown Instrumentation..........
3/4 3-30 Post-Accident Instrumentation...........
3/4 3-33 Fire Detection Ins tation e
3/4 3-37 y
a t e as ou E f1 fn n1 or ng
~
y ns ;ru n at n...
3 l
ad' a ti L qu d ff ue t on to in a
( st um nt ti 4
l 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION STARTUP and POWER OPERATION.....
3/4 4-1 NOT STANDBY.............
3/4 4-2 Shutdown 3/4 4-4 3/4.4.2 SAFETY VALVES...................
3/4 4-6 3/4.4.3 RELIEF VALVES...................
3/4 4-7 3/4.4.4 PRESSURIZER....................
3/4 4-9 3/4.4.5 STEAM GENERATORS 3/4 4-10 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.............
3/4 4-17 Reactor Coolant System Leakage 3/4 4-19 3/4.4.7 CHEMISTRY.....................
3/4 4-21 l
3/4.4.8 SPECIFIC ACTIVITY.................
3/4 4-24 1
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CALVERT CLIFFS - UNIT 2 IV Amendment No. 176
)
i TABLE OF CONTENTS LIMITING CONDITIO@ FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION fAGE 3/4.9.13 SPENT FUEL CASK HANDLING CRANE 3/4 9-19 3/4.9.14 CONTAINMENT VENT ISOLATION VALVES.........
3/4 9-20 3/4.10 SPECIAL TEST EXCEPTIONS l
3/4.10.1 SNUTDOWN MARGIN..................
3/4 10-1 i
3/4.10.2 MODERATOR TEMPERATURE COEFFICIENT, CEA INSERTION AND POWER DISTRIBUTION LIMITS...........
3/4 10-2 l
3/4.10.3 NO FLOW TESTS...................
3/4 10-3 3/4.10.4 CENTER CEA MISALIGNMENT.............. 3/4 10-4 3/4.10.5 COOLANT CIRCULATION.............
3/4 10-5 l
l 3/4.11 RADI0 ACTIVE EFFLUENTS
$E/ETE l
L U FU T o ce tr ti n.
/
s 4
,5 Lq d a a te T a me t yt 3
,f 3/0.13 SEOUS EFFLUENTS os t
3 D se - o'le Ga es
/ t 1:, 1 e
i D
e-oc ne 1 n
d n el d h
in Pa t t F rm.
Explosive Gas Mix ure.............\\.
_3/4 1 I
_ 0 E R S
41 1 m9 Gas Storage Tanks.................
3/4 11 2
3
.1.
OL D 10 C V WA T 34 Yi
/4 11 4 T TA DS 3/ 11 1 BEL 6YE l
l l
i l
CALVERT CLIFFS - UNIT 2 VIII Amendment No. 149
TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILUDICE REQUIREMENTS G
\\
t i3
.12 L
CA IR A M0 T0R NG 1
1
- 4. 2.1 M0 IT IN PR 4
i 3/.12 2 ND US CE US 3/ 12-3 4.
.3 I ER B0 TO C PA S P G 3
1 -15 l
l l
DELE 7'E l
- l l
l l
f CALVERT CLIFFS - UNIT 2 IX Amendment No. 149
i 1
TABLE OF CONTENTS l
BASES 1
l SECTION PAGE 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 9-3 l
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 FliEL 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 9-4 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN..................
B 3/4 10-1 l
l 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 3/4.10.5 COOLANT CIRCULATION................
B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 ' '^"'" EFFLUENTS B 3/4 11-1
/.1.
F U T.5..
3
\\
[34.1.
4 1-
/.1.4
$L, O E B /4 1 DELETE l
l l
CALVERT CLIFFS - UNIT 2 XIII Amendment No. 149
l TABLE OF CONTENTS i
RAD OL CA EN R0 E L
N ORI
/4 2.1 IT IN PR 3
1 1 3
.1 2
US CEN US B
4
-1 1
4.1.3 IN R 0
~
l DEL E TE l
L l
l l
)
l
?
CALVERT CLIFFS - UNIT 2 XIV Amendment No. 149 l
l
l 1.0 DEFINITIONS FRE00ENCY NOTATION 1.15 The FREQUENCY NOTATION specified for the performance of Surveillance l
Requirements shall correspond to the intervals defined in Table 1.2.
q.
GASE0US RADWASTE TREATMENT SYSTEM 1.16 'A GASE0US RADWASTE TREATMENT SYSTEM is any system designed and l
installed to reduce radioactive gaseous effluents by collecting Primary Coolant System offgases from the Primary System and providing for delay or l
holdup for the purpose of reducing the total radioactivity prior to release to the environment.
I IDENTIFIED LEAKAGE i
1.17 IDENTIFIED LEAKAGE shall be:
l l
Leakage (except CONTROLLED LEAKAGE) into closed systems, such as a.
pump seal or valve packing leaks that are captured, and conducted l
to a sump or collecting tank, or I
l b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE B0UNDARY LEAKAGE, or Reactor Coolant System leakage through a steam generator to the c.
Secondary System.
MEMBERfS) 0F THE PUBLIC 1.18 MEMBER (S) 0F THE PUBLIC shall include all persons who are not l
occupationally 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.
Th 0FF TE D LC CU ON NUA shal con in e cu ent l
m hodo ogy dp amet su d in he 1cul tion fo sit dose du to l
adio tive ase ca lig d ef uen
,i the alcu atto of seo a
l i
liqu eff uent ont ring la trip etp nts and n th con et f tj env onm tai adio gic mon ori pro am.
'REPUCE k//7W JNSEW"1.]9" i
f CALVERT CLIFFS - UNIT 2 1-4 Amendment No. 163
l INSERT "1.19" OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.19 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid i
l effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain the radioactive effluent controls, radiological environmental monitoring activities, and descriptions of the l
information that should be included in the Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report, required by Specifications 6.6.2 and 6.63, respectively.
l I
l l
l l
{
I
1.0 DEFINITIONS OPERABLE - OPERABILITY l
1.20 A system, subsystem, train, component or device shall be OPERABLE or l
l have OPERABILITY when it is capable of performing its specified l
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, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).
OPERATIONAL MODE' 1.21 An OPERATIONAL MODE shall correspond to any one inclusive combination l
of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.
PHYSICS TESTS 1.22 PHYSICS TESTS shall be those tests performed to measure the l
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 Comission.
PRESSURE BOUNDARY LEAKAGE 1.23 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator l
tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.
PROCEd CONT /0L PR[ GRAM [CP) 1.2 The ROCE CONT OL PR RAM all ontai the tren form a,
l sa.pling anal es,
- sts, dd ennin tion to be ade o en re th t the p ocess" g an pack ing o soli radi acti was s ba d on emon rate roces ng o actu or s ula d we soli wast wil be a compi hed i
such way to sure ompi nce th I CFR rt 2, 10 FR P t 71 nd Fede 1 an Stat and 1 cal gula ons overn gt dis sal the rad acti was l
DELETE
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l CALVERT CLIFFS - UNIT 2 1-5 Amendment No. 163 l
1.0 DEFINITIONS PURGE - PURGING l.2 Y
- h. PURGE or PURGING is the controlled process of discharging air or gas l
g from a confinement to maintain temperature, humidity, concentration or other operating condition, in such a manner that replacement air or gas is i
required to purify the confinement.
RATED THERMAL POWER f,26 RATED THERMAL POWER shall be a total reactor core heat transfer rate l
he reactor coolant of 2700 MWt.
REACTOR TRIP SYSTEM RESPONSE TINE The REACTOR TRIP SYSTEM RESPONSE TINE shall be the time interval from l
l*
/
w en the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.
REPORTABLE EVENT yg A REPORTABLE EVENT shall be any of those conditions specified in l
ec ion 50.73 to 10 CFR Part 50.
SHUTOOWN MARGIN 0 1. 2 0 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by l
l w c the reactor is subcritical or would be subcritical from its present u
condition assuming all full length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully withdrawn.
SITE B0UNDARY f,2 The SITE B0UNDARY shall be that line beyond which the land is l
j ne ther owned, nor leased, nor otherwise controlled by the licensee.
I d IFID[TI0 /
S0 to!fo
.31 0 LID ICAT N all et co ers no we was s t t
]
(meet shi ing db ial rou re ir nts
/
/
/
Y DEL ETE CALVERT CLIFFS - UNIT 2 1-6 Amendment No. 163
1 l
l 1.0 DEFINITIONS l
SOURCE CHECK h A SOURCE CHECK shall be the qualitative assessment of channel l
O],30
'y response when the channel sensor is exposed to a source of increased radioactivity.
STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of:
l a.
A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test l
interval into n equal subintervals, and b.
The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
l THERMAL POWER yf,
- h. THERMAL POWER shall be the total reactor core heat transfer rate to l
/the reactor coolant.
l W
l TOTAL INTEGRATED RADIAL PEAKING FACTOR - FJ l
J The TOTAL INTEGRATED RADIAL PEAKING FACTOR is the ratio of the peak l
p n power to the average pin power in an unrodded core.
TOTAL PLANAR RADIAL PEAKING FACTOR - FI, l
],3//
The TOTAL PLANAR RADIAL PEAKING FACTOR is the maximum ratio of the l
pea to average power density of the individual fuel rods in any of the unrodded horizontal planes.
UNIDENTIFIED LEAKAGE gQL l
1.35
.7 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED l
GE or CONTROLLED LEAKAGE.
l j
CALVERT CLIFFS - UNIT 2 1-7 Amendment No. 163
s 1.0 DEFINITIONS l
l UNRESTRICTED AREA 1.N f.8 An UNRESTRICTED AREA shall be any area at or beyond the SITE B0UNDARY l
l l
arcess to which is not controlled by the licensee for purposes of i
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 f,37
'g A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and l
.9 j
ns alled to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing 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 TREATHEMI i
SYSTEM components.
i VENTING m*
'rO.4 VENT 1NG is the contreiied process of dischereiae e4r er ses from e i
j 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 l
l l
l CALVERT CLIFFS - UNIT 2 1-8 Amendment No. 163
i l
4.3. INSTRUMENTATION
~
3/4. 3 MONITORING INSTRUMENTATION l
_ Radioactive Gaseous Effluent Monitorina Instrumentation l
l LIMITING C DITION FOR OPERATION l
l e1 3.3.3.9 The dioactive gaseous effluent monitoring instrum tation channels shown n Table 3.3-12 shall be OPERABLE with their lam / trip setpoints set to nsure that the limits of Specification 3 1.2.1 are not exceeded. The al
/ trip setpoints of these channels sh 1 be detemined and adjusted in acc dance with the methodology and par eters in the CDCH.
4 I
APPLICABILITY: As sho n in Table 3.3-12.
N ACTION:
l a.
With a radioactiv gaseous effluent nitoring instrumentation i
channel alam/ trip etpoint less co ervative than required by the above Specificat n, without ay suspend the release of H
radioactive gaseous e luents mo tored by the affected channel, or declare the channel noperab e, or change the setpoint so it l
is acceptably conservati H
b.
With less than the minimum umber of radioactive gaseous effluent r
l H monitoring instrumentatio c nnels OPERABLE, take the ACTION shown in Table 3.3-12.
xert est efforts to return the instruments to OPERABL status ithin 30 days and, if "T'
unsuccessful, explai in the nex Semiannual Radioactive Effluent Release Report why e inoperabili was not corrected in a e
timely manner.
M l
c.
The provisions f Specifications 3.0.3 nd 3.0.4 are not
{s applicable.
l t
SURVEILLANCE REQ REMENTS 4.3.3.9 Eac radioactive gaseous effluent monitoring instr entation channel sha be demonstrated OPERABLE by perfomance of the ANNEL CHECK, SOURCE CH
, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST erations at the freq ncies shown in Table 4.3-11.
i I
4 CALVERT CLIFFS - UNIT 2 3/4 3-41 Amendment No. 176 l
~
DELETE THIS PAGE g
TABLE 3.3-12 g
RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION U
b MINIMUM CHANNELS q
_I UMENT OPERABLE APPLICABILITY CTION E
m 1.
WASTE GAS HOLDUP SYST x
g C5 a.
Noble Gas Activity Mon r - Providing 1
35 d
Alarm and Automatic Temi ion of E
Release b.
Effluent System Flow Rate Measurin 1
36 Device 2.
MAIN VENT SYSTEM a.
Noble Gas Activity Monitor 1
Y'
. 37 g;
b.
Iodine Sampler 38 c.
Particulate Sampler 1
~38 a
R 3
n E.F m
I m
m m
-.-m m-
l 4.3 INSTRUMENTATION
,/
TABLE 3.3-12 (Continued)
TABLE NOTATION At al times.
ACTION STATEMENTS
~
g ACTION 35 -
With t e number of channels OPERABLE les than required by
- g the Min um Channels OPERABLE requireme
, the contents of l
N the tank may be released to the en ronment:
a.
Using t main vent monitor as backup and recording RMS I
readings very 15 minutes dur g the release, or b.
Provided th prior to int ating the release, at least H
two independe t samples o the tank's contents are analyzed, and least o technically qualified members
! HH of the Facility taff dependently verify the release rate calculations n two qualified operators verify the b,d discharge valve li p.
Otherwise, suspend r eas of radioactive effluents via this pathway.
-w1 ACTION 36 -
With the number channels O RABLE less than required by the Minimum Ch nels OPERABLE r quirement, effluent releases
-y via this path y may continue pr ided the flow rate is estimated a least once per 4 hou r
w 1
ACTION 37 --
With the umher of channels OPERABLE ess than required by 4
the Min um Channels OPERABLE requirem nt, effluent releases l
b, via t 's pathway may continue provided ther (1) grab samp s are taken and analyzed for gross ctivity at least per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or (2) an equivalent mo itor is provided.
one ACTION 38 -
O th the number of channels OPERABLE less tha required by the Minimum Channels OPERABLE requirement, ef ent releases
=====.
via the affected pathway may continue provided mples are continuously collected as required in Table 4.11-with auxiliary sampling equipment.
1 CALVERT CLIFFS - UNIT 2 3/4 3-43 Amendment No. 176 l
~
DELETE THIS PAGE g
TABLE 4.3-11 r-h ADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
.m.
'w n
C MS E
CHANNEL 6
4 q
CHANNEL SOURCE CHANNEL FUNCTIONAL S
EILLANCE g
7 INSTRUM CHECK
_ CHECK CALIBRATION TEST
_ REQUIRED m
E 1.
WASTE GAS HOLDUP SYSTEM y
a.
Noble Gas Activity Monitor P
P I3 R)
SAM Providing Alam and Automatic Temination of Release b.
Effluent System Flow Rate D
NA R
NA Measuring Device g
5 2.
MAIN VENT SYSTEM 4
a.
Noble Gas Activity Monitor D
I2 b.
Iodine Sampler NA NA NA c.
Particulate Sampler W
NA NA NA h
E F
g
/4.3 INSTRUMENTATION
,/
~
TABLE 4.3-11 (Continued)
TABLE NOTATION At al times other than when the line is valved out and eked.
3 1
(1)
The C L FUNCTIONAL TEST shall also demonstrate th automatic isolation f this pathway and/or Control Room alarm nunciation l
occurs if t e appropriate following condition (s) e sts:
l I
g
,1.
Instrumen indicates measure levels above th alann/ trip ig
~
setpoint.
N 2.
Circuit failu 3.
Instrument indic es a downscale fail re.
,[
(2)
The CHANNEL FijNCTIONAL ST shall also emonstrate that Control Room alarm annunciation occurs if any of e following conditions exist:
H 1.
Instrument indicates me ured eyels above the alarm setpoint.
2.
Circuit failure.
3.
Instrument indicates a d nse le failure.
(3)
-w The initial CHANNEL CALIB TION shal be performed using one or more 1
of the reference standar s traceable the National Bureau of Standards or using sta ards that have een obtained from suppliers
,q that participate in asurement assuranc activities with NBS.
These standards shall pe t calibrating the sy em within its intended
-5 range of energy an measurement range.
For ubsequent CHANNEL 1
CALIBRATION, sour es that have been related the initial calibration can e used.
3 (4)
The CHANNEL ECK shall consist of verifying ind ation of flow
-5 during peri ds of release and shall be made at lea t once per 24 1
hours on ys on which effluent releases are made.
O l
CALVERT Cliffs - UNIT 2 3/4 3-45 Amendment No. 176 l
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/4.3 INSTRUMENTATION
~
3 3.3 MONITORING INSTRUMENTATION Radioactive Liould Effluent Monitorino Instrumentation LIMITING NDITION FOR OPERATION 3.3.3.10 Th radioactive liquid effluent monitoring instru ntatio~n channels shown i'n Table 3.3-13 shall be OPERABLE with thei alam/ trip setpoints set t ensure that the limits of Specification
.11.1.1 are not exceeded. The a m/ trip se points of these channels s 1 be detemined and adjusted in ac rdance with the methodology and pa meters in the M
0FFSITE DOSE CALCU ION MANUAL (0DCM).
<N APPLICABILITY: At all imes.
ACTION:
a.
With a radioactive liquid effluent.onitoring instrumentation channel alarm / trip tpoint less onservative than required by H
the above Specificat n, withou delay suspend the release of M
radioactive liquid ef uents nitored by the affected channel, or declare the channel ioper ble, or change the setpoint so it is acceptably conservati H
b.
With less than the minim mber of radioactive liquid effluent monitoring instrumenta on ch nnels OPERABLE, take the ACTION l
shown in Table 3.3-13 Exert st efforts to return the l
" ~r '
instruments to OPE E status thin 30 days and, if d
unsuccessful, exp1 n in the next emiannual Radioactive Effluent Release Report wh the inoperabili was not corrected in a H
timely manner.
T c.
The provisio of Specifications 3.0.3 nd 3.0.4 are not applicable.
s 5.
SURVEILLANCE R UIREMENTS 4.3.3.10 ch radioactive liquid effluent monitoring instrun ntation channel s 11 be demonstrated OPERABLE by perfomance of the NEL CHECK.
1 SOURCE C CK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST o rations at the fr uencies shown in Table 4.3-12.
o CALVERT CLIFFS - UNIT 2 3/4 3-46 Amendment No. 176 l
i
/4.3 INSTRUMENTATION TABLE 3.3-13 l
_RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM l
5 1,
CNANNELS INSTRUMENT OPERABLE ACTION 1.
GROSS RADI CTIVITY MONITORS PROVIDING
~
ALARM AND AU TIC TERMINATION OF l
RELEASE a.
Liquid Radwa e Effluent Line 1
28 l
b.
Steam Generator lowdown Effluent 1
29 Line
[
2.
FLOW RATE MEASUREMENT D CES
! H a.
Liquid Radwaste Effluen Line 1
30 l hd b.
Steam Generator Blowdown 'fl ent 1
30 hd Line H
r 3
r M
1:
s s
l
-s m
CALVERT CLIFFS - UNIT 2 3/4 3-47 Amendment No. 176 l
4.3 INSTRUMENTATION TABLE 3.3-13 (Continued)
ACTION STATEMENTS 1
ACTION 28 -
With the number of channels OPERABLE less than r utred by
,3{
the Minimum Channels OPERABLE requirement, effl ent releases y continue provided that prior to initiatin a release:
a.
t least two independent samples are a lyzed in cordance with Specification 4.11.1.
1, and 4
I b.
At ast two technically qualified embers of the N
Fact ty Staff independently veri y the release rate calcu tions and two qualified erators verify the dischar valve line up.
ACTION 29 -
With the numbe of channels OP BLE less than required by the Minimum Cha els OPERABLE equirement, effluent releases H
via this pathway ay contin provided grab samples are bd analyzed for gross adioac vity (beta or gama) at the lower limit of dete ion efined in Table 4.11-1:
Hd r
a.
At least once per hours when the specific activity of H
the secondary co a is greater than 0.01 microcurie / gram OSE UIVALENT I-131.
"T' b.
At least onc per 48 hou s when the specific activity of 4==
the second y coolant is ss than or equal to 0.01 microcuri gram DOSE EQUIY ENT I-131.
M ACTION 30 -
With the n ber of channels OPERA E less than required by s
"T the Minirr m Channels OPERABLE requ ement, effluent releases via thi pathway may continue provid the flow rate is 5
estima ed at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> d ing actual releases.
4 Pump erformance curves may be used to timate flow.
-3 l
m I
/
CALVERT CLIFFS - UNIT 2 3/4 3-48 Amendment No. 176 l
DELETE THIS PAGE g
TABLE 4.3-12 G
P g
DI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w
b m
CHANNEL SOURCE CHANNEL OMAL h
q INSTRUMENT CHECK CHECK CALIBRATION TEST E
cn 1.
GROSS RADI0ACTIVIT NITORS PROVIDING ALARM x
E g
AND AUTOMATIC TERMINA 0F RELEASE g
a.
Liquid Radwaste Effluen ine D
P
'R(2)
SAIII E
m b.
Steam Generator Blowdown Effl t Line D
P R(r)
SA )fl 2.
FLOW RATE MEASUREMENT DEVICES R
a.
Liquid Radwaste Effluent Line NA R
NA l
y b.
Steam Generator Blowdown Effluent Line (3)
NA R
NA e
3 5
.?
cn
\\'
4.3 INSTRUMENTATION
[
1 l
TABLE 4.3-12 (Continued)
TABLE NOTATION i
II) s The C NEL FUNCTIONAL TEST shall also demonstrate that tomatic 1
isolati of this pathway and/or Control Room alann an nciation l
occur if he appropriate following condition (s) exist
)
1.
Instrum t indicates measured levels above the lann/ trip setpoint.
4 I
2.
Circuit fai re.
l N
4 3.
Instrument in cates a downscale failur.
(2)
The initial CHANNEL LIBRATION shall be erformed using one or more l
of the reference stan rds traceable to the National Bureau of Standards or using stan rds that hav been obtained from suppliers i
H that participate in meas ement ass ance activities with NBS.
These bd standards shall permit cal rating he system within its intended range of energy and measure nt r ge. For subsequent CHANNEL HH CALIBRATION, sources that hay en related to the initial calibration can be used.
r M
(3)
CHANNEL CHECK shall consist f ve ifying indication of flow during periods of release.
CHAN CHECK hall be made 'at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on whic effluent r leases are made.
M s
, L s
L-s, m
I i
CAtVEP.T CLIFFS - UNIT 2 3/4 3-50 Amendment No. 176 l
l
/4.11 RADI0 ACTIVE EFFLUENTS 3
11.1 LIOUIO EFFLUENTS Concentration LIMITING ONDITION FOR OPERATION
-51 3.11.1.1 T concentration of radioactive material release in liquid effluents to RESTRICTED AREAS shall be limited to the co centrations specified in IC CFR Part 20 Appendix B. Table II, Colum 2 for radionuclides ot r than dissolved or entrained noble ses.
4 APPLICABILITY: At a times.
q ACTION:
a.
With the concent ation of radioacti e material released in liquid effluents to UNRE RICTED AREAS e eeding the above 1tmits, without delay rest e the concen ation to within the above H
limits.
b.
The provisions of Spect ica ons 3.0.3 and 3.0.4 are not applicable.
-H SURVEILLANCE REQUIREMENTS uid wastes shall\\ sampled and analyzed 4.11.1.1.1 Radioactive 1 according to the sampli and analysis prograrh of Table 4.11-1.
.-s1 4.11.1.1.2 The resul s of the radioactivity ana ses shall be used in 4
accordance with the iethodology and parameters in he ODCM to assure that the concentrations t the point of release are main ined within the limits of Specification
.11.1.1.
L m
M CALVERT CLIFFS - UNIT 2 3/4 11-1 Amendment No. 149
4.11 RADIOACTIVE EFFLUENTS TABLE 4.11-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM 0F DETECTION LIQUID RELEAS SAMPLING ANALYSIS TYPE OF ACTIV (LLD)*
TYPE FREQUENCY FREQUENCY ANALYSIS (pci/al)
(M BatchWagte P
P Principal [ama 5x10-'
A.
Releases E h Batch Each Batch Emitters /
I-131/
1x10 4
Mo-M Ce-144 2x104 P
H H/
1x10-5 Composite [ Gross Alpha 1x10-'
d i
Each Batch i H Each Batch si Sr-89,Sr-90 5x104 B.
Turbine H
Principal Gama 5x10-'
H Building Sump Emitters
- l I-131 1x10-'
Ho-99, Ce-144 2x10-8
\\
e M
s S
r 5
l D
~
i 4
CALVERT CLIFFS - UNIT 2 3/4 11-2 Amendment No. 149
/4.11 RADI0 ACTIVE EFFLUENTS TABLE 4.11-1 (Continued)
TABLE NOTATION 5
r The L is defined, for purposes of these specificatio
, as the
".J smalle concentration of radioactive material in a s pie that will yield a et count, above system background, that wi be detected i
l with 95% robability with only 5% probability of f sely concluding j
that a bla observation represents a "real" sig 1.
4 l g For a particu r measurement system, which ma include radiochemical l
y separation:
LLD =
E V
- 2. 2 x 10' Y exp (-
t)
Where:
>==H LLD is the "a priori" ower mit of detection as defined above, as microcuries per uni ma or volume, "q
s, is the standard devia n of the background counting rate or of the counting rate o a ank sample as appropriate, as counts per minute, e
s 1
E is the counting ficiency, a counts per disintegration, V is the sample ize in units of ss or volume, 2.22 x 10' i the number of disinteg tions per minute per 5
1 microcurie Y is th fractional radiochemical yield, hen applicable, l W "T'
1 is he radioactive decay constant for the articular l
rad nuclide, and O
is the elapsed time between sample collectio or end of the sample collection period, and time of counting.
ma Typical values of E, V, Y, and At should be used in the calculation.
It should be recognized that the LLD is defined as an a pri i
(before the fact) limit representing the capability of a mea rement system and not as an a posteriori (after the fact) limit for a particular measurement.
j CALVERT CLIFFS - UNIT 2 3/4 11-3 Amendment No. 149
4.11 RADI0 ACTIVE EFFLUENTS TABLE 4.11-1 (Continued)
TABLE NOTATION b
Prior o sampling Reactor Coolant Waste and Miscellaneo s Waste for
,s1 analyse, each batch shall be isolated, and then thor ghly mixed to i
l assure r resentative sampling.
l c
The princip 1 gama emitters for which the LLD sp ification applies g
exclusively e the following radionuclides: M 54, Fe-59 Co-58, Co-60, Zn-65, s-134. Cs-137 and Ce-141.
This ist does not mean
<q that only these uclides are to be considere Other gama peaks l
that are identif ble, together with those the above r.uclides, shall also be ana zed and reported in the emiannual Radioactive Effluent Release Re ort pursuant to Spec ication 6.9.1.8.
d A composite sample is ne in which th quantity of liquid sampled is proportional to the qua tity of liqu waste discharged in which the H
method of sampling emplo d result in a specimen that is HH representative of the liq "ds rel sed.
bd e
l
-H s
1 i
-s
! m l
1 1
CALVERT CLIFFS - UNIT 2 3/4 11-4 Amendment No. 149
I 4.11 RADIOACTIVE EFFLUENTS 3/ 11.1 LIOUID EFFLUENTS Dose LIMITING NDITION FOR OPERATION e
w 1
3.11.1.2 Th dose or dose comitment to a MEMBER OF THE PUI C from radioactive ma erials in liquid effluents released to UNRE
'RICTED AREAS shall be limite -
a.
During a ' calendar quarter to less than or qual to 3.0 mrems to g
g the total ody and to less than or equal t 10 mrems to any q
organ, and l
b.
During any ca ndar year to less than r equal to 6 mrems to the l
total body and o less than or equal o 20 mrems to any organ.
4 s
APPLICABILITY: At all times.
HH ACTION:
H a.
With the calculated dose f om the release of radioactive materials in liquid effl ts exceeding any of the above limits, prepare and submit to t e mission within 30 days, pursuant to Specification 6.9.2, Speci 1 ' Report that identifies the cause(s) for exceedi the li t(s) and defines the corrective r
w 1
actions that have en taken to reduce the releases and the proposed correcti actions to b taken to assure that subsequent releases will b in compliance wi the above limits.
-w b.
The provisio of Specifications 3.0.
and 3.0.4 are not 1
applicable.
3 w,
1 SURVEILLANCE VIREMENTS 4.11.1.2 nthly cumulative dose contributions from liqui effluents for m
the curre t calendar quarter and the current calendar year all be determi d in accordance with the methodology and parameters n the ODCM at least ce per 60 days.
4 d
l l
CALVERT CLIFFS - UNIT 2 3/4 11-5 Amendment No. 149
4.11 RADI0 ACTIVE EFFLUENTS 3/ 11.1 LIOUID EFFLUENTS Liaufd Radwaste Treatment System LIMITING NDITION FOR OPERATION 3
1 3.11.1.3 Th Liquid Radwaste Treatment System shall be use to reduce.the radioactive'ma erials in liquid wastes prior to their disc rge when the calculated dose due to the liquid effluent to UNRESTRI AREAS exceeds 0.36 mrem to the otal body or 1.20 mrem to any organ i a 92 day period.
M q
APPLICABILITY: At a times.
ACTION:
a.
With radioactive liquid waste bein discharged without treatment and in excess of e above limits prepare and submit to the Commission within days pursu t to Specification 6.9.2 a H
Special Report that cludes t following infonnation:
bd 1.
Explanation of why iqu radwaste was being discharged bd without treatment, i e ification of any inoperable equipment or subsyst
, and the reason for the inoperability, w
2.
Action (s) taken restor the inoperable equipment to 1
OPERABLE statu, and 3.
Summary des iption of action ) taken to prevent a recurrence
.e., w A
b.
The provisi s of Specifications 3.0, and 3.0.4 are not applicabl s
M
-5E SURVEILLANCE EQUIREMENTS O
4.11.1.3 onthly doses due to liquid releases to UNRESTRI ED AREAS shall be cale ated at least once per 60 days in accordance with t; methodology and p ameters in the ODCH.
l l
/
CALVERT CLIFFS - UNIT 2 3/4 11-6 Amendment No. 149
/4.11 RADI0 ACTIVE EFFLUENTS l
3/ 11.2 G_ASEOUS EFFLUENTS Dose Rate l
l LIMITING NDITION FOR OPERATION e
m 1
3.11.2.1 Th dose rate due to radioactive materials releas in gaseous effluents fro the site to areas at and beyond the SITE 80 DARY (see Figure 5.1-1) s 11 be limited to the following:
l j
a.
For nobi gases: Less than or equal to 500 rems /yr to the total
' g body and ss than or equal to 3000 mrems/
to the skin, and b.
For iodine-1 and for all radionuclide in particulate form with half lives gr ter than a days:
Less an or equal to 1500
,i mrems/yr to an organ.
APPLICABILITY: At all times.
H l
pq ACTION:
HH a.
With the dose rate (s) ex ing the above limits, without delay restore the release rate within the above limit (s).
b.
The provisions of Spec'ficat ns 3.0.3 and 3.0.4 are not applicable.
s SURVEILLANCE REQUIREMENT 4.11.2.1.1 The dose te due to noble gases in seous effluents shall be determined to be wi in the above limits in accorc ce with the methodology i
and parameters in e ODCH.
"y' 4.11.2.1.2 The ose rate due to iodine-131 and all ra ionuclides in a
particulate f with half lives greater than 8 days in aseous effluents shall be det ined to be within the above limits in acco dance with the methodology and parameters in the ODCH by obtaining repres tative samples y
and perfo ing analyses in accordance with the sampling and nalysis program ecified in Table 4.11-2.
i g
I l
CALVERT CLIFFS - UNIT 2 3/4 11-7 Amendment No. 149
DELETE THIS PAGE g
TABLE 4.11-2 r-RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM h
LOWER IT OF G
PLING MINIMUM ANALYSIS DET ON (LLD)*
g GASEOUS RELEASE TYPE FR ENCY FREQUENCY TYPE OF ACTIVITY ANALYSIS (pci/ml)
Q r9 Tank Each Tan Each Tank 1x10" e
\\' n Each Batch E
Batch
- 1x10" t
e ns ny Grab Sample C.
Main Vent M
Principa ama Emittersh Grab Sample Mc (Gase Emissions Only) c
{
Continuous M
V 1x10-*
a d
Continuous I-1x10-22 y
Charcoal Samp d
lPa 1x10*
Continuous Part ate i 0the mple M
Pfr Gross Alpha 1x10-"
d Continuous c
e Sample k
Q Pfr d
ontinuous Sr-89, Sr-90 1x10-11 c
e g
Sample d
Noble Gas Noble Gases 2
Continuous 1x10 P
Monitor Gross Beta or Gamma D.
Inci ated Olla P
P 5x10-7 Each Batch' Each Batch' Principal Gama Emitters
\\
i
\\
/4.11 RADIOACTIVE EFFLUENTS l
TABLE 4.11-2 (Continued) 1 TABLE NOTATION a
The L is defined, for purposes of these specificatio, as the 1
smalle concentration of radioactive material in a s pie that will yield a t count, above system background, that wil be detected with 95%
obability with only 5% probability of f sely concluding l
that a blan observation represents a "real" sign For a particu r measurement system, which may nelude radiochemical q
separation:
LLD =
E V 2.
x 10' Y exp (-
t) i Where:
H Hy LLD is the "a priori" ower 1. it of detection as defined above, as microcuries per unit as or volume, WW "M
s, is the standard deviat of the background counting rate or of the counting rate of b nk, sample as appropriate, as counts per minute -
r 5
E is the counting ficiency, a counts per disintegration, V is the sample ize in units of m s or volume,
?
w 2.22 x 10' is he number of disintegr ions per minute per 1
microcurie, Y is the ractional radiochemical yield, en applica'le, b
M i
r S
A is e radioactive decay constant for the articular 1
radi uclide, and O
A for )lant effluents is the elapsed time betwe n sample 11ect on or end of the sample collection period, and time of counting.
Typical values of E, V, Y, and At should be used in t l
calculation.
It should be recognized that the LLD is defined as an a prior (before the fact) limit representing the capabilit system and not as an a posteriori (after the fact)y of a measur ment limit for a s
particular measurement.
l CALVERT CLIFFS - UNIT 2 3/4 11-9 Amendment No. 149 l.
l l
l
- 4.11 RADI0 ACTIVE EFFLUENTS
\\
TABLE 4.11-2 (Continued) l TABLE NOTATION 1
b
,3 The p ' ncipal ganna emitters for which the LLD specific ion applies 1
exclus ely are the following radionuclides: Kr-87
-88, Xe-133, Xe-133m, e-135, and Xe-138 for gaseous emissions an Mn-54 Fe-59, Co-58, Co 0, Zn-65, Mo-99, Cs-134. Cs-137. Ce-141 nd Ce-144 for particulat emissions. This list does not mean t t only these nuclides are to be considered. Other gamma pea that are identifiable, ogether with those of the above uclides, shall also q
be analyzed an reported in the Semiannual R toactive Effluent Release Report p suant to Specification 6.
1.8.
C Sampling and analy 's shall also be perf ed following shutdown, STARTUP, or a THERMA POWER change exce ding 15 percent of RATED THERMAL POWER within e hour unless
) analysis shows that the DOSE EQUIVALENT I-131 concen ration in th primary coolant has not H
increased more than a fa tor of 5, nd (2) the noble gas activity Hy monitor shows that efflue activ' y has not increased by more than a factor of 5.
hd d
The ratio of the sample flow te to the sampled stream flow rate M
shall be known for the time er'od covered by each dose or dose rate calculation made in accor nce w th Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.
3 8
Samples shall be chan d at least on per 7 days and analyses shall be completed within hours after ch ging, or after removal from sampler. When sam e collection time i less than seven days, the
?
s corresponding LLD may be increased by a ro]ortional factor. This 1
requirement doe not apply if (1) analysis slows that the DOSE EQUIVALENT I-1 concentration in the prima coolant has not s
increased mor than a factor of 5, and (2) t noble gas monitor H
shows that fluent activity has not increase ore than a factor of 5
5 f
Waste s Decay Tank samples shall be collected an analyzed for O
oxyge once per week on the in-service tank and fol wing tank W
iso tion. Waste Gas Surge Tank samples shall be co ected and an yzed daily during power escalation from HODE 6 thr gh MODE 3, d once per week at all other times.
9 Collect sample and analyze daily for total Curie content p l
Specification 3.11.2.6 when the Reactor Coolant System spec 'ic l
activity of Xe-133 is greater than 150 pCi/ml.
/
I CALVERT CLIFFS - UNIT 2 3/4 11-10 Amendment No. 149
4.11 RADI0 ACTIVE EFFLUENTS TABLE 4.11-2 (Continued)
TABLE NOTATION h
-3 Incin ated oil may be discharged via points other tha he main vent 1
(e.g.,
uxiliary Boiler). Releases shall be accounte for based on l
pre-rele e grab sample data.
I Samples fo incinerated oil releases shall be col eted from and j
representati of filtered oil in liquid form.
l
<gs uD HH bH
-H l
M s
1 s-N**
,, 5 6
O l
I l
l l
e CALVERT CLIFFS - UNI 2 3/4 11-11 Amendment No. 149 1
l 4.11 RADI0 ACTIVE EFFLUENTS 3/ 11.2 GASEOUS EFFLUENTS l
Dose - Noble Gases l
LIMITING NDITION FOR OPERATION e
m 1
3.11.2.2 Th air dose due to noble gases released in gaseo effluents to l
l areas at and b ond the SITE B0UNDARY (see Figure 5.1-1) s 11 be limited to the followin -
a.
During a calendar quarter:
Less than or ual to 10 mrads for g
g gamma rad tion and less than or equal to mrads for beta q
radiation a d, b.
During any ca ndar year: Less than o equal to 20 mrads for gamma radiation and less than or equ to 40 mrads for beta radiation.
l APPLICABILITY: At all times.
l H l H ACTION:
H a.
With the calculated air from radioactive noble gases in gaseous effluents exceedi any of the above limits, prepare and submit to the Comissio wi in 30 days, pursuant to tie li. t(port that identifies thes) and defines the cor aeci Re i
Specification 6.9.2, cause(s) for exceedi l
-31 actions that have b en taken to educe the releases and the proposed correcti actions to b taken to assure that subsequent
,q releases will be in compliance wi the above limits.
5 b.
The provision of Specifications 3.0.
and 3.0.4 are not 1
applicable.
r 3
1 SURVEILLANCE R UIREMENTS 4.11.2.2 nthly cumulative dose contributions for the cu rent calendar quarter a current calendar year for noble gases shall be termined in accorda e with the methodology and parameters in the ODCH a least once per 60 ays.
i
}
CALVERT CLIFFS - UNIT 2 3/4 11-12 Amendment No. 149 l
l
I 4.11 RADI0 ACTIVE EFFLUENTS 3/ 11.2 GASEOUS EFFLUENTS Dose - Iodine-131 and Radionuclides in Particulate Fo LIMITING NDITION FOR OPERATION e
w 1
3.11.2.3 The dose to a MEMBER OF THE PUBLIC from todine-13 and all radionuclides particulate fann with half lives greater an 8 days in gaseous effluen released to areas at and beyond the SIT BOUNDARY (see l
Figure 5.1-1) sha 1 be limited to the following:
a.
During an calendar quarter:
Less than or _ qual to 15 mrems to l
q any organ a d.
l b.
During any ca ndar year: Less than o equal to 30 mrems to any organ.
c.
Less than 0.1% of he limits of 3.1.2.3(a) and (b) as a result of burning ontamin ted 011.
bd APPLICABILITY: At all times.
bd I
ACTION:
H a.
With the calculated do e fro the release of iodine-131 and radionuclides in part culate nn with half lives greater than 8
-w1 days, in gaseous ef.uents exce ing any of the above limits, prepare and submi to the Commis on within 30 days, pursuant to Specification 6.
2, a Special Rep t that identifies the cause(s) for e eeding the limit an defines the corrective w
actions that ve been taken to reduc the releases and the 1
proposed cor ective actions to be take to assure that subsequent releases w 1 be in compliance with the bove limits.
s H
b.
The pro sions of Specifications 3.0.3 and
.0.4 are not applic le.
-$1m SURVEIL CE REQUIREMENTS 4.11.
3 Monthly cumulative dose contributions for the current lendar l
quar er and current calendar year for iodine-131 and radionuclide in j
pa iculate form with half lives greater than 8 days shall be dete ined in cordance with the methodology and parameters in the ODCM at least ce j
er 60 days.
s t
CALVERT CLIFFS - UNIT 2 3/4 11-13 Amendment No. 149
4.11 RADI0 ACTIVE EFFLUENTS 3/ 11.2 GASEOUS EFFLUENTS l
l GASE0US RADWASTE TREATHENT SYSTEM l
LIMITING NDITION FOR OPERATION
-s 1
3.11.2.4 Th GASE0US RADWASTE TiiEATHENT SYSTEM and the VE LATION EXNAUST TREATMENT SYS shall be used to reduce radioactive mater is in gaseous waste prior to eir discharge when the gaseous effluent ir doses due to gaseous effluent eleases, to areas at and beyond the S E BOUNDARY (see Figure 5.1-1) exce s 1.20 mrad for gama radiation a 2.4 mrad for beta
<g radiation in a 92 d period. The VENTILATION EXHAU TREATMENT SYSTEM q
shall be used to redu e radioactive materials in g eous waste prior to their discharge when t calculated doses due to seous effluent releases, to areas at and beyond e SITE BOUNDARY (see Fi ure 5.1-1) exceeds 1.8 mrem to any organ in 92 day period.
APPLICABILITY: At all time H
ACTION:
bM a.
With gaseous waste bein di harged without treatment and in bd excess of the above limi prepare and submit to the Comission within 30 days, pursuant Specification 6.9.2, a Special Report that includes the follo ng information:
-8 1.
Explanation of w gaseou radwaste was being discharged 1
without treatm t, identifi tion of any inoperable equipment or bsystems, and 'he reason for the
,q inoperabili
?
8 2.
Action (s) taken to restore the i perable equipment to 1
OPERABL status, and 3.
Sum y description of action (s) take to prevent a M
rec rence.
e 8
1 b.
The ovisions of Specifications 3.0.3 and 3.
4 are not ap icable.
m SURVE LANCE REQUIREMENTS 4.
.2.4 Monthly doses due to gaseous releases shall be calculate at ast once per 60 days in accordance with the methodology and parame ers in l
he ODCM.
l J
l CALVERT CLIFFS - UNIT 2 3/4 11-14 Amendment No. 149
3/4.11 RADI0 ACTIVE EFFLUENTS p/g,ff, f
(//K7d GASEOUS EFFLUENTS Explosive Gas Mixture (Hydrogen rich systems not desi withstand a hydrogen explosion)gned to LIMITING CONDITION FOR OPERATION I
- gy j j
'[ bed[./M The concentration of oxygen in the Waste Gas Holdup System shall 1mited to less than or equal to 4% by volume.
APPLICABILITY: At all times.
ACTION:
With the concentration of oxygen in a waste gas decay tank a.
greater than 4% by volume imediately suspend all additions of waste gases to that tank and reduce the concentration of oxygen to less than or equal to 4% by volume without delay.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS ds b
n 1
11 Rmus wa Insar "411.1.1
I CALVERT CLIFFS - UNIT 2 3/4 11-15 Amendment No. 149
l l
l 1
l 1
1 INSERT "4.11.1.1" l
4.11.1.1
- Ihe concentration of oxygen in the Waste Gas Holdup System shall be detennined to be 1
t 1
within the above limit by collectmg and analyzing a sample from the Waste Gas Decay Tank once per week i
I on the in-service tank and following tank isolation. Waste Gas Surge Tank samples shall be collected and analyzed daily during power escalation from MODE 6 through MODE 3, and once per week at all other times.
4 l
l l
1 l
{
i d
r
i 3/4.11 _RADI0 ACTIVE EFFLUENTS 3/4.11h GASEOUS EFFLUENTS 1
}
Gas Storace Tanks j
LIMITING CONDITION FOR OPERATION j 2" 3.1
.6 The quantity of radioactivity contained in each gas storage tank shall limited to less than or equal to 58,500 curies' noble gases (considered as Xe-133).
APPLICABILITY: At all times.
ACTION:
With the quantity of radioactive material in any gas storage tank a.
exceeding the above limit, immediately suspend all additions of radioactive material to that tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the Ifmit.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not j
applicable.
I SURVEILLANCE REQUIREMENTS 4
- 1. 2 -
4.IIh The quantity of radioactive material contained in the in-service 3
i gas storage tank shall be detemined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the Reactor Coolant System specific activity of 4
Xe-133 is greater than 15') Ci/ml.
t CALVERT CLIFFS - UNIT 2 3/4 11-16 Amendment No. 149
/4.11 RADI0 ACTIVE EFFLUENTS i
3
.11.3 SOLID RADIOACTIVE WASTE LIMITI CONDITION FOR OPERATION 3.11.3 T solid radwaste program shall be used in accordance ith a 3
PROCESS C0 R0L PROGRAM to process wet radioactive wastes to eet shipping 1
and burial g und requirements.
i APPLICABILITY:
t all times.
ACTION:
4 a.
With the p visions of the PROCESS CONTR PROGRAM not satisfied, N
suspend ship ents of defectively proces d or defectively packaged soli radioactive wastes fro the site.
b.
The provision o Specifications 3.0 and 3.0.4 are not applicable.
HH H
SURVEILLANCE REQUIREMENTS 4.11.3 The PROCESS CONTROL PROG s 11. be "used to verify the SOLIDIFICATION of at.least one presen ative test specimen from at least l
every tenth batch of each typ of wet ra ioactive waste (e.g., filter
-w1 sludges, spent resins, evapo tor bottoms, boric acid solutions, and sodium sulfate solutions).
y H:
s
, k
- f
-5, m
,M s
CALVERT CLIFFS - UNIT 2 3/4 11-17 Amendment No. 149 i
/4.11 RADI0 ACTIVE EFFLUENTS 3
.11.4 TOTAL DOSE LIMIT G CONDITION FOR OPERATION 3.11.4 T annual (calendar year) dose or dose comitment to ny MEMBER OF
-5 THE PUBLIC ue to releases of radioactivity and to radiation rom uranium fuel cycle s urces shall be limited to less than or equal 25 mrems to the total bod or any organ, except the thyroid, which sh 1 be limited to less than or e al to 75 mrems.
dPPLICABILITY: A all times.
<gq ACTION:
a.
With the cal lated doses from the r ease of radioactive materials in l' quid or gaseous effl nts exceeding twice the limits of Speci ication 3.11.1.2.
3.11.1.2.b 3.11.2.2.a.
3.11.2.2.b. 3.11.
3.a. or 3.11.
3.b, calculations shall be made including direct r diation cont ibutions from the reactor units H
and outside storage anks to termine whether the above limits H
of Specification 3.1 4 have een exceeded.
If such is the case, prepare and submit to e
mission within 30 days, pursuant to Specification 6.9.2, a cial Report that defines the corrective action to be taken to r ce subsequent releases to prevent recurrence of exceedin th above limits and includes the i
schedule for achievi conf
'ance with the above limits. This Special Report, as fined i 10 CFR 20.405c, shall include an
-w1 analysis that est.ates the ra iation exposure (dose) to a MEMBER OF THE PUBLIC fr uranium fuel ycle sources, including all rq effluent pathw s and direct rad tion, for the calendar year that includes he release (s) cover by this report.
It shall also descri levels of radiation a concentrations of 1
radioactiv material involved, and th cause of the exposure levels or concentrations.
If the esti ted dose (s) exceeds the s
above 1 its, and if the release conditi n resulting in violation M
of 40 R Part 190 has not already been c rected, the Special Repo shall include a request for a varia e in accordance with
-*1 th provisions of 40 CFR Part 190. Submitta of the report is c sidered a timely request, and a variance i granted until O
aff action on the request is complete.
b The provisions of Specifications 3.0.3 and 3.0.4 e not applicable.
/
CALVERT CLIFFS - UNIT 2 3/4 11-18 Amendment No. 149
4.11 RADI0 ACTIVE EFFLUENTS SU EILLANCE REQUIREMENTS 4.11.4 Cumulative dose contributions from liquid and gaseous eff ents shall b determined in accordance with Specifications 4.11.1.2, 4.
.2.2, and 4.11.
3, and in accordance with the methodology and paramet s in the CDCM.
-31 4.11.4.2 Cu lative dose contributions from direct radiatio from the reactor units d outside storage tanks shall be detennine in accordance with the method ogy and parameters in the ODCH. This re frement is applicable only u der conditions set forth in Specifica on 3.11.4.a.
<4N cn HH M+
r 5
M s
L 3
-5, m
m
/
CALVERT CLIFFS - UNIT 2 3/4 11-19 Amendment No. 149
4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/ 12.1 MONITORING PROGRAM l
l LIMITI CONDITION FOR OPERATION I
3.12.1 Th radiological environmental monitoring program shall e
-5 conducted a specified in Table 3.12-1.
b APPLICABILITY: At'all times.
ACTION:
M a.
With the diological environmental monitor ng. program not being l
conducted a specified in Table 3.12-1, p pare and submit to the q
Commission, the Annual Radiological vironmental Operating Report requir by Specification 6.9.1
, a description of the reasons for not conducting the progr as required and the plans for preventing a ecurrence.
b.
With the level of dioactivity the result of plant effluents H
in an environmental mple at specified location exceeding the Hy reporting levels of T le 3.1 2, prepare and submit to the Commission within 30 da s af er receiving the sample analysis, l bd pursuant to Specificatio
.9.2, a Special Report that identifies the cause(s) for exceedin the limit (s) and defines the l M corrective actions to b ta en,to reduce radioactive effluents so i
s that the potential ann 1 do
'to a MEMBER OF THE PUBLIC is l
less than the calend year 1 its of Specifications 3.11.1.2, 3.11.2.2, and 3.11.
3.
When m re than one of the radionuclides l
in Table 3.12-2 ar. detected in e sample this report shall be submitted if:
?
w conce ration (1) + concen ation (2)
+..> 1.0 1
repor ing level (1) reporting level (2)
When radi nuclides other than those in T le 3.12-2 are detected H
and are he result of plant effluents.
report shall be submit ed if the potential annual dose,thi
-5 to MEMBER OF THE PUBLIC l 1 is e al to or greater than the calendar yea limits of l
Spe ifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.
This report is i O n
required if the measured level of radioacti ty was not the esult of plant effluents; however, in such an ey nt, the condition shall be reported and described in the A ual Radiological Environmental Operating Report.
l
/
The methodology and parameters used to estimate the potential ann 1 dose to a MEMBER OF THE PUBLIC shall be indicated in this report.
CALVERT CLIFFS - UNIT 2 3/4 12-1 Amendment No. 149
l l
4.12 RADIOLOGICAL ENVIRONMENTAL HONITORING LI TING CONDITION FOR OPERATION (Continued)
With fresh leafy vegetable samples unavailable from one more of the sample locations required by Table 3.12-1, ident y locations for obtaining replacement samples and add tt to the idiological environmental monitoring program within 0 days.
-5 l
T specific locations from which samples were unav lable may th be deleted from the monitoring program. Pur ant to Spec fication 6.9.1.7, identify the cause of the navailability of s les and identify the new location (s) fo obtaining the i
replac ent samples in the next Annual Radiol ical Environmental
' <g Operatin Report.
q d.
The provis ns of Specifications 3.0.3 a 3.0.4 are not applicable.
uD SURVEILLANCE REQUIREMENTS t H bd 4.12.1 The radiological environ ntal onitoring samples shall be Hy collected pursuant to Table 3.12-fr m the specific locations given in the table and figure (s) in the ODCH, an shall be analyzed pursuant to the l
r H
requirements of Table 3.12-1 and t e etection capabilities required by i
l Table 4.12-1.
-w e
l W l :
s L
s e
8, m
l
}
CALVERT CLIFFS - UNIT 2 3/4 12-2 Amendment No. 149 l
~
DELETE THIS PAGE 0
TABLE 3.12-1
~
c RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM P
.E EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND QUENCY
?
AND/0R SAMPLE PLES AND SAMPLE LOCATIONS
- COLLECTION FREQUENCY 0F LYSIS So b
1.
DIRECT RADIATION 23 rout e monitoring stations At least Quarterly.
Ga dose at least E
E (DRI-DR23 ither with two or arterly.
9 Z
more dosimet or with one m
instrument for suring and E
recording dose rat continuously, d
placed as follows:
lx an inner ring of stati one in each meteorologica g>
t' sector in the general area the SITE BOUNDARY (DR1-DR9);
E i;
5 L,
an outer ring of statio o
one in each meteorol cal ~
5 sector in the 6-8-km E
range from the te (DR10-DR18);
the r ning stations (DR19-p DR2 to be placed in special m
erest areas such as h
population centers, nearby residences, schools, and in m
A 1 area to serve as a control g:
station.
e
- p TABLE 3.12-1 (Continued)
M L
E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM N
P E
7 EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND QUENCY
?
AND/0R SAMPLE PLES AND SAMPLE LOCATIONS
- COLLECTION FREQUENCY OF LYSIS S
o 2.
AIRBORNE O
E 9
Z Radioiodine and Samples fr 5 locations Continuous sampler Radiciodine Canister N
Particulates (Al-AS):
operation with samp I-131 analysis weekly.
E collection week 1 or 5
3 samples (Al-from more frequent if Particulate Sampler:
E close to the 3 S required b ust Gross beta E
BOUNDA'tY locations, loading radioactivity analysis a"j different sectors of t following filter.
R highest calculated change *; dGama isotopic annual average ground-analysis of composite E
M level D/Q.
(bylocation)
E i
quarterly.
E!
I sample (A4) fr the 5
vicinity of a munity E
having the ghest calcula annual aver ground-level D/.
ifg 1 sample (AS) from a control location, as for a
5 example 15-30 km distant A
and in the least prevalent wind 2
direction.
\\
DELETE THIS PAGE np TABLE 3.12-1 (Continued)
U RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM P
5 EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND QUENCY U
AND/0R SAMPLE S
LES AND SAMPLE LOCATIONS' COLLECTION FREQUENCY OF LYSIS 8o 3.
WATERBORNE S
9 2
d Z
a.
Surface 1 sample at take area (Wal) Composite sample over ama isotopic analysis 1 sample at dis arge area month period".
monthly. Composite for g
to (Wa2) tritium analysis g
quarterly.
o E
b.
Sediment from 1 sample from downstream a a Semiannual Gama isotopic analysis g
d shoreline with existing or potential semiannually.
g recreational value (Wb1).
E
=
5 a
a
=5 m
I i
2~
e
~
DELETE THIS PAGE O
TABLE 3.12-1 (Continued) 2 RADIOLOGICAL ENVIRONMENTAL riCMITORING PROGRAM P
E A
EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND ENCY
?
AND/0R SAMPLE S
ES AND SAMPLE LOCATIONS' COLLECTION FREQUENCY OF YSIS S
o
[
4.
INGESTION O9 2
A a.
Fish and 3 samples of mercially Sample in season, or aisptopic m
Invertebrates and/or recreati lly semiannually if they analysis on edible E
important species fish are not seasonal.
portions.
d species and 1 inverte ate E
species) in vicinity of ant E
discharge area (Ial-Ia3).
R 3 samples of same species in areas not influenced by plant E
y discharge (Ia4-Ia6).
y cn o
d b.
Food Products Samples of 3 different nds Monthly dur growing Gama isotopic and of broad leaf vegeta on grown season.
I-131 analysis.
m near the SITE BOU RY at 2 different lo ions of highest pre ' ted annual average undlevel D/Q g
(Ibl-d g
Monthly during growing Gama topic and sample of each of the season.
I-131 ana sis.
a 5
similar broad leaf vegetation 5
grown 15-30 km distant in the least prevalent wind direction 2
(Ib7-Ib9).
3
\\
l
4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING TABLE 3.12-1 (Continued)
TABLE NOTATION The de in parenthesis, e.g., DR1, A1, defines generic ample "T'
locat ns in this specification that can be used to id tify the
m4=
specif locations in the map (s) and table in the CD Specific paramete of distance and direction sector from th central point between t two containment buildings and addition description where perti ent, is provided for each sample loc ion in Table 3.12-1, and in a table and figure (s) in t ODCH. Refer to (d
NUREG-0133 " eparation of Radiological Effl nt Technical N
Specifications or Nuclear Power Plants, Oct er 1978", and to l
Radiological Ass sment Branch Technical P ition, Revision 1, i,
November 1979. D tations are pennitted om the required sampling schedule if specime s are unobtainable e to circumstances such as hazardous conditions, seasonal unavail ility, and malfunction of automatic sampling eq pment.
If sp imens are unobtainable due to sampling equipment mal ction, eff t shall be made to complete corrective action prior the en of the next sampling period. All H
deviations from the sampi sch ule shall be documented in the Annual Radiological Environ nt Operating Report pursuant to Specification 6.9.1.7.
It i ecognized that, at times, it may not y
be possible or practicable t ontinue.to obtain samples of the media of choice at the most desir d 1 ation or time.
In these instances suitable alternative medi and 1 atici s may be chosen for the 1-5 particular pathway in q stion an ppropriate substitutions made within 30 days in the diological vironmental monitoring program.
Pursuant to Specific ion 6.9.1.7, i ntify the cause of the r
H unavailability of s ples for that pat 'ay and identify the new location (s) for o aining samples in th next Annual Radiological "r'
Environmental Op ating Report and also i clude in the report a Jm revised figure and table for the ODCH r lecting the new 4
location (s).
M r
5 m
4 CALVERT CLIFFS - UNIT 2 3/4 12-7 Amendment No. 149
4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING TABLE 3.12-1 (Continued) l TABLE NOTATION b
One more instruments, such as a pressurized ion chamb
, for i
r 5
measu ng and recording dose rate continuously may be ed in place 1
of, or addition to, integrating dosimeters. For t purposes of this tab
, a thermoluminescent dosimeter (TLD) is c sidered to be one phosp r; two or more phosphors in a packet ar considered as two or more dos eters.
Film badges shall not be use as dosimeters for measuring di et radiation. The frequency of a ysis or readout for TLD Systems w 1 depend upon the characteristi of the specific q
system used and hould be selected to obtain ptimum dose information with minimal fad g.
Due to the geographic limitations, 9 sectors are monitored arou d the Calvert Cliffs Nu ear Power Plant.
C Airborne particulate ample filters sha 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 mpling to allow for radon and thoron daughter decay.
f gross bet activity in air particulate H
samples is greater than t n times e yearly mean of control samples, HH gamma isotopic analysis sh 1 be rfomed on the individual samples.
hd d
Gamma isotopic analysis means e identification and quantification of gama-emitting radionuclid that may be attributable to the i
effluents from the facility A composite sample is on in which he quantity (aliquot) of liquid 3
1 sampled is proportional o the quant ~ty of flowing liquid and in which the method of s pling employed esults in a specimen that is representative of th liquid flow.
In his program, composite sample aliquots shall be lected at time inte vals that are very short
?
s (e.g., hourly) re tive to the compositin period (e.g., monthly) in 1
order to assure taining a representative ample.
s b,
r w
m CALVERT CLIFFS - UNIT 2 3/4 12-8 Amendment No. 149
DELETE THIS PAGE g
TABLE 3.12-2 r-
,a h
RE TING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES M
(
REPORTING LEVELS c
E a
s MDPRODUCTS E
WATER AIR NE PARTICULATE FISH & INVERTEBRATES MILK g
ANALYSIS (pci/l)
(pC1/kg, wet)
(pC1/l) / (pC1/kg, wet) y U
H-3 20,000'
[
ro
==
Mn-54 1,000 30,000 o
Fe-59 400 10,000 l
Co-58 1,000 30,00 f
Co-60 300
, 00 l
~
~
Zn-65 300 20,000 y
Zr-Nb-95 400 I-131 2
0.9 3
100 Cs-134 30 10 1,000 60 1,000 Eg Cs-137 50 20 2,000 70 2,000
&g Ba-La-140 200 300 e
?'
For drinki water samples. This is a 40 CFR Part 141 value.
If no drinking water pathway ex s,
a value 30,000 pCi/l may be used.
I
g TABLE 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS.b g
LOWER LIMIT OF DETECTION (LLD)*
g a
E WATER AIRBORNE M ICULATE FISH & INVERTEBRATES MILK FOOD PRO S
SEDIMENT E
ANALYSIS (pci/1)
OR GASES (pWe')
(pC1/kg, wet)
(pC1/1)
(pci/, wet)
(pC1/kg. dry)
[
Gross Beta 4
0.01 g
Fe-59 30 2
5 E
g Co-58,60 15 13 g
i
-4 5
Zn-65 30 260 Zr-Nb-95 15 d
I-131 I
0.07 1
60 Cs-134 15 0.
130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 5#
If no dri ng water pathway exists, a value of 3000 pCf/1 may be used.
4.0 h
a 4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING TABLE 4.12-1 (Continued)
TABLE NOTATION This ist does not mean that only these nuclides are to b
-5 consi red. Other peaks that are identifiable, togethe' with those of the ove nuclides, shall also be analyzed and repo :ed in the Annual R 10 logical Environmental Operating Report p suant to Specificat on 6.9.1.7.
D g
Required det tion capabilities for themolumine ent dosimeters used g
for environmen al measurements shall be in acc dance with the q
recomendations f Regulatory Guide 4.13.
C The LLD is define for purposes of these ecifications, as the smallest concentrat n of radioactive ma rial in a sample that will yield a net count, a ve system backgro d, that will be detected with 95% probability w th only 55s prob ility of falsely concluding that a blank observatio represents "real" signal.
H For a particular measureme t syst
, which may include radiochemical separation:
4.66s E V 2.22 -
exp Mt)
-w1 Where:
LLD is the "A pr ri" lower limit detection as defined above, j
as picocuries p r unit mass or volu.
j m
1 s, is the st dard deviation of the ba ground counting rate or y
of the cou ing rate of a blank sample a appropriate, as counts per minut,
b E is t e counting efficiency, as counts per isintegration,
-5 Vi the sample size in units of mass or volum
.22 is the number of disintegrations per minute r picocurie, Y is the fractional radiochemical yield, when applic ble, 1 is the radioactive decay constant for the particular radionuclide, and s
CALVERT CLIFFS - UNIT 2 3/4 12-11 Amendment No. 149
/4.12 RADIOLOGICAL ENVIRONMENTAL HONITORING TABLE 4.12-1 (Continued)
TABLE NOTATION i
t for environmental samples is the elapsed time be een sample 5
c 11ection, or end of the sample collection period and time of co ting.
Typic values of E V, Y and At should be us in the calcul ion.
(g It should be cognized that the LLD is defin as an a priori y
(before the fa ) limit representing the cap 111ty of a measurement system and not a an a posteriori (after t fact) limit for a particular measur ent. Analyses shall b perfomed in such a manner 1
that the stated LL will be achieved u er routine conditions.
Occasionally backgro d fluctuations, avoidable small sample sizes, the presence of inter ring nuclides or other uncontrollable circumstances may rend these LLDs nachievable.
In such cases, the H
contributing factors sha 1 be ide ified and described in the Annual H
Radiological Environmenta Opera ng Report pursuant to Specification 6.9.1.7.
d LLD for drinking water sampl If no drinking water pathway exists, the LLD of gama isotopic al is.may~be used.
e s
1 b,
-s m
l CALVERT CLIFFS - UNIT 2 3/4 12-12 Amendment No. 149
4.13 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4. 2.2 LAND USE CENSUS LIMITIN CONDITION FOR OPERATION 3.12.2 A nd use census shall be conducted and shall identif within a
-5 distance of fan (5 miles) the location in each of the 9 mete ological 1
sector of th nearest milk animal, the nearest residence a the nearest garden; of grea er than 50 m (500 ft') producing broad lea vegetation.
(For elevated re ases as defined in Regulatory Guide 1.1
, Revision 1, July 1977, the la use census shall also identify with a distance of 5 km (3 miles) the ocations in each of the 9 meteorol ical sectors of all milk animals and all ardens of greater than 50 m pr ducing broad leaf q
vegetation).
APPLICABILITY: At all t es.
ACTION:
a.
With a land use cen s identifyi a location (s) that yields a H
calculated dose or do e comitm t greater than the values H
currently being calcul ed in pecification 4.11.2.3, identify the new location (s) in en t Annual Radiological Environmental Operating Report, pursuan o Specification 6.9.1.7.
b.
With a land use census i ent*fyi.ng a~ 1ocation(s) that yields a calculated dose or dos comi ent (via the same exposure pathway) 20 percent eater th at a location from which samples
-s1 are currently being btained in ccordance with Specification 3.12.1, add the ne location (s) t the radiological environmental monitoring progr within 30 days. Thesamplinglocation(s),
excluding the c trol station locati
, having the lowest
-w calculated do or dose comitment(s), via the same exposure 1
pathway, may e deleted from this monit ring program after October 31 f the year in which this lan use census was s
conducted Pursuant to Specification 6.9.
7, identify the new H
locatio s) in the next Annual Radiological nvironmental Operat figur (sf Report and also include in the rep
-S t a revised 1
and table for the ODCM reflecting th new location (s).
O c.
Th provisions of Specifications 3.0.3 and 3.0.4 re not plicable.
i Broad leaf vegetation sampling of at least three different ki ds of vegetation may be perfonned at the SITE BOUNDARY in each of tw l
different direction sectors with the highest predicted D/Qs in
'eu of the garden census. Specifications for broad leaf vegetation i
sampling in Table 3.12-1.4b shall be followed, including analysis control samples.
l CALVERT CLIFFS - UNIT 2 3/4 12-13 Amendment No. 139 l
i 4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING SUR ILLANCE REQUIREMENTS 4.12.2 The land census shall be conducted during the growing seas at least on e per 12 months using that information that will provide he best
- results, ch as by a door-to-door survey, aerial survey, or by onsulting local agri 1ture authorities. The results of the land use ce us shall be "T'
included in she Annual Radiological Environmental Operating port pursuant a
to Specificat n 6.9.1.7.
<MN r>2 H
H H
H
-w e
M s
1 s
i 5
- o l m i
/
CALVERT CLIFFS - UNIT 2 3/4 12-14 Amendment No. 149
4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/
2.3 INTERLABORATORY COMPARISON PROGRAM l
LIMITI CONDITION FOR OPERATION 3.12.3 An yses shal! be perfonned on all radioactive material, supplied r
3 as part of Interlaboratory Comparison Program that has been pproved by 1
the Commissio that correspond to samples required by Table
.12-1.
l APPLICABILITY:
t all times.
ACTION:
4 I
l a.
With analys not being performed as requi ed above, report the N
corrective a ions taken to prevent a re rrence to the Commission in he Annual Radiological E ironmental Operating Report pursuant o Specification 6.9.
7.
b.
The provisions of ecifications 3
.3 and 3.0.4 are not applicable.
l bd l HH l
SURVEILLANCE REQUIREMENTS i
4.12.3 The Interlaboratory Comp ison ogram shall be described in the 5
ODCH. A summary of the result obtained s part of the above required 1
Interlaboratory Comparison Pr ram shall b included in the Annual l
Radiological Environmental 0 erating Report ursuant to r
l Specification 6.9.1.7.
1 e
s l
s b,
-s l
l m i
4 CALVERT CLIFFS - UNIT 2 3/4 12-15 Amendment No. 149
3/4.3 INSTRUMENTATION sASES In the event more than four sensors in a Reactor Vessel Level channel are
- inoperable, repairs may only be possible during an extended COLD SHUTDOWN.
This is because the sensors are accessible only after the plant has been l
cooled down and drained, and the missile shield has been moved. If only one channel is inoperable, it should be restored to OPERABLE status in accordance with the schedule outlined in a Special Report. If both channels are ino^perable, the system shall be restored to OPERABLE status in the next refueling outage.
3/4.3.3.7 Fire Detection Instrumentation 0PERABILITY of the fire detection instrumentation ensures that ade warning capability is available for the prompt detection of fires.quate This capability is required in order to detect and locate fires in their early
(.
stages.
Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.
In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to~ provide detection capability until the inoperable instrumentation is restored to 0PERABILITY.
.3.3.9 Radioactive Gaseous Effluent Monitorina Instrumentation The ra ctive gaseous effluent instrumentation is provided to no or and r
5 control, a p11 cable, the releases of radioactive materials 1
effluents dur actual or potential releases of gaseous ef ents. The aseous alam/ trip setpo 1 for these instruments shall be cale ed and adjusted r
in accordance with '.
methodology and parameters in ODCM to ensure that the alarm / trip wil cur prior to exc_eeding e limits of 1.5 Specification 3.11.2.1.a ba on average annu
/Q. The OPERABILITY and use of this instrumentation is nsistent the requirements of 10 CFR 4
Part 50. Appendix A. General Dest ri a 60, 63, and 64.
N 3/4.3.3.10 Radioactive Liouid Ef ent itorina Instrumentation The radioactive li uid eff nt instrumentation provided to monitor and control, as applic!ble O
e releases of radioactiv iterials in liquid effluents during ac or potential releases of liqu' ffluents. The alam/ trip setpo s for these instruments shall be calcu ed and adjusted in accordanc th the methodology and parameters in the 0D q
ensure that the trip will occur prior to exceeding the limits of CFR Part
- 20. T PERABILITY and use of this instrumentation is consistent the ements of 10 CFR Part 50, Appendix A. General Design Criteria 60, rec
/
64.
l i
CALVERT CLIFFS - UNIT 2 B 3/4 3-3 Amendment No. 176 l
3/4.11 RADI0 ACTIVE EFFLUENTS l
kBASES 3
.11.1 LIOUID EFFLUENTS 3/4.
.1.1 Concentration This sp ification is provided to ensure that the concentration f radioact e materials released in liquid waste effluents to U ICTED AREAS will e less than the concentration levels specified i 10 CFR Part 0, Appendix B. Table II, Column 2.
This limi ion provides additional as rance that the levels of radioactive mater' is in bodies of water in UNR ICTED AREAS will result in exposures wi
- n (1) the Section II.A des n objectives of 10 CFR Part 50, Appe ix I to a MEMBER 0F THE PUBLIC and (2 the limits of 10 CFR 20.106(e) to e population.
The required detecti capabilities for radioactiv<
materials in liquid waste ' samples are tab ated in terms of the lower imits of detection l.
(LLLs). Detailed discu fon of the ;LLD, and at r detection limits can be found in HASL Procedures. anual. HASL-300, Cur
- e. L.A., " Limits for Qualitative Detection and antitative Dete nation - Application to Radiochemistry," Anal. Chem. 40, 586-93 (19F ), and Hartwell, J.K.,
h
" Detection Limits for Radioa lytical Coung ng Techniq)ues," Atlantic Richfield Hanford Company Repo ARH-SA-?J5 (June 1975.
Z 3/4.11.1.2 Dose w
~
This specification is provided to i lement the requirements of 10 CFR M
Part 50, Appendix /I, Sections II.
I
..A and IV.A. The Limiting Condition H
for Operation implements the gut s se'. forth in Appendix I,Section II.A.
The ACTION statements provide e requir operating flexibility and.at the p
same time implement the guide set forth Appendix I,Section IV.A.to r s 1
assure that the releases of adioactive mat rial in liquid effluents to UNRESTRICTED AREAS will be ept "as low as i reasonably achievable." The N
dose calculation methodol gy and parameters i the ODCM implement the
' g" requirements in Appendi:
I,Section III.A that nfonnance with the guides of Appendix I be show, ay calculational procedu based on models and I
data, such that the tual exposure of a MEMBER 0 THE PUBLIC through h
appropriate pathway is unlikely to be substantiall underestimated. The 1
equations speciff in the ODCM for calculating the ses due to the actual release rates of adioactive materials in liquid efflu ts are consistent O
with the metho ogy provided in Regulatory Guide 1.109, " Calculation of I"""
Annual Doses '
Man from Routine Releases of. Reactor Eff ents for the Purpose of aluation Compliance with 10 CFR Part 50, Appe ix I,"
Revision 1 October 1977 Regulatory Guide 1.113. "Estimati Aquatic Dispersi of Effluents from Accidental and Routine Reactor R eases for the Pu se of Implementing Appendix I," April 1977, and NUREG 133 "Prepa tion of Radiological Effluent Technical Specifications r Nuclear Power lants."
i l
)
CALVERT CLIFFS - UNIT 2 B 3/4 11-1 Amendment No. 149
~
i i
i I,
i d
S 3/4.11 RADI0 ACTIVE EFFLUENTS I
3
.11.1.3 Liouid Radwaste Treatment System The r uf rement that the appropriate portions of this system be ed, when specif
, provides assurance that the releases of radioactive aterials in liquid e
'luents will be kept "as low as is reasonably achiev le".
This specifica'. on implements the requirements of 10 CFR 50.36a, 10 CFR Part 0, Appendix A. General Design Criterion 60 an the design objective gi n in 10 CFR Part 50 Appendix I, Section II The specified limits govern the use of appropriate portions of the iquid Radwaste Treatment Syst were specified as a suitable fraction f the dose design objectives set f th in 10 CFR Part 50 Appendix I, etion II.A for liquid effluents. The do limits apply to the combined e luent of the plant (e.g.,twounits).
3/4.11.2 GASEOUS EFFL NTS i
3/4.11.2.1 Dose Rate h
This specification is provi to ensure at the dose at any time at and beyond the SITE B0UNDARY from aseous ef uents from all units on the site will be within the annual dose imits 10 CFR Part 20 to UNRESTRICTED g
AREAS. The annual dose limits a t
doses associated with the concentrations of 10 CFR Part 20, endix B. Table II, Column 1.
These limits provide reasonable assuranc hat radioactive material discharged in f
gaseous effluents will not resul in he ' exposure of a MEMBER 0F THE PUBLIC H'
in an UNRESTRICTED AREA, exceed g the limits specified in Appendix B, Table II of 10 CFR 20.106(b).
or MEMB S OF THE PUBLIC who may at times dr
- be within the SITE B0UNDARY, he occupan of that MEMBER OF THE PUBLIC t
will be sufficiently low t compensate for ny increase in the atmospheric Q
diffusion factor above th for the SITE B0 DARY.
1 The required detection apabilities for radioa ive materials in gaseous waste samples are tab ated in tems of the low limits of detection s.
(LLDs). Detailed d cussion of the LLD, and othe detection limits can be N
found in HASL Proc ures Manual, HASL-300, Currie,
.A., " Limits for T
Qualitative Dete ion and Quantitative Detemination Application to g
Radiochemistry, Anal. Chem. 40, 586-93 (1968), and H twell, J.K.,
"Detecti'on Li ts for Radioanalytical Counting Techniq
" Atlantic Richfield Ha ord Company Report ARH-SA-215 (June 1975).
3/4.11.2.
Dose - Noble Gases j
This s cification is provided to implement the requirements o 10 CFR Part
. Appendix I, Sections II.B. III.A and IV.A. The Limiti Condition for peration implements the guides set forth in Appendix I, Changed by NRC letter dated April 26, 1993 l
/
CALVERT CLIFFS - UNIT 2 8 3/4 11-2 s
- =... _.
l 1
b j
3/4.11 RADI0 ACTIVE EFFLUENTS i
BASES S tion II.B. The ACTION statements provide the required operating i
fle bility and at the same time implement the guides set forth in l
Appe fx I,Section IV.A to assure that the releases of radioacti i
materi 1 in gaseous effluents to UNRESTRICTED AREAS will be kep as low as reasona y achievable." The Surveillance Requirements-impleme the requi ts in Appendix I,Section III.A that conformance wi a the guides of Appendi I be shown by calculational procedures based on als and data i
such that t actual exposure of a MEMBER 0F THE PUBLIC th ugh appropriate j
pathways is u ikely to be substantially underestimated.
he dose calculation me odology and parameters established in t 00CM for calculating the
~ses due to the actual release rates radioactive noble gases in gaseous fluents are consistent with the hodology provided in
{i "r' Rep.latory Guide 1. 09, " Calculation of Annual Dose to Man from Routine Releases of Reactor fluents for the Purpose of aluating Compliance with 10 CFR Part 50, Appen x I." Revision 1, October 977 and Regulatory Guide 1.111. " Methods Estimating Atmospheri Transport and Dispersion i
of Gaseous Effluents in utine Releases from ight-Water-Cooled Reactors,"
i Revision 1. July 1977, an UREG-0133 "Prepa tion of Radiological Effluent Technical. Specifications fo Nuclear Power ants".
j The ODCM equations provided fo detemi ng the air doses at and beyond the jZ SITE B0UNDARY are based upon th histo cal annual average atmospheric
=
conditions.
3/4.11.2.3 Dose - Iodine-131 and fonuclides in Particulate Fom i
H This specification is provided impi nt the requirements of 10 CFR Part 50, Appendix I, Sections
.C, III. and IV.A. The Limiting L
-'1 Conditions for Operation are he guides s forth in Appendix I, i
Section II.C. The ACTION s tements provi the required operating iQ flexibility and at the s time implement t guides set forth in Appendix I,Section IV.
o assure that the r eases of radioactive
-: '[
materials in gaseous e uents to UNRESTRICTED EAS will be kept "as low as is reasonably acht able." The ODCM calculat nal methods specified in s.
!y the Surveillance Re frements implement the requi nts in Appendix I,Section III.A that onfomance with the guides of A endix I be shown by l
,,1.s.
calculational prc edures based on models and data, s h that the actual j
exposure of a M BER OF THE PUBLIC through appropriate athways is unlikely to be substant ally underestimated. The 00CM calculati al methodology and 4
i parameters f calculating the doses due to the actual re ase rates of the subject mat ials are consistent with the methodology prov ed in Regulator ~
utde 1.109, " Calculation of Annual Doses to Man rom Routine Releases f Reactor Effluents for the Purpose of Evaluating pliance with 10 CFR art 50, Appendix I," Revision 1, October 1977. Regulat Guide
.111. " Methods for Estimating Atmospheric Transport and persion j
CALVERT CLIFFS - UNIT 2 8 3/4 11-3 Amendment No. 149 i
i
,,y y
..-..-_y.
-_...,,m,,_
1 1
3/4.11 RADI0 ACTIVE EFFLUENTS BASES Gaseous Effluents in Routine Releases from Light-Water-cooled Reactor Re ion 1. July 1977, and NUREG-0133, " Preparation of Radiological Efflu t Technical Specifications for Nuclear Power Plants". These I
equatio also provide for determining the actual doses based up the historical nual average atmospheric conditions.
The release ate specificatio for iodine-131 and radionuclides in aarticul fonn with l"T' half lives grea than 8 days are dependent upon t1e exi ng radionuclide
d=
pathways to man, the areas at and beyond the SITE B DARY.
The t
pathways that were e ined in the development of t e calculations were:
rH
- 1) individual inhalati of airborne radionuclide, 2) deposition of i
i~
radionuclides onto green afy vegetation with bsequent consumption by
T man, 3) deposition onto gra areas where animals and meat producing
'==h==
animals graze with consumption f the mil nd meat by man, and
- 4) deposition on the ground with bse nt exposure of man.
5 l"
3/4.11.2.4 GASEOUS RADWASTE TREA N
YSTEM i *f T '
The requirement that the app riate portio of these systems be used,
)
when specified, provides r sonable assurance at the releases of l
radioactive materials i aseous effluents will kept "as low as is reasonably achievabl 1
This specificat' implements the requirements of 10 CF 0.36a, 10 CFR l
Part 50, App
< x A, General Design Criterion 60 and the ign objectives given in 1 FR Part 50, Appendix I,Section II.D. The spec ed limits i
governi the use of appropriate portions of the systems were s cified as a sui le fraction of the dose design objectives set forth in 10 R
Par 0, Appendix I, Sections II.B and II.C for gaseous effluents.
e se limits apply to the combingd effluent of the plant (e.g. two unit 1.$
f.11.e:"r) Explosive Gas Mixture 3/4 l
l This specification is provided to ensure that the concentration of potentially ex)1osive gas mixtures contained in the Waste Gas Holdup System is maintained aelow the flamability limit of oxygen. Maintaining the concentration of oxygen below its flamability limit provides assurance SENuM354 that the releases of radioactive materials will be controlled in conformance with the requirements of 10 CFR Part 50, Appendix A, General
'~ Design Criterion 60.
=
L,2 l
3/4.11.fhfr) Gas Storace Tanks The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification to a quantity that is less than the i
quantity that provides assurance that in the event of an Ch = ged by NRC letter 6 ted Ar,ri! x rg3 DELETE l
3/N. Il.I GASECUS EFFLUENTS '
CALVERT CLIFFS - UNIT 2 B 3/4 11-4
l l
3/4.11 RADI0 ACTIVE EFFLUENTS d
BASES i
uncontrolled release of the tank's contents, the resulting total body exposure to a MEM8ER OF THE PUBLIC at the nearest SITE B0UNDARY will not a
]
exceed 10 CFR Part 100 limits.
I Restricting the quantity of radioactivity contained in each gas storage tank tank'provides assurance that in the event of an uncontrolled release of the i
s contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE B0UNDARY will not exceed accident guidelines.
t l
4.11.3 SOLID RADI0 ACTIVE WASTE This ecification implements the requirements of 10 CFR 50.36(a) 4 10 CFR rt 50 Appendix A, General Design Criterton 60. The.pr ss l
paramete are included in the PROCESS CONTROL PROGRAM.
l' 3/4.11.4 TO DOSE i
1 This specificatio is provided to meet the dose limit-ons of 3
"T 40 CFR Part 190 tha ave been incorporated into 10 R Part 20 by
d=
46 FR 18525. The spe fication requires the pre ation and submittal of a Special Report wh3never e calculated doses f plant generated H
radioactive effluents and frect radiation e eed 25 mrems to the total i};{3 body or any organ, except t thyroid, whi shall be Ifmited to less than or equal to 75 mrems. The Sp al Repor will. describe a course of action i
that should result in the limit on the annual dose to a MEMBER OF THE 5
PUBLIC to within the 40 CFR Part imits. For the purposes of the H
Special Report, it may be assume h
the dose comitment to the HEMBER OF THE PUBLIC from other uranium 1 cyc sources is negligible.
r 3
If the dose to any MEMBER THE PUBLIC is timated to exceed the j8 requirements of 40 CFR P t 190, the Special port with a request for a variance (provided th elease conditions resu ng in violation of 40 CFR Part 190 hay not already been corrected), n accordance with the 2
provisions of 40 3 Part 190.11 and 10 CFR Part 2. 05c, is considered to 1
be a timely re st and fulfills the requirements of CFR Part 190 until NRC staff ac on is completed. The variance only relat,to the limits of j
40 CFR Par 90, and does not apply in any way to the oth stequirements for dos imi.tation of 10 CFR Part 20, as addressed in Speci ations 3.11.1.1 and 3.11.2.1.
An individ.ual is not co idered a 4
MEM 0F THE PUBLIC during any period in which he/she is engage in rying out any operation that is part of the nuclear fuel cycle.
c l
j CALVERT CLIFFS - UNIT 2 B 3/4 11-5 1
Amendment No. 149 l
1 3/1.12 RADIOLOGICAL ENVIRONMENTAL MONITORING q
i wS
/
3 12.1 MONITORING PROGRAM The r iological environmental monitoring program required by thi specif ation provides representative measurements of radiation nd of radioac ve materials in those exposure pathways and for those radionuci es that lead to the highest potential radiation osures to MEMBERS 0F E PUBLIC resulting from the plant operation.
is monitoring
'i program impi nts 10 CFR Part 50 Appendix I, Section IV. 2 and thereby supplements t radiological effluent monitoring program y verifying that the measurable oncentrations of radioactive materials d levels of i
radiation are no higher than expected on the basis of the effluent measurements and e modeling of the environmental 1 osure pathways.
g, Guidance for this itoring program is provided by ne Radiological Assessment Branch Te nical Position on Environme al Monitoring.
Program changes may be initia d based on operational e rience.
The required detection c abilities for envi ntal sample analyses are tabulated in tems of the wer limits of d ection (LLDs). The LLDs required by Table 4.12-1 ar considered op" mum for routine environmental i
measurements in industrial la oratories.
J,t should be recognized that the LLD is defined as an a oriori efore t fact) limit representing the Z
capability of a measurement sys and ot as an a posteriori (after the I
w fact) limit for a particular meas nt.
pq Detailed discussion of the LLD an o er. detection limits can be found in HASL Procedures Manual. HASL-300 rey ed annually), Currie, L.A., " Limits for Qualitative Detection and C antita ve Detemination - Application to Radiochemistry," Anal. Chem. 44, 586-93 968), and Hartwell, J.K.,
i["
o
" Detection Limits for Radioa lytical Cou ing Techniques," Atlantic' Richfield Hanford Company port ARH-SA-21 (June 1975).
H 3/4.12.2 LAND USE CENS I; s, This specification i provided to ensure that ch ges in the use of areas s
h at and beyond the 5 E B0UNDARY are identified anc that modifications to d-T the radiological ironmental monitoring program a made if required by the results of t s census. The best infomation fr the door-to-door p
survey, from a al survey or from consulting with loc 1 agricultural authorities s 11 be used. This census satisfies the r uirements of 10 i
CFR Part 50, ppendix I,Section IV.B.3.
Restricting th census to gardens of greate.r an 50 m* provides assurance that significant posure pathways via leafy egetables will be identified and monitored since garden of i
this si is the minimum required to produce the quantity (2 g/ year) of leafy getables assumed in Regulatory Guide 1.109 for j
CALVERT CLIFFS - UNIT 2 B 3/4 12-1 Amendment No. 149 i
I l
1 3/1.12 RADIOLOGICAL ENVIRONMENTAL MCHITORING SES l
con ption by a child. To detemine this minimum garden size, the l
foll ing assumptions were made:
- 1) 20% of the garden was used for rowing l
broad eaf vegetation (i.e., similar to lettuce and cabbage), and a
vegetat n yield of 2 kg/m".
3/4.12.3 TERLABORATORY COMPARISON PROGRAM l
The requir t for participation in an approved Interlabor ory Comparison l
Program is pro ided to ensure that independent checks on e precision and i
accuracy of the asurements of radioactive material in vironmental sample matrices e performed as part of the quality a urance program for environmental moni ring in order to demonstrate that he results are valid i
[
for the purposes of 0 CFR Part 50, Appendix I, Sec on IV.B.2.
l <
i 4 VD-
.m.m u.sq I
- 4
'f 1
C 1
O i
i
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CALVERT CLIFFS - UNIT 2 B 3/4 12-2 Amendment No. 149
l q
6.0 ADMINISTRATIVE CONTROLS c.
The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.
d.
Proposed changes to the Technical Specifications incorporated in i
the license or proposed changes to the UFSAR or Bases that involve an unreviewed safety question shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC a) proval shall be provided to i
the NRC on a frequency consistent witi 10 CFR 50.71(e).
a 4
l g y
6.5.5 Radioactive Effluent Controls Proaram l
1 D.
T program conf 6rms to 10 CFR 50.36a for the control of radioactiv eff ents and for maintaining the doses to members of the public f m
, N radio tive effluents as low as reasonably achievable. The progr shall j
i be cont ned in the ODCM, shall be implemented by procedures, a shall e
include r edial actions to be taken whenever the program lim s are ji N exceeded.
e program shall include the following elements:
g a.
Limi tions on the functional capability of ra 'oactive liquid 1
g i
and ga ous monitoring instrumentation, inclu ng surveillance f
3 tests an setpoint determination, in accord ce with the j
methodolog in the CDCM; b.
Limitations o the concentrations of ra oactive material i
released in lig d effluents to unres icted areas, conforming to 10 CFR Part 20, A endix B, Table II Column 2; b
j\\
i c.
Monitoring, sampling, nd analysi of radioactive liquid and f
f gaseous effluents, in a ordanc with 10 CFR 20.1302, and with I
the methodology and para ter in the ODCM; k
d.
Limitations on the annual quarterly doses or dose commitment to a member of the publi from adioactive materials in liquid effluents released from ach un to unrestricted areas, t
conforming to 10 CFR P rt 50, App dix I; e.
Determination of c ulative and proje ed dose contributions from radioactive effl ts for the current c endar quarter and current calenda year, in accordance wit he methodology and parameters in e ODCM, at least every 31 s;
I(
f.
Limitation on the functional capability and u of the liquid and gaseo effluent treatment systems to ensure hat appropriate portion of these systems are used to reduce relea s of radio ivity when the projected doses in a period 31 days
)
woul exceed 2% of the guidelines for the annual dose r dose T
co tment, conforming to 10 CFR Part 50, Appendix I; g.
imitations on the dose rate resulting from radioactive mat ial released in gaseous effluents to areas beyond the site bound confonning to the dose associated with 10 CFR Part 20, Appendix B, Table II, Column 1; l
A-.<&
x x
CALVERT CLIFFS - UNIT 2 6-6 Amendment No. 193
r i
l INSERT "6.5.5" l
6.5.5 Radioactive Emuent Controls Program l
This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the 1
j doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable.
The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
Limitations on the functional capability of radioactive liquid and gaseous monitoring a.
instrumentation, including surveillance tests and setpoint determination, in accordance with the methodology in the ODCM; b.
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, I
Column 2; I
Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in c.
accordance with 10 CFR 20.1302, and with the methodology and parameters in the ODCM; d.
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF TIIE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS to t>e limited:
1.
During any calendar quarter: Less than or equal to 3 mrems to the total body, and to less than or equal to 10 mrems to any organ; and 2.
During any calendar year: Less than or equal to 6 mrems to the total body, and l
to less than or equal to 20 mrems to any organ; I
1 INSERT "6.5.5" (continued) e.
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year, in accordance with the i
methodology and parameters in the ODCM, at least every 31 days; f.
Limitations on the functional capability and use of the Liquid Radwaste Treatment System to ensure that appropriate portions of this system are used to reduce releases of radioactivity when the projected doses to UNRESTRICTED AREAS exceeds 0.36 mrem to the total body, or 1.20 mrem to any organ in a 92-day period; g.
Limitations on the functional capability and use of the Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System to ensure that appropriate l
portions of these systems are used to reduce releases of radioactivity 5. hen the calculated l
doses to UNRESTRICTED AREAS exceeds 1.20 mrad for gan* na radiation, and l
2.40 mrad for beta radiation in a 92-day period; h.
Limitations on the functional capability and use of the Ventilation Exhaust Treatment l
System to ensure that appropriate portions of this system are used to reduce releases of radioactivity when the calculated doses due to gaseous releases to UNRESTRICTED AREAS exceeds 1.8 mrem to any organ in a 92-day period; i.
Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY, to be limited:
1.
For noble gases: Less than or equal to 500 mrems/yr to the total body, and less than or equal to 3000 mrems/yr to the skin; and 2.
For iodine-131 and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ;
1 i
i INSERT "6.5.5" (continued) j.
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the SITE BOUNDARY, to be limited:
1.
During any calendar quarter: Less than or equal to 10 mrads for gamma radiation, and less than or equal to 20 mrads for beta radiation; and 2.
During any calendar year: Less than or equal to 20 mrads for gamma radiation, and less than or equal to 40 mrads for beta radiation; k.
Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from iodine-131, and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released to areas beyond the SITE BOUNDARY, to be limited:
1.
During any calendar quarter: Less than or equal to 15 mrems to any organ; j
2.
During any calendar year: Less than or equal to 30 mrems to any organ; and l
l 3.
Less than 0.1% of the limits of 6.5.5.k(l) and (2) as a result of burning contaminated oil; and I.
Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity, and to radiation from uranium fuel cycle sources to be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
l l
I i
i
l 6.0 ADMINISTRATIVE CONTROLS Limitations on the annual and quarterly air doses resuiting from ble gases released in gaseous effluents from each unit to as P
bey the site boundary, conforming to 10 CFR Part 50 Appendix
)
N 1.
Limitations on the al and quarter 1 es to a member of the Q
{
public from iodine-131, ne-13 tium, and all
\\
radionuclides in particulate with half lives > 8 days in l
N I
gaseous effluents relea rom ea it to areas beyond the k
site boundary, con ng to 10 CFR Par Appendix I; and h
j.
Limitat on the annual dose or dose commitment member of public due to releases of radioactivity and to ra on rom uranium fuel cycle sources, conforming to 40 CFR Part 1 A_
^
s 6.5.6 Containment Leakage Rate Testing Program l
A program shall be established to implement the leakage testing of the containment as required by 10 CFR 50.54(o) and 10 CFR Part 50, Appendix J.
Option B.
This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.
The peak calculated containment internal pressure for the design basis loss-of-coolant accident, P., is 49.4 psig. The containment design pressure is 50 psig.
I The maximum allowable containment leakage rate, L., shall be 0.20 percent of containment air weight per day at P,.
Containment leakage rate acceptance criterion is 51.0 L. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria is 5 0.75 L, for Type A tests.
The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.
The provisions of Specification 4.0.3 are applicable to the Containment Leakage Rate Testing Program.
CALVERT CLIFFS - UNIT 2 6-7 Amendment No. 193 l
l
1 6.0 ADMINISTRATIVE CONTROLS i
6.6 REPORTING REQUIREMENTS The following reports shall be submitted in accordance with 10 CFR 50.4.
6.6.1 Occupational Radiation Exposure Report
- A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures > 100 mrem /yr and their associated man rem exposure according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance [ describe maintenance], waste processing, l
and refueling). This tabulation supplements the requirements of 10 CFR j
l 20.2206. The dose assignment to various duty functions may be estimates based on pocket dosimeter, electronic personal dosimeter or l
thermoluminescent dosimeter. Small exposures totalling < 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources should be assigned to specific major work functions. The report shall be submitted prior to March 31 of each year.
6.6.2 Annual Radiological Environmental Operatino Report The Annual Radiological Environmental Operating Report covering the o ration of the unit during the previous calendar year shall be submitted
-iortomyIgeachyear.
C.mkne IThe report shall include sumaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the wM p*iod < reporting period. The material provided shall be consistent with the parayaph objectives outlined in the ODCM, and in 10 CFR Part 50, Appendix I, Sections IV.B.2, IV.B.3 and IV h nnual Niele lealTnsenmenh d>e The /eport s a i inciuoe e resu s of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these l
analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. p In the event that some individual results are not available for inclusio i with the report, the report shall be submitted noting and explaining the rtasons for the missin y su_1ts. _. Themissingdatashallbesubmittepassoon s
possible in a supplementary repor.
l tee reporf sAall idenllh fbe TZ h resulh Ebaf represenf ccl/ceakd desimefets in ralaH.n f. de H)?C 72Dpogram,and the exposee yrt.d associskd will each resuN.
~
A single submittal may be made for Calvert Cliffs. The submittal should combine those sections that are comon to both units.
Occupational dose from the Independent Spent Fuel Storage Installation will be reported separately.
CALVERT CLIFFS - UNIT 2 6-8 Amendment No. 193
l l
l 6.0 ADMINISTRATIVE CONTROLS l
6.6.3 Radioactive Effluent Release Report
- The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a (i.e.,
e between submittal of the reports must be no longer than 12 months). "
fThe report shall include a summary of the quantities of radioactive liquid Cem bine i and gaseous effluents and solid waste released from the units. The w;gfmts material provided shall be consistant with the objectives outlined in the A
ODCM and Process Control Program and in conformance with 10 CFR 50.36a and NY 10 CFR Part 50, Appendix I, Section IV.B.1 l
Licensee initiated major changes to the Radioactive Waste Systems (liquid, gaseous and solid) shall be reported to the Commission in the Radioactive Effluent Release Report for the period in which the modification to the waste system is completed. The discussion of each change shall contain:
a.
A description of the equipment, components and processes involved; and b.
Documentation of the fact that the changeVincluding the safety analysis s reviewed and found acceptable by the onsite review function, g l
The report shall also include changes to the ODCM, in accordance with i
Specification 6.5.1.c j
6.6.4 Monthly Operatina Report l
Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis, no later than the 15th of each month following the calendar month covered by the report.
l l
I I
W n
1#N Zn lieu of submission A ibe Radioachve Effluent Release Report, Se and Se'* analyses resulfs may be submiHed in a supplementy report within i
120 days afkr submi}hl of Ae Radioaelive Efflued 7felease Report.
.v A single submittal may be made for Calvert Cliffs, since the Radwaste 3
Systems are cor.inon to both units.
CALVERT CLIFFS - UNIT 2 6-9 Amendment No. 193