NUREG-1302, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors
Text
Offsite Dose Calculation
Manual Guidance: Standard
Radiological Effluent Controls
for Boiling Water Reactors
Generic Letter 89-01, Supplement No. 1
U.S. Nuclear Regulatory Commission
Office of Nuclear Reactor Regulation
W. W. Meinke, T. H. Essig
AVAILABILITY NOTICE
Availability of Reference Materials Cited in NRC Publications
Most documents cited in NRC publications will be available from one of the following
sources:
1. The NRC Public Document Room, 2120 L Street, NW, Lower Level, Washington, DC
20555
2. The Superintendent of Documents, U.S. Government Printing Office, P.O. Box 37082,
Washington, DC 20013-7082
3. The National Technical Information Service, Springfield, VA 22161
Although the listing that follows represents the majority of documents cited in NRC publications,
it is not intended to be exhaustive.
Referenced documents available for Inspection and copying for a fee from the NRC Public
Document Room include NRC correspondence and internal NRC memoranda; NRC Office of
Inspection and Enforcement bulletins, circulars, information notices, inspection and investigation
notices; Licensee Event Reports; vendor reports and correspondence: Commission
papers; and applicant and licensee documents and correspondence.
The following documents in the NUREG series are available for purchase from the GPO Sales
Program: formal NRC staff and contractor reports, NRG-sponsored conference proceedings,
and NRC booklets and brochures. Also available are Regulatory Guides, NRC regulations
in the Code of Federal Regulations, and Nuclear Regulatory Commission Issuances.
Documents available from the National Technical Information Service include NUREG series
reports and technical reports prepared by other federal agencies and reports prepared by
the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission.
Documents available from public and special technical libraries include all open literature
items, such as books, journal and periodical articles, and transactions. Federal Register
notices, federal and state legislation, and congressional reports can usually be obtained
from these libraries.
Documents such as theses, dissertations, foreign reports and translations, and non-NRC
conference proceedings are available for purchase from the organization sponsoring the
publication cited.
Single copies of NRC draft reports are available free, to the extent of supply, upon written
request to the Office of Information Resources Management, Distribution Section, U.S.
Nuclear Regulatory Commission, Washington, DC 20555.
Copies of industry codes and standards used in a substantive manner in the NRC regulatory
process are maintained at the NRC Library, 7920 Norfolk Avenue, Bethesda, Maryland, and
are available there for reference use by the public. Codes and standards are usually copyrighted
and may be purchased from the originating organization or, if they are American
National Standards, from the American National Standards Institute, 1430 Broadway,
New York, NY 10018.
Offsite Dose Calculation
Manual Guidance: Standard
Radiological Effluent Controls
for Boiling Water Reactors
Generic Letter 89-01, Supplement No. 1
Date Published: April 1991
W.W. Meinke, T. H. Essig
Division of Radiation Protection and Emergency Preparedness
Office of Nuclear Reactor Regulation
U.S. Nuclear Regulatory Commission
Washington, DC 20555
ABSTRACT
This report contains guidance which may be voluntarily used by licensees who
choose to implement the provision of Generic Letter 89-01, which allows Radiological
Effluent Technical Specif 1cations (RETS) to be removed from the main
body of the Technical Specifications and placed in the Offsite Dose Calculation
Manual (ODCM). Guidance is provided for Standard Effluent Controls definitions,
Controls for effluent monitoring instrumentation, Controls for effluent releases,
Controls for radiological environmental monitoring, and th~ basis for Controls.
Guidance on the formulation of RETS has been available in draft form (NUREG-0472
and -0473) for a number of years; the current effort simply recasts those RETS
into Standard Rad1ological Effluent Controls for application to the ODCM. Also
included for completeness are: (1) radiological environmental monitoring program
9uidance previously which had been available as a Branch Technical Position
(Rev. 1, November 1979); (2) existing ODCM guidance; and (3) a reproduction of
ii i
PREFACE
This compilation of Standard Radiological Effluent Controls (SREC) contains all
of the controls addressed in Generic Letter 89-01, to be incorporated into a
licensee's Offsite Dose Calculation Manual (ODCM) at the time the procedural
details of the current Radiological Effluent Technical Specifications (RETS)
are transferred out of the licensee's Technical Specifications (TS). It has
been developed by recasting the RETS of the most current Standard Technical
Specifications from the "LCO" format into the "Controls" format of an ODCM
entry. Note that these GE-SREC have been patterned after the ~-SREC. The
following text guidance incorporates the wording of the most recent SREC,
however, no attempt has been made to translate REC numbering of the W-SREC
into that of the BWR numbering system. -
The following GE-SREC provide the latest version of staff guidance, and document
current practice in the operating procedures required by 10 CFR 20.106,
40 CFR Part 190, 10 CFR 50.36(a), and Appendix I to 10 CFR Part 50. This
document contains no new requirements and its use is completely voluntary.
v
1
3/4
3/4.0
3/4.3
3/4.11
3/4.12
3/4
GE-SREC
TABLE OF CONTENTS
ABSTRACT. • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • iii
PREFACE.. . . • • • • • • • • • • • • • • • • • • . • • • • • • • • • • . • • • • • • • • • . • • • • v
FOREWORD............................................... [l]
DEFINITIONS •••..••••••••••••••••.••••••••••••••••••••••
CONTROLS AND SURVEILLANCE REQUIREMENTS ••••.••••••••••••
App l i cab i 1 i ty ......................................... .
Instrumentation . ...................................... .
Radioactive Effluents •.•.•.••.•••...•••..••.•.••••..•..
Radiological Environmental Monitoring •••••••.••••••.•••
BASES • •••••••••••••••••••••••••••••••••••••••••••••••••
[5]
[15]
[16]
[18]
[39]
[59]
[74]-
APPENDIX A: Radiological Assessment Branch Technical [85]
Position, Revision 1, November 1979
APPENDIX B: General Contents of the Offsite Dose
Calculation Manual
APPENDIX C: Generic Letter 89-01
vii
[94]
[98]
FOREWORD
RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS
Licensee Technical Specification (TS) amendment requests for incorporation of
Radiological Effluent Technical Specifications (RETS) pursuant to 10 CFR 50.36a
and Appendix I to 10 CFR Part 50 were approved in the mid-1980s for most
operating reactors licensed before 1979 (ORs). Plants licensed after 1979
(NTOLs), included the RETS as part of their initial Technical Specifications.
By November 1987, the RETS were implemented by all licensees of operating power
reactors. Detailed Safety Evaluation Reports (SERs) documented the acceptability
of the plant-specific RETS of the ORs, while the acceptance of the RETS
for the NTOLs followed the regular pattern of the Standard Technical Specifications
(STS). Thus, for all operating plants, the compliance of the licensee
with 10 CFR 50.36a and Appendix I to 10 CFR Part 50 is a matter of record.
Early draft revisions of model RETS, distributed to licensees in mid-1978,
·contained equations for dose calculations, setpoint determinations and meteorological
dispersion factors, as well as the procedural details for complying
with Appendix I to 10 CFR Part 50. In later revisions, including Revision 2
used as the bench mark for the NRC staff's acceptance of OR RETS, the equations
were removed and incorporated into an Offsite Dose Calculation Manual (ODCM)
prepared by the licensee and provided to NRC for review along with the proposed
RETS.
Early guidance for preparation of the Radiological Effluent Technical Specifications
(RETS) and Offsite Dose Calculation Manual (ODCM) was published in
NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for
Nuclear Power Plants," October 1978. Copies of model RETS, however, have been
available only in draft form as NUREG-0472, Revision 2, "Radiological Effluent
Technical Specifications for PWRs," February 1, 1980; NUREG-0473, Revision 2,
"Radiological Effluent Technical Specifications for BWRs," February 1, 1980;
and succeeding draft revisions. Staff guidance for the Radiological
Environmental Monitoring Program is contained in the Radiologica1 Assessment
Branch Technical Position (RAB-BTP), originally issued in March 1978 and
upgraded by Revision 1 in November 1979 as a result of the accident at Three
Mile Island. This Revision 1 to the RAB-BTP was forwarded to all operating
reactor licensees in November 1979 and remains in effect at the present time.
Since this BTP was never incorporated into the Regulatory Guide System, a copy
is reproduced in this document as Appendix A. Even though it has been used
extensively in reviewing ODCMs, guidance for the contents of the ODCM is found
only in an appendix to a paper presented at an Atomic Industrial Forum conference
in 1981, and has had only informal distribution since that time.
OFFSITE DOSE CALCULATION MANUAL
The potential for augmentation of a licensee's ODCM through transfer of the
procedural details of the RETS following the guidance of Generic Letter 89-01,
provides an opportunity to assemble in one set of documents the staff guidance
for the ODCM.
GE-SREC [1]
The current overview guidance for development of the ODCM was prepared origina
1 ly in July 1978 and revised in February 1979 after discussions with committees
of the Atomic Industrial Forum. This guidance was made generally
available as "Appendix B - General Contents of the Offsite Dose Calculation
Manual (ODCM) (Revision 1, February 1979)" to the paper authored by . ·
c. A. Willis and F. J. Congel, "Status of NRC Radiological Effluent Technical
Specification Activities" presented at the Atomic Industrial Forum Conference
on NEPA and Nuclear Regulation, October 4-7, 1981, Washington, D.C. -A copy of
this guidance that continues in effect to date, is reproduced in this document
as Appendix B.
During the discussions leading up to the implementation of the RETS by the ORs,
it became important to record in a "living" document certain interpretations
and understandings reached in these discussions. The ODCM thus became a
repository for such interpretations, as well as for other information requested
by the staff in connection with its evaluation of licensee's commitments and
performance under 10 CFR 50.36a and Appendix I to 10 CFR Part 50.
TECHNICAL SPECIFICATION IMPROVEMENT PROGRAM
Recently, the NRC staff has examined the contents of the RETS in relation to
the Commission's Interim Policy Statement on Technical Specification Improvements.
The staff has determined that progranrnatic controls can be implemented
in the Administrative Controls section of the Technical Specifications {TS) to
satisfy existing regulatory requirements for RETS. At the same time, the
procedural details of the current TS on radioactive effluents and radiological
environmental monitoring can be relocated to the Offsite Dose Calculation
Ma nu a 1 ( ODCM).
To initiate the change, new programmatic controls for radioactive effluents and
radiological environmental monitoring are incorporated in the TS to conform to
the regulatory requirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a,
and Appendix I to 10 CFR Part 50. The procedural details included in
licensees' present TS on radioactive effluents, environmental monitoring, and
associated reporting requirements will be relocated to the ODCM •. Licensees
will handle future changes to these procedural details in the ODCM ~nder the
administrative controls for changes to the ODCM. Detailed guidance to effect
the transfer of the RETS to the ODCM is given in Generic Letter 89-01, reproduced
in its entirety as Appendix C.
GUIDANCE FOR THE TRANSFER OF RETS TO ODCM
Enclosure 1 of Generic Letter (GL) 89-01 of Appendix B provides detailed
guidance for the preparation of a license amendment request to implement the
transfer of RETS to ODCM. Page 1 of the enclosure states:
"The NRC staff's intent in reco11111ending --- the relocation of procedural
details of the current RETS to the ODCM is to fulfill the goal of the
Commission Policy Statement for Technical Specification Improvements. It
is not the staff's intent to reduce the level of radiological effluent
control. Rather, this amendment will provide programmatic controls for
RETS consistent with regulatory requirements and allow relocation of the
procedura 1 deta i1 s of current RETS to the ODCM."
GE-SREC [2]
Page 2 of Enclosure 1 states:
11 ••• the procedural details covered in the licensee's current RETS,
consisting of the limiting conditions for operation, their applicability,
remedial actions, surveillance requirements, and the Bases
section of the TS for these requirements, are to be relocated to the
ODCM --- in a manner that ensures that these details are incorporated
in plant operating procedures. The NRC staff does not intend to repeat
technical reviews of the relocated procedural details because their
consistency with the applicable regulatory requirements is a matter
of record from past NRC reviews of RETS. 11
DISCUSSION
For the purpose of the transfer described in GL 89-01 of Appendix B, the RETS
will consist of the specifications from the STS listed in Enclosure 2 of Appendix
B of GL 89-01. Licensees with nonstandard TS should consider the analogous
TS in their format.
It is suggested that the most straightforward method of transferring a licensee's
commitments in the RETS to the ODCM in accordance with GL 98-01 is to recast
the RETS in the licensee's present TS from the "Limiting Condition for Operation
(LCO)" format of the TS into the "Controls0 format of the ODCM entry. The
accompanying package provides an example of this recasting into Standard Radiological
Effluent Controls (SREC) from the model RETS for Boiling Water Reactors
(BWRs). This recasting is in format only. The TS pages have been transferred
to the ODCM without change except for the substitution of °Controls0 for "LC0. 11
Plants that have RETS that closely follow the STS format will be able to use
the accompanying examples directly as guidance. For plants with nonstandard
RETS, the transfer of TS commitments to the ODCM should be made similarly page
by page, again with the substitution of °Controls" for 11 LC0. 11
This NUREG report contains no new requirements; licensee implementation of this
guidance is completely voluntary.
SUMMARY
As part of the license amendment request for TS improvement relative to the
RETS, a licensee confirms that the guidance of Generic Letter 89-01 has been
followed. This guidance includes the following:
"The procedural details covered in the licensee's current RETS, consisting
of the limiting conditions for operation, their applicability,
remedial actions, surveillance requirements, and the Bases section of
the TS for these requirements, are to be relocated to the ODCM --- in
a manner that ensures that these details are incorporated in plant
operating procedures."
The Standard Radiological Effluent Controls {SREC) compiled in this report
document current staff practice in the operating procedures required by
10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36(a), and Appendix I to 10 CFR Part 50. Thus they contain all of the controls required by Generic Letter 89-01, to be incorporated into a licensee's ODCM at the time the procedural
details of the current RETS are transferred out of the licensee's TS.
GE-SREC [3]
GE-SREC
NOTE
These GE-SREC have been
patterned after the ~-SREC.
The following text guidance incorporates the
wording of the most recent SREC; however,
no attempt has been made to translate the
REC numbering of the ~-SREC into that
of the BWR numbering system
[4]
GE-SREC
SECTION 1. 0
DEFINITIONS
[5]
1. 0 DEFINITIONS
The defined terms of this section appear in capitalized type and are applicable
throughout these Controls.
ACTION
1.1 ACTION shall be that part of a Control that prescribes remedial measures
required under designated conditions.
CHANNEL CALIBRATION
1.4 An CHANNEL CALIBRATION shall be the adjustment, as necessary, of the
channel such that it responds within the required range and accuracy to known
values of input. The CHANNEL CALIBRATION shall encompass the entire channel
including the sensors and alarm, interlock and/or trip functions and shall
include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed
by any series of sequential, overlapping, or total channel steps such that the
entire channel is calibrated.
CHANNEL CHECK
1.5 A CHANNEL CHECK shall be the qualitative assessment of channel behavior
during operation by observation. This determination shall include, where
possible, comparison of the channel indication and/or status with other
indications and/or status derived from independent instrument channels
measuring the same parameter.
CHANNEL FUNCTIONAL TEST
1.6 A CHANNEL FUNCTIONAL TEST shall be:
a. Analog channels - the injection of a simulated signal into the
channel as close to the sensor as practicable to verify OPERABILITY
including alarm and/or trip functions and channel failure trips.
b. Bistable channels - the injection of a simulated signal into the
sensor to verify OPERABILITY including alarm and/or trip functions.
The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential,
overlapping or total channel steps such that the entire channel is tested.
GE-SREC [6]
DEFINITIONS
DOSE EQUIVALENT I-131
1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microCurie/gram)
which alone would produce the same thyroid dose as the quantity and isotopic
mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid
dose conversion factors used for this calculation shall be those listed in
[Table III of TID-14844, "Calculation of Distance Factors for Power and Test
Reactor Sites" or Table E-7 of NRC Regulatory Guide 1.109, Revision 1,
October 1977].
GE-SREC [7]
DEFINITIONS
FREQUENCY NOTATION
1.13 The FREQUENCY NOTATION specified for the performance of Surveillance
Requirements shall correspond to the intervals defined in Table 1.1.
GASEOUS RADWASTE TREATMENT SYSTEM
1.14 A GASEOUS RADWASTE TREATMENT SYSTEM (e.g., the "augmented offgas
system") is any system designed and installed to reduce radioactive gaseous
effluents by collecting primary coolant system offgases from the main
condenser evacuation system and providing for delay or holdup for the purpose
of reducing the total radioactivity prior to release to the environment.
MEMBER(S) OF THE PUBLIC
1.16 MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally
associated with the plant. This category does not include employees
of the licensee, its contractors, or vendors. Also excluded from this category
are persons who enter the site to service equipment or to make deliveries.
This category does include persons who use portions of the site for recreational,
occupational, or other purposes not associated with the plant.
OFFSITE DOSE CALCULATION MANUAL
1.17 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/Trip Setpoints, and in the conduct of the
Environmental Radiological Monitoring Program. The ODCM shall also contain
(1) the Radioactive Effluent Controls and Radiological Environmental Monitoring
Programs required by Section 6.8.4 and (2) descriptions of the information that
should be included in the Annual Radiological Environmental Operating and
Semiannual Radioactive Effluent Release Reports required by TS 6.9.l.3 and
6.9.1.4.
GE-SREC [8]
DEFINITIONS
1.18 A system, subsystem, train, component or device shall be OPERABLE or
have OPERABILITY when it is capable of performing its specified function(s),
and when all necessary attendant instrumentation, controls, electric61 power,
cooling or seal water, lubrication or other 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 CONDITION - CONDITION
1.19 An OPERATIONAL CONDITION, i.e., CONDITION, shall be any one inclusive
combination of mode switch position and average reactor coolant temperatures
as specified in Table 1.2.
PURGE - PURGING
1.23 PURGE or PURGING shall be any controlled process of discharging air or gas
from a confinement to maintain temperature, pressure, humidity, concentration
or other operating condition, in such a manner that replacement air or gas is
required to purify the confinement.
GE-SREC [9]
DEFINITIONS
RATED THERMAL POWER
1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to
the reactor coolant of MWt.
REPORTABLE EVENT
1.27 A REPORTABLE EVENT shall be any of those conditions specified in
Section 50.73 of 10 CFR Part 50.
SITE BOUNDARY
1.30 The SITE BOUNDARY shall be that line beyond which the land is neither
owned, nor leased, nor otherwise controlled by the licensee.
GE-SREC [10]
DEFINITIONS
SOURCE CHECK
1.33 A SOURCE CHECK shall be the qualitative assessment of channel response
when the channel sensor is exposed to a source of increased radioactivity.
THERMAL POWER
1.35 THERMAL POWER shall be the total reactor core heat transfer rate to the
GE-SREC [ 11 ]
DEFINITIONS
UNRESTRICTED AREA
1.38 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY
access to which is not controlled by the licensee for purposes of pr~tection of
individuals from exposure to radiation and radioactive materials, or any area
within the SITE BOUNDARY used for residential quarters or for industrial,
commercial, institutional, and/or recreational purposes.
VENTILATION EXHAUST TREATMENT SYSTEM
1.39 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and
installed to reduce gaseous radioiodine or radioactive material in particulate
form in effluents by passing ventilation or vent exhaust gases through charcoal
adsorbers and/or HEPA filters for the purpose of removing iodines or particu-
-lates 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 Features Atmospheric Cleanup Systems are not considered
to be VENTILATION EXHAUST TREATMENT SYSTEM components.
VENTING
1.40 VENTING shall be the controlled process of discharging air or gas from a
confinement to maintain temperature, pressure, humidity, concentration, or other
operating condition, in such a manner that replacement air or gas is not provided
or required during VENTING. Vent, used in system names, does not imply
a VENTING process.
GE-SREC [12]
NOTATION
s
GE-SREC
D
w
M
Q
R
S/U
N.A.
p
TABLE 1.1
FREQUENCY NOTATION
FREQUENCY
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
At least once per 7 days.
At least once per 31 days.
At least once per 92 days.
At least once per 184 days.
At least once per 18 months.
Prior to each reactor startup.
Not applicable.
Completed prior to each release.
[13]
TABLE 1. 2
OPERATIONAL CONDITIONS
MODE SWITCH AVERAGE REACTOR
CONDITION POSITION COOLANT TEMPE&ATURE
1.
2.
3.
4.
5.
POWER OPERATION Run Any temperature
STARTUP Startup/Hot Standby Any temperature
HOT SHUTDOWN Shutdown # ' *** > 200°F
COLD SHUTDOWN Shutdown#,##,*** <= 200°F
REFUELING* Shutdown or Refuel ** •# ~ 140°F
- The reactor mode switch may be placed in the Run or Startup/Hot Standby
position to test the switch interlock functions provided that the control
rods are verified to remain fully inserted by a second licensed operator or
other technically qualified member of the unit technical staff.
- The reactor mode switch may be placed in the Refuel position while a single
control rod drive is being removed from the reactor pressure vessel per
Specification 3.9.10.1.
- Fuel in the reactor vessel with the vessel head closure bolts less than
fully tensioned or with the head removed.
- See Special Tests Exceptions 3.10.1 and 3.10.3.
- The reactor mode switch may be placed in the Refuel position while a single
control rod is being recoupled provided that the one-rod-out interlock is
GE-SREC [14]
GE-SREC
SECTIONS 3.0 AND 4.0
CONTROLS
AND
SURVEILLANCE REQUIREMENTS
[15]
3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS
3/4.0 APPLICABILITY
CONTROLS
3.0.1 Compliance with the Controls contained in the succeeding controls is
required during the OPERATIONAL CONDITIONS or other conditions specified
therein; except that upon failure to meet the Control, the associated ACTION
requirements shall be met.
3.0.2 Noncompliance with a control shall exist when the requirements of the
Control and associated ACTION requirements are not met within the specified
time intervals. Jf the Control is restored prior to expiration of the
specified time intervals, completion of the ACTION requirements is not
required.
3.0.3 When a Control is not met, except as provided in the associated ACTION
requirements, within l hour action shall be initiated to place the unit in an
OPERATIONAL CONDITION in which the control does not apply by placing it, as
applicable, in:
1. At least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and
3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where corrective measures are completed that permit operation under the ACTION
requirements, the action may be taken in accordance with the specified time
limits as measured from the time of failure to meet the Control. Exceptions
to these requirements are stated in the individual controls.
This control is not applicable in OPERATIONAL CONDITIONS 4 or 5.
3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall
not be made unless the conditions for the Control are met without reliance on
provisions contained in the ACTION requirements. _This provision shall not
prevent passage through or to OPERATIONAL CONDITIONS as required to comply
with ACTION requirements. Exceptions to these requirements are stated in the
individual controls.
GE-SREC [16]
APPLICABILITY
SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL.
CONDITIONS or other conditions specified for individual Controls unless
otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall be performed within the specified
time interval with:
a. A maximum allowable extension not to exceed 25% of the surveillance
interval, but
b. The combined time interval for any three consecutive surveillance
intervals shall not exceed 3.25 times the specified surveillance
interval.
4.0.3 Failure to perform a Surveillance Requirement within the specified
time interval shall constitute a failure to meet the OPERABILITY requirements
for a Control. Exceptions to these requirements are stated in the individual
controls. Surveillance Requirements do not have to be performed on inoperable
equipment.
4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable
condition shall not be made unless the Surveillance Requirement(s) associated
with the Control has been performed within the applicable surveillance
interval or as otherwise specified.
GE-SREC [17]
INSTRUMENTATION
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
CONTROLS
3.3.3.10 In accordance with [plant name] TS 6.8.4.g.l), the radioactive liquid
effluent monitoring instrumentation channels shown in Table 3.3-12 shall be
OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of
Control 3.11.l.l are not exceeded. The Alarm/Trip Setpoints of these channels
shall be determined and adjusted in accordance with the methodology and
parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
APPLICABILITY: At all times.
ACTION:
a. With a radioactive liquid effluent monitoring instrumentation channel
Alarm/Trip Setpoint less conservative than required by the above
control, immediately suspend the release of radioactive liquid
effluents monitored by the affected channel, or declare the channel
inoperable, or change the setpoint so it is acceptably conservative.
b. With less than the minimum number of radioactive liquid effluent
monitoring instrumentation channels OPERABLE, take the ACTION shown
in Table 3.3-12. Restore the inoperable instrumentation to OPERABLE
status within 30 days and, if unsuccessful, explain in the next
Semiannual Radioactive Effluent Release Report pursuant to Control
6.9.1.4 why this inoperability was not corrected in a timely manner.
c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
Report all deviations in the Semiannual Radioactive Effluent Release
Report.
SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel
shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE
CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies
shown in Table 4.3-8.
GE·SREC [18]
TABLE 3.3-12
,G,",t
' RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ,"::,:u,'
n
MINIMUM
CHANNELS
INSTRUMENT OPERABLE ACTION
1. Radioactivity Monitors Providing Alarm and
Automatic Termination of Release
a. Liquid Radwaste Effluent Line 1 35
2. Radioactivity Monitors Providing Alarm But Not Providing
Automatic Termination of Release
a. Service Water System Effluent line 1 37
b. Component Cooling Water System Effluent line 1 37
,........, 3. (Not Used) ~ ......
4. Flow Rate Measurement Devices
a. liquid Radwaste Effluent line 1 38
b. Discharge Canal 1 38
5. Radioactivity Recorders*
a. liquid Radwaste Effluent line 1 39
- Required only if Alarm/Trip Setpoint is based on recorder-controller.
GE-SREC
(NOT USED}
[20]
ACTION 35 -
ACTION 37 -
ACTION 38 -
ACTION 39 -
GE-SREC
TABLE 3.3-12 (Continued)
ACTION STATEMENTS
With the number of channels OPERABLE less than requir!d by the
Minimum Channels OPERABLE requirement, effluent releases via
this pathway may continue provided that prior to initiating a
release:
a. At least two independent samples are analyzed in accordance
with Control 4.11.1.1.1, and
b. At least two technically qualified members of the facility
staff independently verify the release rate calculations
and discharge line valving.
Otherwise, suspend release of radioactive effluents via this
pathway.
With the number of channels OPERABLE less than required by the
Minimum Channels OPERABLE requirement, effluent releases via
this pathway may continue provided that, at least once per
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for radioactivity
at a lower limit of detection of no more than
10-7 microCurie/ml.
With the number of channels OPERABLE less than required by the
Minimum Channels OPERABLE requirement, effluent releases via
this pathway may continue provided the flow rate is estimated
at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump performance
curves generated in place may be used to estimate flow.
With the number of channels OPERABLE less than required by the
Minimum Channels OPERABLE requirement, effluent releases via
this pathway may continue provided the radioactivity level is
determined at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
[ 21]
TABLE 4.3-8
C')
m
"~ ~ADI_OACTI_VE_LJJlUID EFFLUENT MONITORING INSTRUMENTATIOt!__~U~Y_EILLANCE REQUIREMENTS m
n
CHANNEL
CHANNEL SOURCE CHANNEL FUNCTIONAL
INSTRUMENT CHECK CHECK CALIBRATION TEST
1. Radioactivity Monitors Providing
Alarm and Automatic Termination
of Release
a. liquid Radwaste Effluent Line 0 p R(l) Q(l)
2. Radioactivity Monitors Providing Alarm But
Not Providing Automatic Termination
of Release
a. Service Water System Effluent line 0 M R(l) Q(2)
,...., b. Component Cooling Water System Effluent N
.N.... ... Line 0 M R(3) Q(2)
3. (Not Used)
4. Flow Rate Measurement Devices
a. liquid Radwaste Effluent Line 0(4) N.A. R Q
b. Discharge Cana 1 0(4) N.A. R Q
5. Radf oactf vf ty Recorders*
a. liquid Radwaste Effluent line 0 N.A. R •Q
- Required only if Alarm/Trip Setpoint in based on recorder-controller.
GE·SREC
(NOT USED)
[23]
TABLE 4.3-8 (Continued)
TABLE NOTATIONS
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation
of this pathway and control room alarm annunciation occur tf any
of the following conditions exists:
a. Instrument indicates measured levels above the Alarm/Trip Setpoint, or
b. Circuit failure, or
c. Instrument indicates a downscale failure, or
d. Instrument controls not set in operate mode.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm
annunciation occurs if any of the following conditions exists:
a. Instrument indicates measured levels above the Alarm Setpoint, or
b. Circuit failure, or
c. Instrument indicates a downscale failure, or
d. Instrument controls not set in operate mode.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of
the reference standards certified by the National Bureau of Standards (NBS)
or using standards that have been obtained from suppliers that participate
in measurement assurance activities with NBS. These standards shall permit
calibrating the system over its intended range of energy and measurement
range. For subsequent CHANNEL CALIBRATION, sources that have been related
to the initial calibration shall be used.
(4) CHANNEL CHECK shall consist of verifying indication of flow during periods
of release. CHANNEL CHECK shall 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 continuous, periodic, or batch releases are made.
GE·SREC
[24]
INSTRUMENTATION
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
CONTROLS
3.3.3.11 In accordance with [plant name] TS 6.8.4.g.1), the radioactive gaseous
effluent monitoring instrumentation channels shown in Table 3.3-13 shall be
OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of
Control 3.11.2.1 are not exceeded. The Alarm/Trip Setpoints of these channels
shall be determined and adjusted in accordance with the methodology and
parameters in the ODCM.
APPLICABILITY: As shown in Table 3.3-13
ACTION:
a. With a radioactive gaseous effluent monitoring instrumentation
channel Alarm/Trip Setpoint less conservative than required by the
above control, immediately suspend the release of radioactive
gaseous effluents monitored by the affected channel, or declare the
channel inoperable, or change the setpoint so it is acceptably
conservative.
b. With less than the minimum number of radioactive gaseous effluent
monitoring instrumentation channels OPERABLE, take the ACTION shown
in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE
status within 30 days and, if unsuccessful, explain in the next Semiannual
Radioactive Effluent Release Report pursuant to Control
6.9.1.4 why this inoperability was not corrected in a timely
manner.
c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
Report all deviations in the Semiannual Radioactive Effluent Release
Report.
SURVEILLANCE REQUIREMENTS 4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel
shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE
CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown
in Table 4.3-9.
GE-SREC (25]
a TABLE 3.3-13
e"'n' RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ::a
"n '
MINIMUM CHANNELS
INSTRUMENT OPERABLE APPLICABILITY ACTION
1. Main Condenser Offgas Treatment System
Effluent Monitoring System
a. Noble Gas Activity Monitor -
Providing Alarm and Automatic
Termination of Release 1 fr 47
b. Iodine Sampler 1 fr 51
c. Particulate Sampler 1 fr 51
d. Effluent System Flow Rate
,...., Measuring Device 1 fr 46
N
.°...'.. e • Sa1111>ler Flow Rate Measuring Device 1 fr 46
2A. NOT USED
28. NOT USED
a
IABLE_3.3-13 (Continued)
ITI
.,I , RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
- ID
ITI n
MINIMUM CHANNELS
INSTRUMENT OPERABLE APPLICABILITY ACTION
3. Reactor Building Ventilation/Purge System
a. Noble Gas Activity Monitor 1 * 48
b. Iodine Sampler 1 * 51
c. Particulate Sampler 1 * 51
d. Flow Rate Monitor 1 * 46
e. Sampler Flow Rate Monitor 1 * 46
~
N
4. Main Stack System
'"-" a. Noble Gas Activity Monitor 1 * 47
b. Iodine Sampler 1 * 51
c. Particulate Sampler 1 * 51
d. Flow Rate Monitor 1 * 46
e. Sampler Flow Rate Monitor 1 * 46
5. Turbfne Building Ventilation System
•• Noble Gas activity Monitor 1 * 47
b. Iodine Sampler 1 * 51
c • Particulate Sampler 1 * 51
..
TABLE 3.3~13 (Continued)
G')
'"' RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION :"0' n'"
MINIMUM CHANNELS
INSTRUMENT OPERABLE APPLICABILITY ACTION
5. Turbine Building Ventilation
System (Continued)
d. Flow Rate Monitor 1 * 46
e. Sampler Flow Rate Monitor 1 * 46
6. Auxiliary Building Ventilation System
a. Noble Gas Activity Monitor 1 * 47
,....., b. Iodine Sampler 1 * 51
N
00 c. Particulate Sampler 1 * 51 L-1
d. Flow Rate Monitor 1 * 46
e. Sampler Flow Rate Monitor 1 * 46
7. Fuel Storage Area Ventilation System
a. Noble Gas Activity Monitor 1 * 47
b. Iodfne Sampler 1 * 51
c. Particulate Sampler 1 * 51
'
d. Flow Rate Monitor 1 * 46
e. Sampler Flow Rate Monitor 1 * 46
JABLE 3.3-13 (Continued)
~ "e'n' RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
- .0 "n '
MINIMUM CHANNELS
INSTRUMENT ·OPERABLE APPLICABILITY ACTION
8. Radwaste Area Ventilation System
a. Noble Gas Activity Monitor 1 llll 47
b. Iodine Sampler 1 llll 51
c. Particulate Sampler 1 llll 51
d. Flow Rate Monitor 1 llll 46
e. Sampler Flow Rate Monitor 1 llll 46
,_.,
I\) 9. Turbine Gland Seal Condenser Vent and '-0 L...I Mechanical Vacuum Pump Exhaust System
a. Noble Gas Activity Monitor 1 llll 47
b. Iodine Sampler 1 llll 51
c. Particulate Sampler 1 llll 51
d. Flow Rate Monitor 1 llll 46
e. Sampler Flow Rate Monitor 1 llll 46
10. Condenser Air Ejector Radioactivity
Monitor (Prior to Input to Holdup
System)
a. Noble Gas Activity Monitor 1 llllllllllll 45
GE-SREC
CNOT USED)
[30]
TABLE 3.3-13 (Continued)
TABLE NOTATIONS
- At all times.
- During main condenser offgas treatment system operation.
- During operation of the main condenser air ejector.
ACTION 45 -
ACTION 46 -
ACTION 47 -
ACTION 48 -
ACTION 49 -
ACTION 50 -
ACTION 51 -
GE-SREC
ACTION STATEMENTS
With the number of channels OPERABLE less than required by the
Minimum Channels OPERABLE requirement, releases to the
environment may continue for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided:
a. The offgas system is not bypassed, and
b. The offgas delay system noble gas activity effluent
(downstream) monitor is OPERABLE;
Otherwise, be in at least HOT STANDBY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
With the number of channels OPERABLE less than required by the
Minimum Channels OPERABLE requirement, effluent releases via
this pathway may continue provided the flow rate is estimated at
least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
With the number of channels OPERABLE less than required by the
Minimum Channels OPERABLE requirement, effluent releases via
this pathway may continue provided grab samples are taken at
least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for
radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
With the number of channels OPERABLE less than required by the
Minimum Channels OPERABLE requirement, innediately suspend
release of radioactive effluents via this pathway.
With the number of channels OPERABLE less than required by the
Minimum Channels OPERABLE requirement, operation of the main
condenser offgas treatment system may continue provided grab
samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed
within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
With the number of channels OPERABLE one less than required by
the Minimum Channels OPERABLE requirement, operation of this
system may continue for up to 14 days.
With the number of channels OPERABLE less than required by the
Minimum Channels OPERABLE requirement, effluent releases via
the affected pathway may continue provided samples are continuously
collected with auxiliary sampling equipment as required
in Table 4.11-2.
[31]
GE-SREC
(NOT USED)
(32]
TABLE 4.3-9
~ .'",•, RADIOACTIVE GASEOUS EFFLUENT_MONJ"TORING_ INSTRUMENTATION _SURVEILLANCE REQUIREMENTS
- ID "n '
CHANNEL MODES FOR WHICH
CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE
INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED
1. Main Condenser Offgas Treatment
System Effluent Monitoring System
a. Noble Gas Activity Monitor -
Providing Alarm and Automatic
Termination of Release D D R(3) Q(l) lit
b. Iodine Sampler w N.A. N.A. N.A. lit
c. Particulate Sampler w N.A. N.A. N.A. lit
d. Effluent System Flow Rate D N.A. R Q· 1t
,......, Measuring Devke w
w
'--' e. Sampler Flow Rate Monitor D N. A. R Q 1t
2A. NOT USED
28. NOT USED
~-- -------
TABLE 4.3-9 (Continued)
C')
rT'I I RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION _SURVEILLANCE REQUIREMENTS
";;o'
rT'I n
CHANNEL MODES FOR WHICH
CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE
INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED - - --- ----- ------ -
3. Reactor Building Ventilation/Purge
System
a. Noble Gas Activity Monitor 0 M R(3) Q(l) *
b. Iodine Sampler w N.A. N.A. N.A. *
c. Particulate Sampler w N.A. N.A. N.A. *
d. Flow Rate Monitor 0 N.A. R Q *
,......,
w e. Sampler Flow Rate Monitor 0 N.A. R Q * +::>
'-'
4. Main Stack System
a. Noble Gas Activity Monitor 0 M R(3) Q(2) *
b. Iodine Sampler w N.A. N.A. N.A. *
c. Particulate Sampler w N.A. N.A. N.A. *
d. Flow Rate Monitor 0 N.A. R Q *
e. Sampler Flow Rate Monitor 0 N.A. R Q lit
C')
TABLE 4.3-9 {Continued)
"I" "::u' RADIOACTIVE GASEOUS EFFLUENTMONITORING INSTRUMENTATJON_~URVEltLANCEREQUIREMENTS
n""
CHANNEL MODES FOR WHICH
CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE
INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED
5. Turbine Building Ventilation
System
a. Noble Gas Activity Monitor D M R{3) Q(2) *
b. Iodine Sampler w N.A. N.A. N.A. *
c. Particulate Sampler w N.A. N.A. N.A. *
d. Flow Rate Monitor D N.A. R Q *
,....., e. Sampler Flow Rate Monitor D N.A. R Q * w
<J1
L-1 6. Auxiliary Building Ventilation
System
a. Noble Gas Activity Monitor D M R(3) Q(2) *
b. Iodine Sampler w N.A. N.A. N.A. *
c. Particulate Sampler w N. A. N.A. N.A. *
d. Flow Rate Monitor D N.A. R Q *
e. Sa111Pler Flow Rate Monitor D N.A. R Q *
TABLE 4. 3-_9 (Continued)
C) m
' RADIOACT_l'{_E _ G~~IQUS EFFLUENT MONITORING INSTRUMENTATION SU~VEIJ_L~NCE REQUIREMENTS ;"a' m
n
CHANNEL MODES FOR WHICH
CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE
INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED
7. Fuel Storage Area Ventilation
System
a. Noble Gas Activity Monitor D M R(3) Q(2) Jilt
b. Iodine Sampler w N. A. N.A. N.A. Jilt
c. Particulate Sampler w N.A. N.A. N.A. Jilt
d. Flow Rate Monitor D N.A. R Q Jilt
,......,
w e. Sampler Flow Rate Monitor D N.A. R Q Jilt
L°-1'
8. Radwaste Area Ventilation System
a. Noble Gas Activity Monitor D M R(J) Q(2) Jilt
b. Iodine Sampler w N.A. N.A. N.A. Jilt
c. Particulate Sampler w N.A. N.A. N.A. Jilt
d. Flow Rate Monitor D N.A. R Q Jilt
e. Sampler Flow Rate Monitor D N.A. R Q lit
G')
JABJ.E_4~3-_~ __ (Continued)
"I ' "' RAOl_OAC'f_l_VE_GASEOUS_~f'FLUENT MONITORING INSTRUMENTJ\IJON_SURVEILLANCE REQUIREMENTS :ID "n '
CHANNEL MODES FOR WHICH
CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE
INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED
9. Turbine Gland Seal Condenser Vent
and Mechanical Vacuum Pump
Exhaust System
a. Noble Gas Activity Monitor D M R(3) Q(2) *
b. Iodine Sampler w N.A. N.A. N.A. *
c. Particulate Sampler w N.A. N. A. N.A. *
,...., d. Flow Rate Monitor 0 N.A. R Q *
w
...... e. Sampler Flow Rate Monitor D N.A. R Q * ~
10. Condenser Air Ejector Radioactivity
Monitor (Prior to Input to Holdup
System)
a. Noble Gas Activity Monitor D M R(3) Q(2) ***
- At all times.
TABLE 4.3-9 (Continued)
TABLE NOTATIONS
- During main condenser offgas treatment system operation.
- During operation of the main condenser air ejector.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic
isolation of this pathway and control room alarm annunciation occurs if
any of the following conditions exists:
a. Instrument indicates measured levels above the Alarm/Trip Setpoint, or
b. Circuit failure, or
c. Instrument indicates a downscale failure, or
d. Instrument controls not set in operate mode.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room
alarm annunciation occurs if any of the following conditions exists:
a. Instrument indicates measured levels above the Alarm Setpoint, or
b. Circuit failure, or
c. Instrument indicates a downscale failure, or
d. Instrument controls not set in operate mode.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of
the reference standards certified by the National Bureau of Standards (NBS)
or using standards that have been obtained from suppliers that participate
in measurement assurance activities with NBS. These standards shall permit
calibrating the system over its intended range of energy and measurement
range. For subsequent CHANNEL CALIBRATION, sources that have been related
to the initial calibration shall be used.
(4) The CHANNEL CALIBRATION shall include the use of standard gas samples
containing a nominal:
a. One volume percent hydrogen, balance nitrogen, and
b. Four volume percent hydrogen, balance nitrogen.
(5} The CHANNEL CALIBRATION shall include the use of standard gas samples
containing a nominal:
a. One volume percent oxygen, balance nitrogen, and
b. Four volume percent oxygen, balance nitrogen.
GE-SREC [38]
3/4.11 RADIOACTIVE EFFLUENTS
3/4.11.1 LIQUID EFFLUENTS
CONCENTRATION
CONTROLS
3.11.1.1 In accordance with [plant name] TS 6.8.4.g.2) and 3), the concentration
of radioactive material released in liquid effluents to UNRESTRICTED AREAS
(see Figure 5.1-3) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved
or entrained noble gases. For dissolved or entrained noble gases, the concentration
shall be limited to 2 x 10-4 microCurie/ml total activity.
APPLICABILITY: At all times.
ACTION:
a. With the concentration of radioactive material released in liquid
effluents to UNRESTRICTED AREAS exceeding the above limits,
immediately restore the concentration to within the above limits.
b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.1.l Radioactive liquid wastes shall be sampled and analyzed according
to the sampling and analysis program of Table 4.11-1.
4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance
with the methodology and parameters in the ODCM to assure that the concentrations
at the point of release are maintained within the limits of Control 3.11.1.1.
GE-SREC [39]
TABLE 4.11-1
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM
- LOWER LIMIT
MINIMUM OF DETECTION
LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)(l)
TYPE FREQUENCY FREQUENCY ANALYSIS (μCi/ml)
l. Batch Waste p p
Release Each Batch Each Batch Principal Gamma 5xl0- 7
Tanks(2) Emitters(3)
I-131 lxlO-ti
a.
p M Dissolved and lxl0-5
One Batch/M Entrained Gases
(Gamma Emitters)
b.
p M H-3 lxl0-5
Each Batch Composite<4>
Gross Alpha lxl0-7
c.
p Q Sr-89, Sr-90 5x10- 8
Each Batch Composite<4>
Fe-55 lxl0-6
2. Continuous w Principal Gamma 5x10- 7
Releases< 5> Continuous<6> Composite< 6> Emitters<3>
I-131 lxl0-6
a.
M M Dissolved and lxl0-5
Grab Sample Entrained Gases
(Gamma Emitters)
b.
Continuous<6>
M
Composite<6>
H-3 lxl0-5
Gross Alpha lxl0-7
c.
Continuous<6>
Q
Composite<6>
Sr-89, Sr-90 Sxl0-8
Fe-SS lxl0-6
GE-SREC [40]
TABLE NOTATIONS
(l)The LLD is defined, for purposes of these controls, as the smallest
concentration of radioactive material in a sample that will yield a net
count, above system background, that will be detected with 95% probability
with only 5% probability of falsely concluding that a blank bbservation
represents a "real" signal.
For a particular measurement system, which may include radiochemical
separation:
LLD = 07:54, 10 May 2016 (EDT)07:54, 10 May 2016 (EDT)Mark Hawes 07:54, 10 May 2016 (EDT)
E • V • 2.22 x 106 • Y· exp (-AAt)
Where:
LLD = the 11a priori" lower limit of detection (microCurie per unit
mass or volume),
sb = the standard deviation of the background counting rate or of
the counting rate of a blank sample as appropriate (counts per
minute),
E = the counting efficiency (counts per disintegration),
V = the sample size (units of mass or volume),
2.22 x 106 =the number of disintegrations per minute per microCurie,
Y = the fractional radiochemical yield, when applicable,
A= the radioactive decay constant for the particular radionuclide
(sec- 1), and ·
At = the elapsed time between the midpoint of sample collection and
the time of counting (sec).
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 ! priori (before
the fact) limit representing the capability of a measurement system and
not as an! posteriori (after the fact) limit for a particular measurement.
<2>A batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each batch shall be isolated, and then
thoroughly mixed by a method described in the ODCM to assure
representative sampling.
GE-SREC [41]
TABLE 4.11-1 (Continued)
TABLE NOTATIONS (Continued)
C3>The principal gamma emmiters for which the LLD control applies include
the following radionucli~es: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99,
Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but with an
LLD of S x 10-6 • This list does not mean that only these nuclides are to
be considered. Other gamma peaks that are identifiable, together with
those of the above nuclides, shall also be analyzed and reported in the
Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.4
in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1,
June 1974.
<4>A composite sample is one in which the quantity of liquid sampled is
proportional to the quantity of liquid waste discharged and in which the
method of sampling employed results in a specimen that is representative
of the liquids released.
C5>A continuous release is the discharge of liquid wastes of a nondiscrete
volume, e.g., from a volume of a system that has an input flow during the
continuous release.
<6>To be representative of the quantities and concentrations of radioactive
materials in liquid effluents, samples shall be collected continuously in
proportion to the rate of flow of the effluent stream. Prior to analyses,
all samples taken for the composite shall be thoroughly mixed in order
for the composite sample to be representative of the effluent release.
GE-SREC
[42]
RADIOACTIVE EFFLUENTS
DOSE
CONTROLS
3.11.1.2 In accordance with [plant name] TS 6.8.4.g.4) and 6.8.4.9.5), the
dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials
in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see
Figure 5.1-3) shall be limited:
a. During any calendar quarter to less than or equal to 1.5 mrems to
the whole body and to less th~n or equal to 5 mrems to any organ,
and
b. During any calendar year to less than or equal to 3 mrems to the
whole body and to less than or equal to 10 mrems to any organ.
APPLICABILITY: At all times.
ACTION:
a. With the calculated dose from the release of radioactive materials
in liquid effluents exceeding any of the above limits, prepare
and submit to the Commission within 30 days, pursuant to Control
6.9.2, a Special Report that identifies the cause(s) for exceeding
the limit(s) and defines the corrective actions that have been taken
to reduce the releases and the proposed corrective actions to be
taken to assure that subsequent releases will be in compliance with
the above limits. This Special Report shall also include: (1) the
results of radiological analyses of the drinking water source, and
(2) the radiological impact on finished drinking water supplies with
regard to the requirements of 40 CFR Part 141, Safe Drinking Water
Act.*
b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current
calendar quarter and the current calendar year shall be determined in accordance
with the methodology and parameters in the ODCM at least once per 31 days.
aThe requirements of ACTION a.(l) and (2) are applicable only if drinking water
supply is taken from the receiving water body within 3 miles of the plant
discharge. In the case of river-sited plants this is 3 miles downstream only.
GE-SREC [43]
RADIOACTIVE EFFLUENTS
LIQUID RADWASTE TREATMENT SYSTEM
CONTROLS
3.11.1.3 In accordance with [plant name] TS 6.8.4.g.6), the Liquid Radwaste
Treatment System shall be OPERABLE and appropriate portions of the system shall
be used to reduce releases of radioactivity when the projected doses due to the
liquid effluent, frOll each unit, to UNRESTRICTED AREAS (see Figure S.1-3) would
exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.
APPLICABILITY: At all times.
ACTION:
a. With radioactive liquid waste being discharged without treatment and
in excess of the above limits and any portion of the Liquid Radwaste
Treatment System not in operation, prepare and submit to the Commission
within 30 days, pursuant to Control 6.9.2, a Special Report that
includes the following information:
1. Explanation of why liquid radwaste was being discharged without
treatment, identification of any inoperable equipment or
subsystems, and the reason for the inoperability,
2. Action(s) taken to restore the inoperable equipment to OPERABLE
status, and
3. Summary description of action(s) taken to prevent a recurrence.
b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS
shall be projected at least once per 31 days in accordance with the methodology
and parameters in the ODCM when Liquid Radwaste Treatment Systems are not being
fully utilized.
4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be
considered OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2.
GE-SREC
[44]
RADIOACTIVE EFFLUENTS
3/4.11.1.4 (NOT USED)
GE-SREC [45]
RADIOACTIVE EFFLUENTS
3/4.11.2 GASEOUS EFFLUENTS
DOSE RATE
CONTROLS
3.11.2.1 In accordance with [plant name] TS 6.8.4.g.3) and 7), the dose rate
due to radioactive materials released in gaseous effluents from the site to
areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to
the following:
a. For noble gases: Less than or equal to 500 mrems/yr to the whole
body and less than or equal to 3000 mrems/yr to the skin, and
b. For Iodine-131, for Iodine-133, for tritium, 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.
APPLICABILITY: At all times.
ACTION:
a. With the dose rate(s) exceeding the above limits, immediately restore
the release rate to within the above limit(s).
b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.1.l The dose rate due to noble gases in gaseous effluents shall be
determined to be within the above limits·in accordance with the methodology
and parameters in the ODCM.
4.11.2.1.2 The dose rate due to Iodine-131, Iodine-133, tritium, and all
radionuclides in particulate form with half-lives greater than 8 days in
gaseous effluents shall be determined to be within the above limits in
accordance with the methodology and parameters in the ODCM by obtaining
representative samples and performing analyses in accordance with the sampling
and analysis program specified in Table 4.11-2.
GE-SREC [46]
,C.',>,
I
,":I.D,',
n
,....,
~ ....... .......
TABLE 4.11-2
RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM
SAMPLING
GASEOUS RELEASE TYPE FREQUENCY
1. -Off gas Treatment M
System
MINIMUM
ANALYSIS
FREQUENCY
M
Grab Sample ________ _
TYPE OF
ACTIVITY ANALYSIS
Principal Gamma Emitters(Z)
2. - Containment PURGE ___ - P 3 P
OR VENT Each PURGE( ) Each PURGE(J) Principal GaMa Emitters(Z)
-Grab Samp 1 e
LOWER LIMIT OF
DETECTION (LLD)(l)
(μCi/ml)
lxl0-4
lxl0-4
M H-3 (oxide) lx10~ 6
3. a. (list other M(lT,TS)
M(3)
Principal Gamma Emitters(Z) lxl0-4
release points
where gaseous Grab Sample
effluents are
released from
the facility)
4. All Release Types
as listed in 1.,
2., and 3. above
,~~ ,,~ H-3 (oxide) lxl0-6
c-ontinuous\UJ W I-131 ___ - --------- - lx10- 1z
Continuous< 6>
Charcoal
Sample
w<7)
Particulate
Sample
Principal Gamma Emitters<2>
Continuous< 6> M Gross Alpha
Composite Particulate
Sample
Continuous(G) Q Sr-89, Sr-90
Composite Particulate
Sample
Continuous<6> Noble Gas
Monitor
Noble Gases
Gross Beta or Gamma
lxlQ-11
lxlQ-11
lxlo-11
lxl0-6
TABLE 4.11-2 (Continued)
TABLE NOTATIONS
(l)The LLD is defined, for purposes of these controls, as the smallest
concentration of radioactive material in a sample that will yield a net
count, above system background, that will be detected with 95% probability
with only 5% probability of falsely concluding that a blank observation
represents a 11 real 11 signal.
For a particular measurement system, which may include radiochemical
separation:
4.66 Sb
LLD = ----------------
E • V • 2.22 x 106 • Y • exp (-~t)
Where:
LLD = the "a priori" lower limit of detection (microCurie per unit
mass or volume),
sb = the standard deviation of the background counting rate or of
the counting rate of a blank sample as appropriate (counts per
minute),
E = the counting efficiency (counts per disintegration),
V = the sample size (units of mass or volume),
2.22 x 106 = the number of disintegrations per minute per microCurie,
Y = the fractional radiochemical yield, when applicable,
A= the radioactive decay constant for the particular radionuclide
(sec- 1), and
~t = the elapsed time between the midpoint of sample collection and
the time of counting (sec).
Typical values of E, V, Y, and ~t should be used in the calculation.
It should be recognized that the LLD is defined as an ! priori (before
the fact) limit representing the capability of a measurement system and
not as an! posteriori (after the fact) limit for a particular measurement.
GE-SREC [48]
TABLE 4.11-2 (Continued)
TABLE NOTATIONS (Continued)
(l)The principal gamma emitters for which the LLD control applies include
the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and
Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn;65, Mo-99,
I-131, Cs-134, Cs-137, Ce-141 and Ce-144 in Iodine and particulate
releases. This list does not mean that only these nuclides are to be
considered. Other gamma peaks that are identifiable, together with those
of the above nuclides, shall also be analyzed and reported in the
Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.4
in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1,
June 1974.
<3>sampling and analysis shall also be performed following shutdown, startup,
or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a
1-hour period.
<4>Not applicable.
<5>Tritium grab samples shall be taken at least once per 7 days from the
ventilation exhaust from the spent fuel pool area, whenever spent fuel is
in the spent fuel pool.
(G)The ratio of the sample flow rate to the sampled stream flow rate shall be
known for the time period covered by each dose or dose rate calculation
made in accordance with Controls 3.11.2.1, 3.11.2.2, and 3.11.2.3.
C7>samples shall be changed at least once per 7 days and analyses shall be
completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler.
Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least
7 days following each shutdown, startup, or THERMAL POWER change exceeding
15% of RATED THERMAL POWER within a 1-hour period and analyses shall be
completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
are analyzed, the corresponding LLDs may be increased by a factor of 10.
This requirement does not apply if: (1) analysis shows that the DOSE
EQUIVALENT 1-131 concentration in the reactor coolant has not increased
more than a factor of 3; and (2) the noble gas monitor shows that
effluent activity has not increased more than a factor of 3.
GE-SREC [49]
RADIOACTIVE EFFLUENTS
DOSE - NOBLE GASES
CONTROLS
3.11.2.2 In accordance with [plant name] TS 6.8.4.g.5) and 8), the air dose
due to noble gases released in gaseous effluents, from each unit, to areas at
and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the
following:
a. During any calendar quarter: Less than or equal to 5 mrads for
gamma radiation and less than or equal to 10 mrads for beta radiation,
and
b. During any calendar year: Less than or equal to 10 mrads for gamma
radiation and less than or equal to 20 mrads for beta radiation.
APPLICABILITY: At all times.
ACTION
a. With the calculated air dose from radioactive noble gases in gaseous
effluents exceeding any of the above limits, prepare and submit to
the Commission within 30 days, pursuant to Control 6.9.2, a Special
Report that identifies the cause(s) for exceeding the limit(s) and
defines the corrective actions that have been taken to reduce the
releases and the proposed corrective actions to be taken to assure
that subsequent releases will be in compliance with the above limits.
b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and
current calendar year for noble gases shall be determined in accordance with
the methodology and parameters in the ODCM at least once per 31 days.
GE-SREC [50]
RADIOACTIVE EFFLUENTS
DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIOACTIVE MATERIAL IN
PARTICULATE FORM
CONTROLS
3.11.2.3 In accordance with [plant name] TS 6.8.4.g.5) and 9), the dose to a
MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides
in particulate form with half-lives greater than 8 days in gaseous
effluents released, from each unit, to areas at and beyond the SITE BOUNDARY
{see Figure 5.1-3) shall be limited to the following:
a. During any calendar quarter: Less than or equal to 7.5 mrems to any
organ and,
b. During any calendar year: Less than or equal to 15 mrems to any
organ.
APPLICABILITY: At all times.
ACTION:
a. With the calculated dose from the release of lodine-131, Iodine-133,
tritium, and radionuclides in particulate form with half-lives
greater than 8 days, in gaseous effluents exceeding any of the above
limits, prepare and submit to the Commission within 30 days, pursuant
to Control 6.9.2, a Special Report that identifies the cause{s) for
exceeding the limit{s) and defines the corrective actions that have
been taken to reduce the releases and the proposed corrective actions
to be taken to assure that subsequent releases will be in compliance
with the above limits.
b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and
current calendar year for Iodine-131, Iodine-133, tritium and radionuclides
in particulate form with half-lives greater than 8 days shall be determined
in accordance with the methodology and parameters in the ODCM at least once
per 31 days.
GE-SREC [ 51]
RADIOACTIVE EFFLUENTS
GASEOUS RADWASTE TREATMENT SYSTEM
CONTROLS
3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation.
APPLICABILITY: Whenever the main condenser air ejector (evacuation) system is
in operation.
ACTION:
a. With gaseous radwaste from the main condenser air ejector system
being discharged without treatment for more than 7 days, prepare and
submit to the Commission within 30 days, pursuant to Control 6.9.2, a
Special Report that includes the following information:
1. Identification of the inoperable equipment or subsystems and
the reason for inoperability,
2. Action(s) taken to restore the inoperable equipment to OPERABLE
status, and
3. Summary description of action(s) taken to prevent a
recurrence.
b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4 The readings of the relevant instruments shall be checked every 12
hours when the main condenser air ejector is in use to ensure that the gaseous
radwaste treatment system is functioning.
GE-SREC [52]
RADIOACTIVE EFFLUENTS
VENTILATION EXHAUST TREATMENT SYSTEM
CONTROLS
3.11.2.5 The VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE and
appropriate portions of this system shall be used to reduce releases of
radioactivity when the projected doses in 31 days due to gaseous effluent
releases, from each unit, to areas at and beyond the SITE BOUNDARY
(see Figure 5.1-3) would exceed:
a. 0.2 mrad to air from gamma radiation, or
b. 0.4 mrad to air from beta radiation, or
c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
APPLICABILITY: At all times.
ACTION:
a. With radioactive gaseous waste being discharged without treatment
and in excess of the above limits, prepare and submit to the
Commission within 30 days, pursuant to Control 6.9.2, a Special
Report that includes the following information:
1. Identification of any inoperable equipment or subsystems, and
the reason for the inoperability,
2. Action(s) taken to restore the inoperable equipment to OPERABLE
status, and
3. Summary description of action(s) taken to prevent a recurrence.
b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from each unit to areas at and
beyond the SITE BOUNDARY shall be projected at least once per 31 days in
accordance with the methodology and parameters in the ODCM when the Ventilation
Exhaust Treatment System is not being fully utilized.
4.11.2.5.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM shall be
considered OPERABLE by meeting Controls 3.11.2.1, and either 3.11.2.2 or
3.11.2.3.
GE-SREC [53]
RADIOACTIVE EFFLUENTS
3/4.11.2.6 (NOT USED)
GE-SREC [54]
RADIOACTIVE EFFLUENTS
3/4.11.2.7 (NOT USED)
GE-SREC [55]
RADIOACTIVE EFFLUENTS
MARK I or II CONTAINMENT
CONTROLS
3.11.2.8 VENTING or PURGING of the Mark I or II containment drywell shall be
through the Standby Gas Treatment System.
APPLICABILITY: Whenever the drywell is vented or purged.
ACTION:
a. With the requirements -0f the above control not satisfied, suspend all
VENTING and PURGING of the drywell.
b. The provisions of fontrols 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.8 The containment drywell shall be determined to be aligned for VENTING
or PURGING through the Standby Gas Treatment System within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to
start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during VENTING or PURGING of the
drywell.
GE-SREC (56]
RADIOACTIVE EFFLUENTS
3/4.11.3 (NOT USED)
GE-SREC [57]
RADIOACTIVE EFFLUENTS
3/4.11.4 TOTAL DOSE
CONTROLS
3.11.4 in accordance with [plant name] TS 6.8.4.g.ll), the annual (calendar
year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of
radioactivity and to radiation from uranium fuel cycle sources shall be limited
to less than or equal to 25 mrems to the whole body or any organ, except the
thyroid, which shall be limited to less than or equal to 75 mrems.
APPLICABILITY: At all times.
ACTION:
a. With the calculated doses from the release of radioactive materials
in liquid or gaseous effluents exceeding twice the limits of Control
3.ll.l.2a., 3.ll.l.2b., 3.ll.2.2a., 3.11.2.2b., 3.11.2.3a., or
3.ll.2.3b., calculations shall be made including direct radiation
contributions from the units (including outside storage tanks etc.) to
determine whether the above limits of Control 3.11.4 have been
exceeded. If such is the case, prepare and submit to the Commission
within 30 days, pursuant to Control 6.9.2, a Special Report that
defines the corrective action to be taken to reduce subsequent
releases to prevent recurrence of exceeding the above limits and
includes the schedule for achieving conformance with the above limits.
This Special Report, as defined in 10 CFR 20.405(c), shall include an
analysis that estimates the radiation exposure (dose) to a MEMBER OF
THE PUBLIC from uranium fuel cycle sources, including all effluent
pathways and direct radiation, for the calendar year that includes
the release(s) covered by this report. It shall also describe levels
of radiation and concentrations of radioactive material involved, and
the cause of the exposure levels or concentrations. If the estimated
dose(s) exceeds the above limits, and if the release condition resulting
in violation of 40 CFR Part 190 has not already been corrected,
the Special Report shall include a request for a variance in accordance
with the provisions of 40 CFR Part 190. Submittal of the report
is considered a timely request, and a variance is granted until staff
action on the request is complete.
b. The provisions of Controls 3.0.3 and 3.-0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents
shall be determined in accordance with Controls 4.11.1.2, 4.11.2.2, and
4.11.2.3, and in accordance with the methodology and parameters in the ODCM.
4.11.4.2 Cumulative dose contributions from direct radiation from the units
(including outside storage tanks etc.) shall be determined in accordance with
the methodology and parameters in the ODCM. This requirement is applicable
only under conditions set forth in ACTION a. of Control 3.11.4.
GE-SREC [58]
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING
3/4.12.1 MONITORING PROGRAM
CONTROLS
3.12.1 In accordance with [plant name] TS 6.8.4.h.1), the Radiological
Environmental Monitoring Program shall be conducted as specified in -
Table 3.12-1.
APPLICABILITY: At all times.
ACTION:
a. With the Radiological Environmental Monitoring Program not being
conducted as specified- in Table 3.12-1, prepare and submit to
the Commission, in the Annual Radiological Environmental Operating
Report required by Control 6.9.l.3, a description of the reasons
for not conducting the program as required and the plans for preventing
a recurrence.
b. With the level of radioactivity as the result of plant effluents in
an environmental sampling medium at a specified location exceeding
the reporting levels of Table 3.12-2 when averaged over any calendar
quarter, prepare and submit to the Commission within 30 days, pursuant
to Control 6.9.2, a Special Report that identifies the cause(s)
for exceeding the limit(s) and defines the corrective actions to be
taken to reduce radioactive effluents so that the potential annual
dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits
of Controls 3.11.1.2, 3.11.2.2, or 3.11.2.3. When more than
one of the radionuclides in Table 3.12-2 are detected in the sampling
medium, this report shall be submitted if:
concentration 1 + concentration 2
repor t"1 ng 1e ve 1 l repor t 1ng eve 2 + ••• > 1.0
When radionuclides other than those in Table 3.12-2 are detected and
are the result of plant effluents, this report shall be submitted if
the potential annual dose* to a MEMBER OF THE PUBLIC from all radionuclides
is equal to or greater than the calendar year limits of
Control 3.11.1.2, 3.11.2.2, or 3.11.2.3. This report is not
required if the measured level of radioactivity was not the result
of plant effluents; however, in such an event, the condition shall
be reported and described in the Annual Radiological Environmental
Operating Report required by Control 6.9.1.3.
- The methodology and parameters used to estimate the potential annual dose to
a MEMBER OF THE PUBLIC shall be indicated in this report.
GE-SREC
[59]
RADIOLOGICAL ENVIRONMENTAL MONITORING
CONTROLS
ACTION (Continued)
c. With milk or fresh leafy vegetation samples unavailable from one or
more of the sample locations required by Table 3.12-1, identify
specific locations for obtaining replacement samples and add them
within 30 days to the Radiological Environmental Monitoring Program
given in the ODCM. The specific locations from which samples were
unavailable may then be deleted from the monitoring program. Pursuant
to Control 6.14, submit in the next Semiannual Radioactive Effluent
Release Report documentation for a change in the ODCM including a
revised figure(s) and table for the ODCM reflecting the new
location(s) with supporting information identifying the cause of
the unavailability of samples and justifying the selection of the
new location(s) for obtaining samples.
d. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected
pursuant to Table 3.12-1 from the specific locations given in the table and
figure(s) in the ODCM, and shall be analyzed pursuant to the requirements of
Table 3.12-1 and the detection capabilities required by Table 4.12-1.
GE·SREC [60]
a
.m,•,
- ID m
n
,.....,
.°....._.'..
EXPOSURE PATHWAY
AND/OR SAMPLE
TABLE 3.12-1
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM*
NUMBER OF
REPRESENTATIVE
SAMPLES AND
SAMPLE LOCATIONS(l)
SAMPLING AND
COLLECTION FREQUENCY
1. Direct Radiation<2> Forty routine monitoring stations Quarterly.
(DR1-DR40) either with two or more
dosimeters or with one instrument
for measuring and recording dose
rate continuously, placed as
follows:
An inner ring of stations, one in
each meteorological sector in the
general area of the SITE BOUNDARY
(DR1-DR16);
An outer ring of stations, one in
each meteorological sector in
the 6- to 8-km range from the
site (DR17-DR32); and
The balance of the stations
(DR33-DR40) to be placed in
special interest areas such
as population centers, nearby
residences, schools, and in one
or two areas to serve as control
stations.
TYPE ANO FREQUENCY
OF ANALYSIS
Gamma dose quarterly.
•The number, media, frequency, and location of samples may vary from site to site. This table pre's ents an
acceptable minimum program for a site at which each entry is applicable. Local site characteristics must be
examined to determine if pathways not covered by this table may significantly contribute to an individual's
dose and should be included in the sample program. The code letters in parentheses, e.g., ORI, Al, provide
one way of defining sample locations in this control that can be used to identify the specific locations
in the map(s) and table in the OOCM.
........
°' N
........
I:')
""I '
":a'
"n" '
EXPOSURE PATHWAY
AND/OR SAMPLE
2. Airborne
Radioiodine and
Particulates
3. Waterborne
a. Surface(S)
b. Ground
TABLE 3.12-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
NUMBER OF
REPRESENTATIVE
SAMPLES AND
SAMPLE LOCATIONS(l)
Samples from five locations
(Al-AS):
Three samples (Al-A3) from
close to the three SITE
BOUNDARY locations, in
different sectors, of the
highest calculated annual
average ground-level D/Q;
One sample (A4) from the
vicinity of a community
having the highest calculated
annual average groundlevel
D/Q; and
One sample (AS) from a control
location, as for example 15 to
30 km distant and in the least
prevalent wind direction.
SAMPLING AND
COLLECTION FREQUENCY
Continuous sampler operation
with sample collection
weekly, or more
frequently if required by
dust loading.
One sample upstream (Wal). Composite sample over
One sample downstream (Wa2). 1-month period. (G)
Samples from one or two sources Quarterly.
(Wbl, Wb2), only if likely to be
affected<7>.
TYPE AND FREQUENCY
OF ANALYSIS
Radioiodine Cannister:
I-131 analysis weekly.
Particulate Sampler:
Gross beta radioactivity
analysis following
filter change;(J) and 4
gamma isotopic analysis< )
of composite (by
location) quarterly.
Gamma isotopic analysis<4>
monthly. Composite for
tritium analysis quarterly.
Gamma isotopic<4> and
tritium analysis quarterly
G)
m
I
"::0' m
n
r-1
O'I
w
L....J
EXPOSURE PATHWAY
AND/OR SAMPlE
TABLE 3.12-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
NUMBER OF
REPRESENTATIVE
SAMPLES AND
SAMPLE LOCATIONS(l)
SAMPLING ANO
COLLECTION FREQUENCY
3. Waterborne (Continued)
c. Drinking
d. Sediment
from
Shoreline
4. Ingestion
a. Milk
One sample of each of one to
three (Wcl - Wc3) of the nearest
water supplies that could be
affected by its discharge.
One sample from a control
location (Wc4).
One sample from downstream area
with existing or potential
recreational value (Wdl).
Samples from milking animals
in three locations (lal - Ia3)
within 5 km distance having the
highest dose potential. If
there are none, then one
sample from milking animals
in each of three areas
(lal - la3) between 5 to
8 km distant where doses
are calculated to bf8~reater
than 1 mrem per yr. One
sample from milking animals
at a control location (la4),
15 to 30 km distant and in the
least prevalent wind direction.
Composite sample over
2-week period(6) when
1-131 analysis is performed;
monthly composite
otherwise.
Semiannually.
Semimonthly when
animals are on pasture;
monthly at other times.
TYPE AND FREQUENCY
OF ANALYSIS
I-131 analysis on each
composite when the dose
calculated for the consumption
of the water
is greater than 1 mrem
per year<8>. Composite
for gross beta and gannna
isotopic analyses<4>
monthly. Composite for
tritium analysis quarterly.
Gamma isotopic analysis<4>
semiannually.
Gamma isotopic<4> and
1-131 analysis semimonthly
when animals
are on pasture; monthly
at other times.
~
I
Cit
,~,,
"
,....,
0\
.i::.
1--1
EXPOSURE PATHWAY
AND/OR SAMPLE
4. Ingestion (Continued)
b. Fish and
Invertebrates
c. Food
Products
TABLE 3.12-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
NUMBER OF
REPRESENTATIVE
SAMPLES AND
SAMPLE LOCATIONS(l)
One sample of each commercially
and recreationally important
species in vicinity of plant
discharge area. (lbl - lb~>·
One sample of same species in
areas not influenced by plant
discharge (lblO - lb ).
One sample of each principal
class of food products from
any area that is irrigated
by water in which liquid
plant wastes have been
discharged (Icl - le~>·
Samples of three different
kinds of broad leaf vegetation
grown nearest each of
two different offsite locations
of highest predicted
annual average ground level
D/Q if milk sampling is not
performed (lclO - Icl3).
One sample of each of the
similar broad leaf vegetation
grown 15 to 30 km distant
in the least prevalent
wind direction if milk sampling
is not performed (lc20 -
lc23).
SAMPLING AND
COLLECTION FREQUENCY
Sample in season, or
semiannually if they
are not seasonal.
At time of harvest<9>.
Monthly during
growing season.
Monthly during
growing season.
TYPE AND FREQUENCY
OF ANALYSIS
Gamma isotopic analysis(4)
on edible portions.
Gamma isotopic analyses<4>
on edible portion.
Gamma isotopic<4> and 1-131
analysis.
Gamma isotopic<4> and 1-131
analysis.
TABLE 3.12-1 (Continued)
TABLE NOTATIONS
(1) Specific parameters of distance and direction sector from the centerline
of one reactor, and additional description where pertinent, shall be provided
for each and every sample location in Table 3.12-1 in a table and
figure(s) in the ODCM. Refer to NUREG-0133, "Preparation of Radiological
Effluent Technical Specifications for Nuclear Power Plants," October 1978,
and to Radiological Assessment Branch Technical Position, Revision 1,
November 1979. Deviations are permitted from the required sampling
schedule if specimens are unobtainable due to circumstances such as
hazardous conditions, seasonal unavailability, and malfunction of automatic
sampling equipment. If specimens are unobtainable due to sampling
equipment malfunction, eff~rt shall be made to complete corrective action
prior to the end of the next sampling period. All deviations from the
sampling schedule shall be documented in the Annual Radiological Environmental
Operating Report pursuant to Control 6.9.1.3. It is recognized
that, at times, it may not be possible or practicable to continue to
obtain samples of the media of choice at the most desired location or
time. In these instances suitable alternative media and locations may be
chosen for the particular pathway in question and appropriate substitutions
made within 30 days in the Radiological Environmental Monitoring Program
given in the ODCM. Pursuant to Control 6.14, submit in the next
Semiannual Radioactive Effluent Release Report documentation for a change
in the ODCM including a revised figure(s) and table for the ODCM reflecting
the new location(s) with supporting information identifying the cause
of the unavailability of samples for the pathway and justifying the selection
of the new location(s) for obtaining samples.
(2) One or more instruments, such as a pressurized ion chamber, for measuring
and recording dose rate continuously may be used in place of, or in addition
to, integrating dosimeters. For the purposes of this table, a
thermoluminescent dosimeter (TLD) is considered to be one phosphor; two
or more phosphors in a packet are considered as two or more dosimeters.
Film badges shall not be used as dosimeters for measuring direct radiation.
(The 40 stations is.not an absolute number. The number of direct radiation
monitoring stations may be reduced according to geographical limitations;
e.g., at an ocean site, some sectors will be over water so that the number
of dosimeters may be reduced accordingly. The frequency of analysis or
readout for TLD systems will depend upon the characteristics of the specific
system used and should be selected to obtain optimum dose information
with minimal fading.)
(3) Airborne particulate sample filters shall be analyzed for gross beta
radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and
thoron daughter decay. If gross beta activity in air particulate samples
is greater than 10 times the yearly mean of control samples, gamma
isotopic.analysis shall be performed on the individual samples.
GE-SREC [65]
TABLE 3.12-1 (Continued)
TABLE NOTATIONS (Continued)
(4) Gamma isotopic analysis means the identification and quantification of
gamma-emitting radionuclides that may be attributable to the effluents
from the facility.
(5) The "upstream sample" shall be taken at a distance beyond significant
influence of the discharge. The 11 downstream11 sample shall be taken in an
area beyond but near the mixing zone. "Upstream" samples in an estuary
must be taken far enough upstream to be beyond the plant influence. Salt
water shall be sampled only when the receiving water is utilized for
recreational activities.
(6) A composite sample is one in which the quantity (aliquot) of liquid sampled
is proportional to the quantity of flowing liquid and in which the method
of sampling employed results in a specimen that is representative of the
liquid flow. In this program composite sample aliquots shall be collected
at time intervals that are very short (e.g., hourly) relative to the
compositing period (e.g., monthly) in order to assure obtaining a
representative sample.
(7) Groundwater samples shall be taken when this source is tapped for drinking
or irrigation purposes in areas where the hydraulic gradient or recharge
properties are suitable for contamination.
(8) The dose shall be calculated for the maximum organ and age group, using
the methodology and parameters in the ODCM.
(9) If harvest occurs more than once a year, sampling shall be performed
during each discrete harvest. If harvest occurs continuously, sampling
shall be monthly. Attention shall be paid to including samples of
tuberous and root food products.
GE-SREC [66]
G'>
'"I
"::0' n""
......,
O"I
.......
L.....I
ANALYSIS
Mn-54
Fe-59
Co-58
Zn-65
Zr-Nb-95
1-131
Cs-134
Ba-La-140
TABLE 3.12-2
REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES
REPORTING LEVELS
WATER AIRBORNE PARTICULATE FISH MILK
(pCi/1) OR GASES (pCi/m3) (pCi/kg, wet) (pCi/1)
20,000*
1,000 30,000
400 10,000
1,000 30,000
300 10,000
300 20,000
400
2** 0.9 3
30 10 1,000 60
50 20 2,000 70
200 300
FOOD PRODUCTS
(pCi/kg, wet)
100
1,000
2,000
- For drf nkf ng water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value
of 30,000 pCf/1 may be used.
- If no drfnkfng water pathway exists, a value of 20 pCi/1 may be used.
I:) TABLE 4.12-1
"' DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS(!) (l) I
";:a'
"n ' LOWER LIMIT OF DETECTION ~LLD}( 3 )
WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT
ANALYSIS (pCi/1) OR GASES (pCi/m3) (pCi/kg, wet) (pCi/l) (pCi/kg, wet) (pCi/kg, dry)
Gross Beta 4 0.01
H-3 2000*
Mn-54 15 130
Fe-59 30 260
Co-58,60 15 130
....,
CJ'I Zn-65 30 260
CX>
~
Zr-Nb-95 15
1-131 1** 0.07 1 60
Cs-134 15 0.05 130 15 60 150
Cs-137 18 0.06 150 18 80 180
Ba-La-140 15 15
- If no drinking water pathway exists, a value of 3000 pCi/1 may be used.
- If no drinking water pathway exists, a value of 15 pCi/1 may be used.
TABLE 4.12-1 (Continued)
TABLE NOTATIONS
(l)This list does not mean that only these nuclides are to be considered.
Other peaks that are identifiable, together with those of the above
nuclides, shall also be analyzed and reported in the Annual Radiological
Environmental Operating Report pursuant to Control 6.9.1.3.
(2)Required detection capabilities for thermoluminescent dosimeters used
for environmental measurements shall be in accordance with the recommendations
(3)The LLD is defined, for purposes of these controls, as the smallest
concentration of radioactive material in a sample that will yield a net
count, above system background, that will be detected with 95% probability
with only 5% probability of falsely concluding that a blank observation
represents a "real" signal.
For a particular measurement system, which may include radiochemical
separation:
4.66 Sb
LLD = ---------------
E • V • 2.22 • Y • exp(-~t)
Where:
LLD = the "a priori" lower limit of detection (picoCuries per unit
mass or volume),
E
v
= the standard deviation of the background counting rate or of the
counting rate of a blank sample as appropriate (counts per minute),
= the counting efficiency (counts per disintegration),
= the sample size (units of mass or volume),
2.22 = the number of disintegrations per minute per picoCurie,
Y = the fractional radiochemical yield, when applicable,
A = the radioactive decay constant for the· particular radionuclide
(sec- 1), and
At = the elapsed time between environmental collection, or end of
the sample collection period, and time of counting (sec).
Typical values of E, V, Y, and At should be used in the calc·ulation.
GE-SREC [69)
TABLE 4.12-1 (Continued)
TABLE NOTATIONS (Continued)
It should be recognized that the LLD is defined as an ! priori (before the
fact) limit representing the capability of a measurement system and not as
an! posteriori (after the fact) limit for a particular measuremeQt.
Analyses shall be performed in such a manner that the stated LLDs will be
achieved under routine conditions. Occasionally background fluctuations,
unavoidable small sample sizes, the presence of interfering nuclides, or
other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors shall be identified and described
in the Annual Radiological Environmental Operating Report pursuant to
Control 6.9.1.3.
GE-SREC [70]
RADIOLOGICAL ENVIRONMENTAL MONITORING
3/4.12.2 LAND USE CENSUS
CONTROLS
3.12.2 In accordance with [plant name] TS 6.8.4.h.2), a Land Use Census shall
be conducted and shall identify within a distance of 8 km (5 miles) the
location in each of the 16 meteorological sectors of the nearest milk animal,
the nearest residence, and the nearest garden* of greater than 50 m2 (500 ft2 )
producing broad leaf vegetation. [For elevated releases as defined in Regulatory
Guide 1.111, Revision 1, July 1977, the Land Use Census shall also
identify within a distance of 5 km (3 miles) the locations in each of the
16 meteorological sectors of all milk animals and all gardens of greater than
50 m2 producing broad leaf vegetation.]
· APPLICABILITY: At all times.
ACTION:
a. With a Land Use Census identifying a location(s) that yields a·
calculate1 dose or dose commitment greater than the values currently
being calculated in Control 4.11.2.3, pursuant to Control 6.9.1.4,
identify the new location(s) in the next Semiannual Radioactive
Effluent Release Report.
b. With a Land Use Census identifying a location(s) that yields a·
calculated dose or dose commitment (via the same exposure pathway)
20% greater than at a location from which samples are currently
being obtained in accordance with Control 3.12.1, add the new
location(s) within 30 days to the Radiological Environmental Monitoring
Program given in the ODCM. The sampling location(s), excluding
the control station location, having the lowest calculated dose
or dose commitment(s), via the same exposure pathway, may be deleted
from this monitoring program after [October 31] of the year in which
this Land Use Census was conducted. Pursuant to Control 6.14,
submit in the next Semiannual Radioactive Effluent Release Report
documentation for a change in the ODCM including a revised figure(s)
and table(s) for the ODCM reflecting the new location(s) with information
supporting the change in sampling locations.
c. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
- Broad leaf vegetation sampling of at least three different kinds of vegetation
may be performed at the SITE BOUNDARY in each of two different direction
sectors with the highest predicted D/Qs in lieu of the garden census.
Controls for broad leaf vegetation sampling in Table 3.12-1, Part 4.c., shall
be followed, including analysis of control samples.
GE-SREC [71]
RADIOLOGICAL ENVIRONMENTAL MONITORING
SURVEILLANCE REQUIREMENTS 4.12.2 The Land Use Census shall be conducted during the growing season at
least once per 12 months using that information that will provide the best
results, such as by a door-to-door survey, aerial survey, or by conS'Ulting
local agriculture authorities. The results of the Land Use Census shall be
included in the Annual Radiological Environmental Operating Report pursuant to
Control 6.9.1.3.
GE-SREC [72]
RADIOLOGICAL ENVIRONMENTAL MONITORING
3/4.12.3 INTERLABORATORY COMPARISON PROGRAM
CONTROLS
3.12.3 In accordance with [plant name] TS 6.8.4.h.3), analyses shall be
performed on all radioactive materials, supplied as part of an Interlaboratory
Comparison Program that has been approved by the Commission, that correspond to
samples required by Table 3.12-1.
APPLICABILITY: At all times.
ACTION:
a. With analyses not being performed as required above, report the
corrective actions taken to prevent a recurrence to the Commission
in the Annual Radiological Environmental Operating Report pursuant
to Control 6.9.1.3.
b. The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM.
A summary of the results obtained as part of the above required Interlaboratory
Comparison Program shall be included in the Annual Radiological Environmental
Operating Report pursuant to Control 6.9.1.3.
GE-SREC
[73]
GE-SREC
BASES FOR
SECTIONS 3.0 AND 4.0
CONTROLS
AND
SURVEILLANCE REQUIREMENTS
-NOTE
The BASES contained in succeeding paqes summarize
the reasons for the Controls in Sect1ons 3.0
and 4.0, but are not part of these Controls.
[74]
INSTRUMENTATION
BASES
3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
The radioactive liquid effluent instrumentation is provided to monitor
and control, as applicable, the releases of radioactive materials in liquid
effluents during actual or potential releases of liquid effluents. The
Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in
accordance with the methodology and parameters in the ODCM to ensure that the
alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The
OPERABILITY and use of this instrumentation is consistent with the requirements
of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
The radioactive gaseous effluent instrumentation is provided to monitor and
control, as applicable, the releases of radioactive materials in gaseous effluents
during actual or potential releases of gaseous effluents. The Alarm/Trip
Setpoints for these instruments shall be calculated and adjusted in accordance
with the methodology and parameters in the ODCM to ensure that the alarm/trip
will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY
and use of this instrumentation is consistent with the requirements of General
Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
GE-SREC [75]
3/4.11 RADIOACTIVE EFFLUENTS
BASES
3/4.11.1 LIQUID EFFLUENTS
3/4.11.1.1 CONCENTRATION
This control is provided to ensure that the concentration of radioactive
materials released in liquid waste effluents to UNRESTRICTED AREAS will be less
than the concentration levels specified in 10 CFR Part 20, Appendix B, Table
II, Column 2. This limitation provides additional assurance that the levels of
radioactive materials in bodies of water in UNRESTRICTED AREAS will result in
exposures within: (1) the Section II.A design objectives of Appendix I, 10 CFR
Part SO, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.106(e)
· to the population. The concentration limit for dissolved or entrained noble
gases is based upon the assumption that Xe-13S is the controlling radioisotope
and its MPC in air (submersion) was converted to an equivalent concentration in
water using the methods described in International Commission on Radiological
Protection (ICRP) Publication 2.
This control applies to the release of radioactive materials in liquid
effluents from all units at the site.
The required detection capabilities for radioactive materials in liquid
waste samples are tabulated in terms of the lower limits of detection (LLDs).
Detailed discussion of the LLD, and other detection limits can be found in
Currie, L. A., "Lower Limit of Detection: Definition and Elaboration of a
Proposed Position for Radiological Effluent and Environmental Measurements,"
NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300.
3/4.11.1.2 DOSE
This control is provided to implement the requirements of Sections II.A,
III.A, and IV.A of Appendix I, 10 CFR Part SO. The Control implements the
guides set forth in Section II.A of Appendix I. The ACTION statements provide
the required operating flexibility and at the same time implement the guides
set forth in Section IV.A of Appendix I to assure that the releases of radioactive
material in liquid effluents to UNRESTRICTED AREAS will be kept "as low
as is reasonably achievable." Also, for fresh water sites with drinking water
supplies that can be potentially affected by plant operations, there is
reasonable assurance that the operation of the facility will not result in
radionuclide concentrations in the finished drinking water that are in excess
of the requirements of 40 CFR Part 141. The dose calculation methodology and
parameters in the ODCM implement the requirements in Section III.A of
Appendix I that conformance with the guides of Appendix I be shown by calculational
procedures based on models and data, such that the actual exposure of
a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially
underestimated. The equations specified in the ODCM for calculating the
doses due to the actual release rates of radioactive materials in liquid
effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of
GE-SREC [76]
RADIOACTIVE EFFLUENTS
BASES
DOSE (Continued)
Reactor Effluents for the Purpose of Evaluating Compliance with 10 CF~ Part SO,
Appendix I, 11 Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating
Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases
for the Purpose of Implementing Appendix I," April 1977.
This control applies to the release of radioactive materials in liquid
effluents from each unit at the site. For units with shared Radwaste Systems,
the liquid effluents from the shared system are to be proportioned among the
units sharing that system .
. 3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM
The OPERABILITY of the Liquid Radwaste Treatment System ensures that this
system will be available for use whenever liquid effluents require treatment
prior to release to the environment. The requirement that the appropriate portions
of this system be used when specified provides assurance that the releases of
radioactive materials in liquid effluents will be kept "as low as is reasonably
achievable." This control implements the requirements of 10 CFR 50.36a,
General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design
objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified
limits governing the use of appropriate portions of the Liquid Radwaste Treatment
System were specified as a suitable fraction of the dose design objectives set
forth in Section II.A of Appendix I, 10 CFR Part 50 for liquid effluents.
This control applies to the release of radioactive materials in liquid
effluents fr~m·each unit at the site. For units with shared Radwaste Systems,
the liquid effluents from the shared system are to be proportioned among the
units sharing that system.
GE-SREC [77]
RADIOACTIVE EFFLUENTS
BASES
3/4.11.2 GASEOUS EFFLUENTS
3/4.11.2.1 DOSE RATE
This control is provided to ensure that the dose at any time at and
beyond the SITE BOUNDARY from gaseous effluents from all units on the site
will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS.
The annual dose limits are the doses associated with the concentrations of
10 CFR Part 20, Appendix B, Table II, Column I. These limits provide reasonable
assurance that radioactive material discharged in gaseous effluents will not
result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA,
either within or outside the SITE BOUNDARY, to annual average concentrations
exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20
-(10 CFR Part 20.106(b)). For MEMBERS OF THE PUBLIC who may at times be within
the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be
sufficiently low to compensate for any increase in the atmospheric diffusion
factor above that for the SITE BOUNDARY. Examples of calculations for such
MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given
in the ODCM. The specified release rate limits restrict, at all times, the
corresponding gamma and beta dose rates above background to a MEMBER OF THE
PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/year
to the whole body or to less than or equal to 3000 mrems/year to the skin.
These release rate limits also restrict, at all times, the corresponding
thyroid dose rate above background to a child via the inhalation pathway to
less than or equal to 1500 mrems/year.
This control applies to the release of radioactive materials in gaseous
effluents from all units at the site.
The required detection capabilities for radioactive material in gaseous
waste samples are tabulated in terms of the lower limits of detection (LLDs).
Detailed discussion of the LLD, and other detection limits can be found in
Currie, L. A., "Lower Limit of Detection: Definition and Elaboration of a
Proposed Position for Radiological Effluent and Environmental Measurements,"
NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300.
3/4.11.2.2 DOSE - NOBLE GASES
This control is provided to implement the requirements of Sections II.B,
III.A and IV.A of Appendix I, 10 CFR Part 50. The control implements the
guides set forth in Section I.B of Appendix I. The ACTION statements provide
the required operating flexibility and at the same time implement the guides
set forth in Section IV.A of Appendix I to assure that the releases of radioactive
material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low
as is reasonably achievable." The Surveillance Requirements implement the
requirements in Section III.A of Appendix I that conformance with the guides of
Appendix I be shown by calculational procedures based on models and data such
that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways -
is unlikely to be substantially underestimated. The dose calculation
GE-SREC [78]
RADIOACTIVE EFFLUENTS
BASES
DOSE-NOBLE GASES (Continued)
methodology and parameters established in the ODCM for calculating the doses
due to the actual release rates of radioactive noble gases in gaseous effluents
are consistent with the methodology provided in Regulatory Guide 1.109,
"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents
for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,11
Revision I, October 1977 and Regulatory Guide 1.111, "Methods for Estimating
Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases
from Light-Water Cooled Reactors, 11 Revision l, July 1977. The ODCM equations
provided for determining the air doses at and beyond the SITE BOUNDARY are
based upon the historical average atmospheric conditions.
This control applies to the release of radioactive materials in gaseous
effluents from each unit at the site. For units with shared Radwaste Treatment
Systems, the gaseous effluents from the shared system are proportioned among
the units sharing that system.
3/4.11.2.3 DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIOACTIVE MATERIAL
IN PARTICULATE FORM
This control is provided to implement the requirements of Sections II.C,
III.A and IV.A of Appendix I, 10 CFR Part 50. The Controls are the guides set
forth in Section II.C of Appendix I. The ACTION statements provide the
required operating flexibility and at the same time implement the guides set
forth in Section IV.A of Appendix I to assure that the releases of radioactive
materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is
reasonably achievable." The ODCM calculational methods specified in the
Surveillance Requirements implement the requirements in Section III.A of
Appendix I that conformance with the guides of Appendix I be shown by calculational
procedures based on models and data such that the actual exposure of a
MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially
underestimated. The ODCM calculational methodology and parameters for
calculating the doses due to the actual release rates of the subject materials
are consistent with the methodology provided in Regulatory Guide 1.109,
"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents
for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"
Revision 1, October 1977 and, Regulatory Guide 1.111, "Methods for Estimating
Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases
from Light-Water-Cooled Reactors," Revision 11 July 1977. These equations also
provide for determining the actual doses based upon the historical average
atmospheric conditions. The release rate controls for Iodine-131 Iodine-133,
tritium, and radionuclides in particulate form with half-lives greater than
8 days are dependent upon the existing radionuclide pathways to man in the
GE-SREC [79]
RADIOACTIVE EFFLUENTS
BASES
DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE
FORM (Continued)
areas at and beyond the SITE BOUNDARY. The pathways that were examined in the
development of the calculations were: (1) individual inhalation of airborne
radionuclides, (2) deposition of radionuclides onto green leafy vegetation
with subsequent consumption by man, (3) deposition onto grassy areas where milk
animals and meat producing animals graze with consumption of the milk and meat
by man, and (4) deposition on the ground with subsequent exposure of man.
This control applies to the release of radioactive materials in gaseous
effluents from each unit at the site. For units with shared Radwaste Treatment
Systems, the gaseous effluents from the shared system are proportioned among
the units sharing that system.
3/4.11.2.4 ANO 3/4.11.2.5 GASEOUS RAOWASTE TREATMENT SYSTEM AND VENTILATION
EXHAUST TREATMENT SYSTEM
The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST
TREATMENT SYSTEM ensures that the systems will be available for use whenever
gaseous effluents require treatment prior to release to the environment. The
requirement that the appropriate portions of these systems be used, when specified,
provides reasonable assurance that the releases of radioactive materials in
gaseous effluents will be kept "as low as is reasonably achievable. 11 This
control implements the requirements of 10 CFR 50.36a, General Design
Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given
in Section 11.D of Appendix I to 10 CFR Part 50. The specified limits governing
the use of appropriate portions of the systems were specified as a suitable
fraction of the dose design objectives set forth in Sections 11.B and II.C of
Appendix I, 10 CFR Part 50, for gaseous effluents.
This control applies to the release of radioactive materials in gaseous
effluents from each unit at the site. For units with shared Radwaste Treatment
Systems, the gaseous effluents from the shared system are proportioned among
the units sharing that system.
GE-SREC [80]
RADIOACTIVE EFFLUENTS
BASES
3/4 11.2.6 NOT USED
3/4 11.2.7 NOT USED
3/4.11.2.8 MARK I CONTAINMENT
This specification provides reasonable assurance that releases from drywell
purging operations will not exceed the annual dose limits of 10.CFR part 20
for unrestricted areas.
3/4.11.3 NOT USED
3/4.11.4 TOTAL DOSE
This control is provided to meet the dose limitations of 10 CFR Part 190
that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The control
requires the preparation and submittal of a Special Report whenever the
calculated doses due to releases of radioactivity and to radiation from
uranium fuel cycle sources exceed 25 mrems to the whole body or any organ,
except the thyroid, which shall be limited to less than or equal to 75 mrems.
For sites containing up to four reactors, it is highly unlikely that the
resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR
Part 190 if the individual reactors remain within twice the dose design
objectives of Appendix I, and if direct radiation doses from the units
GE-SREC [81]
RADIOACTIVE EFFLUENTS
BASES
TOTAL DOSE (Continued)
(including outside storage tanks, etc.) are kept small. The Special Report
will describe a course of action that should result in the limitation of the
annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.
For the purposes of the Special Report, it may be assumed that the dose
commitment to the MEMBER of the PUBLIC from other uranium fuel cycle sources is
negligible, with the exception that dose contributions from other nuclear fuel
cycle facilities at the same site or within a radius of 8 km must be
considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the
requirements of 40 CFR Part 190, the Special Report with a request for a
variance (provided the release conditions resulting in violation of 40 CFR Part
190 have not already been corrected), in accordance with the provisions of 40
CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and
fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed.
The variance only relates to the limits of 40 CFR Part 190, and does
not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 3.11.1.l and 3.11.2.1. An individual is not
considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged
in carrying out any operation that is part of the nuclear fuel cycle.
GE-SREC [82]
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING
BASES
3/4.12.1 MONITORING PROGRAM
The Radiological Environmental Monitoring Program required by tRis
control provides representative measurements of radiation and of radioactive
materials in those exposure pathways and for those radionuclides that lead to
the highest potential radiation exposure of MEMBERS OF THE PUBLIC resulting
from the plant operation. This monitoring program implementsSection IV.B.2
of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological
Effluent Monitoring Program by verifying that the measurable concentrations of
radioactive materials and levels of radiation are not higher than expected on
the basis of the effluent measurements and the modeling of the environmental
exposure pathways. Guidance for this monitoring program is provided by the
Radiological Assessment Branch Technical Position on Environmental Monitoring,
Revision 1, November 1979. The initially specified monitoring program will be
effective for at least the first 3 years of commercial operation. Following
this period. program changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are
tabulated in terms of the lower limits of detection (LLDs). The LLDs required
by Table 4.12-1 are considered optimum for routine environmental measurements
in industrial laboratories. It should be recognized that the LLD is defined
as an! priori (before the fact) limit representing the capability of a measurement
system and not as an! posteriori (after the fact) limit for a particular
measurement.
Detailed discussion of the LLD, and other detection limits, can be found
in Currie, L. A., "Lower Limit of Detection: Definition and Elaboration of a
Proposed Position for Radiological Effluent and Environmental Measurements,"
NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300.
3/4.12.2 LAND USE CENSUS
This control is provided to ensure that changes in the use of areas at and
beyond the SITE BOUNDARY are identified and that modifications to the
Radiological Environmental Monitoring Program given in the ODCM are made if
required by the results of this census. The best information from the
door-to-door survey, from aerial survey or from consulting with local agricultural
authorities shall be used. This census satisfies the requirements
of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to
gardens of greater than 50 m2 provides assurance that significant exposure
pathways via leafy vegetables will be identified and monitored since a garden
of this size is the minimum required to produce the quantity (26 kg/year) of
leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.
To determine this minimum garden size, the following assumptions were made:
(1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar
to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2 •
GE-SREC [83]
RADIOLOGICAL ENVIRONMENTAL MONITORING
BASES
3/4.12.3 INTERLABORATORY COMPARISON PROGRAM
The requirement for participation in an approved Interlaboratory Comparison
Program is provided to ensure that independent checks on the precision and
accuracy of the measurements of radioactive materials in environmental sample
matrices are performed as part of the quality assurance program for environmental
monitoring in order to demonstrate that the results are valid for the purposes
of Section IV.B.2 of Appendix I to 10 CFR Part 50.
GE-SREC [84]
APPENDIX A
Rad;olog;cal Assessment Branch Technical Position,
Revision 1, November 1979
[85]
Branch Technical Position
Background
Revision l
November 1979
Regulatory Guide 4.8 1 Environmental Technical Specifications for Nuclear Power
Plants, issued for comment fn December 1975, is being revised based on CDftlllents
received. The Radiological Assessment Branch issued a Branch Position on the
radiological portion of the environmental monitoring program in March, 1978.
The position was formulated by an NRC working group which considered comments
received after the issuance of the Regulatory Guide 4.8. This is Revision 1
of that Branch Position paper. The changes ar1 marked by a vertical line in
the right margin. The most significant change is the increase in direct
radiation measurement stations.
10 CFR Parts 20 and 50 requir1 that radiological environmental monitoring
programs be established to provide data on measurabl1 levels of radiation and
radioactive materials in the site environs. In addition, Appendix I to 10 CFR Part 50 requires that the relationship between quantities of radioactive
material released in effluents during normal operation, including anticipated
operational occurrences, and resultant radiation doses to individuals from
principals pathways of exposure be evaluated. These programs should be conducted
to verify the effectiveness of in-plant measures used for controlling
the release of radioactive materials. Surveillance should be established to
identify changes in the use of unrestricted areas (1.g., for agricultrual
purposes) to provide a basis for modifications in th• monitoring programs for
evaluating doses to individuals from principal pathways of exposure. NRC
Regulatory Guide 4.1, Rev. l, uPrograms for Monitoring Radioactivity in the
·environs of Nuclear Power Plants," provides an acceptable basis for the design
of programs to monitor levels of radiation and radioactivity in the station
environs.
This position sets forth an example of an acceptable minimum radiological
monitoring program. Local site characteristics •ust be examined to determine
if pathways not covered by this guide may significantly contribute to an
individual's dose and should be included in the sampling program.
[86]
Program Reouirements
2
AN ACCEPTABLE RADIOLOGICAL
ENVIRONMENTAL MONITORING PROGRAM
Environmental samples shall be collected and analyzed according to Table 1 at
locations shown in Figure l. 1 Analytical techniques used shall be such that
the detection capabilities in Table 2 are achieved.
The results of the radiological environmental monitoring are intended to
supr·~ment the results of the radiological effluent •onitoring by verifying
that-:he measurable concentrations of radioactive materials and levels of
radiation are not higher than expected on the basis of the effluent measurements
and modeling of the environmental exposure pathways. Thus, the specified
environmental monitoring program provides measurements of radiation and of radioactive
materials in those exposure pathways and for those radionuclides which
lead to the highest potential radiation exposures of individuals resulting from
the station operation. The initial radiological environmental monitoring program
should be conducted for the first three years of con111ercial operation (or other
period corresponding to a maximum burnup in the initial core cycle). Following
this period, program changes may be proposed based on operational experience.
The specified detection capabilities are state-of-the-art for routine environmental
measurements in industrial laboratories.
Deviations are permitted from the required sampling schedule if specimens are
unobtainable due to hazardous conditions, seasonal unavailability, malfunction
of automatic sampling equipment and other legitimate reasons. If specimens
are unobtainable due to sampling equipment malfunction, every effort shall be
made to complete corrective action prior to the end of the next sampling
period. All deviations from the sampling schedule shall be documented in the
annual report.
The laboratories of the licensee and licensee's contractors which perform
analyses shall participate in the Environmental Protection Agency's (EPA's)
Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck)
Program or equivalent program. This participation shall include 111 of the
determinations (sample medium-radionuclide combination) that are offered by
EPA and that also are included in the monitoring program. The results of
analysis of these crosscheck samples shall be included in the annual report.
The participants in the EPA crosscheck program may provide their EPA program
code so that the NRC can review the EPA's participant data directly in lieu of
submission in the annual report.
It may be necessary to require special studies on a case-by-case and
site specific basis to establish the·relationship between quantities of
radioactive material released in effluents, the concentrations in
environmental media, and the resultant doses for important pathways.
[87]
3
If the results of a determination in the EPA crosscheck progr .. (or equivalent
program) art outside the specified control limits, the laboratory shall inv~stigate
the cause of the problem and take steps to correct it. The results cf
this investigation and corrective action shall be included fn the annual
report.
The requirement for the participation in the EPA crosscheck program, or simila~
program, is based on the need for independent checks on the precision and
accuracy of the measurements of radioactive material f n environmental sample
matrices as part of the quality assurance program for environmental monitoring
in or-der to demonstrate that the results are l"easoQably valid. A census shall be conducted annually during the growing season to determine
the location of the nearest milk animal and nearest garden greater than
SO square meters (SOO sq. ft.) prodwcfng broad leaf vegetation in each of the
16 meteorological sectors within a dist.Ince of 8 km (S •iles).I For elevated
releases as defined in Regulatory Guide 1.111, Rev. 1., the census shall also
~dentify the locations of all mflk animals, and gardens greater than 50 square
meters producing broad 11a'T"V1g1tation out to a distance of 5 km. (3 milts)
for each radial sector.
If ft is learned fl'"Oll thf s census that the milk animals or gardens are present
at a location which yields a calculated thyroid dose greater than those previously
sampled, or if the census results f n changes f n the location used f n the
radioactive effluent technical specfffcatfons for dose calculations, a written
report shall be submitted to the Director of Operating Reactors, NRR (with a
copy to the Director of the NRC Regional Office) within 30 days identifying
the new location (distance and direction). Milk animal or garden locations
·resulting in higher calculated doses shall be added to the surveillance program
as soon as practicable.
The sampling location (excluding the control sample location) having the
lowest calculated dose 111y then be dropped from the surveillance program at
the end of the grazing or growing season during which the census was conducted.
Any location frOll whicn mf lk can no longer be obtained may be dropped
from the surveillance program after notifying the NRC in writing that they are
no longer obtainable at that lotition. The results of the land-use census
shall be reported in the annual :-eport.
ihe census of milk animals and ~ardens producing broad leaf vegetation is
based on the requirement fn Appendix I of 10 CFR Part 50 to "Identify changes
fn the use of unrestricted area' (e.g., for agricultural purposes) to permit
aodificatfons in monitoring prog•·ams for evaluating doses to individuals from
principal pathways of 1xposure.h The consumption of •ilk from ani .. ls grazing
on contaminated pasture and of l~~fy vegetation contaminated by airborne
Broad leaf vegetation sampling ~•Y be performed at the site boundary in a
sector with the highest D/Q in ~itU of the garden census.
[88]
4
radioiodine is a major potential source of exposure. Samples from milk_animals
are considered a better indicator of radioiodine in the environment than
vegetation. If the census reveals milk animals are not present or are
unavailable for sampling, then vegetation must be sampled.
The SO square meter garden, considering 20% used for growing broad leaf vegetation
(i.e., similar to lettuce and cabbage), and a vegetation yield of 2 kg/m2 ,
will produce the 26 kg/yr assumed in Regulatory Guide 1.109, Rev 1., for child
consumption of leafy vegetation. The option to consider the garden to be
broad leaf vegetation at the site boundary in 1 sector with the highest D/Q
should be conservative and that location may be used to calculate doses due to
radioactive effluent releases in place of the actual locations which would be
determined by the census. This option does not apply to plants with elevated
releases as defined in Regulatory Guide 1.111, Rev. l.
The increase in the number of direct radiation stations is to better characterize
the individual exposure (mrem) and population exposure (man-rem) in accordance
with Criterion 64 - Monitoring radioactivity releases, of 10 CFR Part 50,
Appendix A. The NRC will place a similar amount of stations in the area
between the two rings designated in Table 1.
NOTE ~
Guidance on the subjects contained on pages 4 through 16 of the Radiological
Assessment Branch Technical Position (RAB-BTP) has been modified and upgraded
based on operating £xperience since Revision 1 was published in 1979. The
current staff guidance for the following items has been incorporated in the
Section 3/4-12 and Secti~n 6 Controls of NUREG-1301 and 1302.
0
•
0
Reporting Requirement
Table 1: Operational Radiological Environmental Monitoring Report
lable 2: Detection Capabilities for Environmental Sample Analysis
Table 4: Reporting Levels for Radioactivity Concentrations in Environmental
Samples
7he following items remain unchanged:
•
0
0
Footnote to lable 1 on page 10
Table 3 of page 14
Figure l of page 16
[89]
Pages s. 6, 7, s. 9, 11. 12, 13, 15
The above pages have been superceded by text and tables
in NUREG-1301 and 1302.
[90]
lAOLE 1 (Conltnued)
Note: In addition to the above guidance for operational 110niloring. the following ..atertal ts supplied for guidance
on preoperattonal pt·ogra•s.
Preoperalional Envlro11111enlal Surveillance Progra•
A Preoper·attonal Envlron11enlal Surveillance Progra• should be instituted two years prior to the institution of station
plant operation.
The purposes of thf s progra• are:
1. To .. asure background levels and their variations along the anticipated critical pathways in the area
surrounding the station.
2. To train personnel
3. To evaluate procedures, equi.,.ent and techniques
The elements (sa11Pllng .. dla and type of analysts) of both preoperational and operational progra•s should be essentially
the sa.e. The duration of the preoperatlonal progra•. for specific .. dia, presented in the following table
~ should be followed:
_.,
'--' Dur.lion of Preoperaltonal Sa1111>1tng Progra• for Specific Media
6 110nths
• airborne Iodine
• Iodine In •Ilk (while
anl•als are In pasture)
1 year
. airborne particulates
. •ilk (re•alning analyses)
• surf ace waler
• groundwater
• drinking water
2 years
• direct radiation
• fish and invertebrates
• food products
. sediment fro• shoreline
.... 0
.T..,A. _B_L_E _ l_
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL SUtttARY
Na11e of Faclltty Docket No.
Location of Facf1fty Reporting P-er_,i_o. d... -' -
- (County, Slate) -----
Medlu• or
Pathway Sa111pled
{Unit of
Measure11enl)
Air Parttculates
(pCf /•3)
,......,
U)
"' L...J
Fish pCf/kg
(wet weight)
.
Type- and-- ---lowe_r_ Lt11ft Alflndtcalor--Tocallon with-Highest - --Control locat~ons
Total NUllber of a LocatlonB Annual Mean b Mean (f)
of Analyses Detectton Mean (f) Name Mean (f) Range
Perforwed (LLD) Range Dtstance & Range
Dtrectton
Gross p 416 0.01 0.08(200/312) Middletown 0.10 (5/52) 0.08 (8/104)
(0.05-2.0) 5 11i les 340° (0.08-2.0) (0. 05-1. 40)
y·Spec. 32
137cs 0.01 0.05 (4/24) S11fthvtlle 0.08 (2/4) <LLD
(0.03-0. 13) 2.5 •fles 160° (0.03-2.0)
1311 0.07 0. 12 (2/24) Podunk 0.20 (2/4) 0.02 (2/4)
(0.09-0. 18) 4.0 11tles 270° (0.10-0.31)
y-Spec. 8
137Cs 130 <LLD - <LLD 90 (1/4)
134cs 130 <LLD - <LLD <LLD
60co 130 180 (3/4) River Mt le 35 See Col111111 4 <LLD
(150-225)
•see Table 2, note b.
NU.her of ·
Nonrouttne
Reported
Measurements
1
4
1
0
0
0
b Mean and range based upon detectable 11easure11ents only. Fraction of detectable 11easure11ents at specified locations
ts indicated In parentheses. ( f)
Hole: The example data are provided for f llustratfve purposes only.
......
Figure l
{This figure shall be of a suitable scale to show the distance and direction
of each monitoring station. A key shall be provided to indicate what is
sampled at each location.)
[93]
..
APPENDIX B
"Appendix B - General Contents of the Offsite Dose Calculat;on
Manual (ODCM) (Revision 1, February 1979)" to the paper authored by
C. A. Willis and F. J. Congel, "Status of NRC Radiological Effluent Technical
Specification Activities" presented at the Atomic Industrial Forum Conference
on NEPA and Nuclear Reg.ulation, October 4-7, 1981, Washington, D.C.
[94]
APPENDIX 8
GENERAL CONTENTS OF THE OFFSITE DOSE CALCULATION MANUAL (ODCM*)
(Rev. 1, February 1979)
Section 1 - Set Points
Provide the equations and methodology to be used at the station or unit for
each alarm and trip set point on each effluent release point according to the
Specifications 3.3.3.8 and 3.3.3.9. The instrumentation for each alarm and
trip set point, including radiation.monitoring and sampling systems and
effluent control features, should be identified by reference to the FSAR
(or Final Hazard Summary). This information should be consistent with the
recommendations of Section I of Standard Review Plan 11.5, NUREG-75/087,
(Revision 1). If the alarm and/or trip set point value is variable~ provide
the equation to determine the set point value to be used, based on actual
release conditions, that will assure that the Specification is met at each
release point; and provide the value to be used when releases are not in
progress. If dilution or dispersion is used, state the onsite equipment
and measurement method used during release, the site related parameters and
the set points used to assure that the Specification is met at each release
point. The fixed and variable set points should consider the radioactive
effluent to have a radionuclide distribution represented by normal and
anticipated operational occurrences.
Section 2 - Liquid Effluent Concentration
Provide the equations and methodology to be used at the station or unit
for each liquid release point according to the Specification 3.11.1.1. For
systems ~1th continuous or batch releases, and for systems designed to
monitor and control both continuous and batch releases, provide the assump-
. tions and parameters to be used to compare the output of the monitor with
the 1 i'qui d concentration sped fi ed. State the 1 imitations for comb1 ned
discharges to the same release point. In addition, describe the method and
assumptions for obtaining representative samples fran ~ach batch and use of
previous post-release analyses or canposite sample analyses to meet the
Specification. ·
S~ction 3 - Gaseous Effluent Dose Rate
Provide the equations and methodology to be used at the station or unit for
each gaseous release point according to Specification 3.11.2.1. Consider
the various pathways, release point elevations, site related parameters and
radionuclide contribution to.the dose impact limitation. Provide the
- the fonnat for the ODCM fs left up to the licensee and may be simplified by
tables and grid printout. Each page should be numbered and indicate the
facility approval and effective date. ·
[95]
- 2 -
dose factors to be used for the identified radionuclides released. Provide
the annual average dispersion values (X/Q and D/Q), the site specific parameters
and release point elevations.
Section 4 - Liquid Effluent Dose
Provide the equations and methodology to be used at the station or unit for
each liquid release point according to the dose objectives given in Specification
3.11.1.2. The section should describe how the dose contributions
are to be calculated for the various pathways and release points, the equations
and assumptions to be used, the site specific parameters to be measured
and used, the receptor location by direction and distance, and the method of
estimating and updating cumulative doses due to liquid releases. The dose
factors, pathway transfer factors, pathway usage factors, and dilution factors
for the points of pathway origin, etc., should be given, as well as
receptor age group, water and food consumption rate and other factors
assumed or measured. Provide the met~od of determining the dilution factor
at the discharge during any liquid effluent release and any site specific
parameters used in these determinations.
Section 5 - Gaseous Effluent Dose
Provide the equations and methodology to be used at the station or unit for
each gaseous release point according to the dose objectives given fn
Specifications 3.11.2.2 and 3.11.2.3. The section should describe how the
dose contributions are to be calculated for the various pathways and release
points, the equations and assumptions to be used, the site specific parameters
to be measured and used, the receptor location by direction and distance, and
the method to be used for estimating and updating cumulative doses due to
gaseous releases. The location, direction and distance to the neare~t residence,
cow, goat, meat animal, garden, etc., should be given, as well as
receptor age group, crop yield, grazing time and other factors.assumed or
measured. Provide the method of determining dispersion values (X/Q and D/Q)
for releases and any site specific parameters and release point elevations
used in these determinations.
Section 6 - Projected Doses
For liquid and gaseous radwaste treatment systems, prCHide the method of
p~ojecting doses due to effluent releases for the normal and alternate
pathways of treatment according to the specifications, describing the components
and subsystems to be used.
[96]
- 3 -
Section 7 - Operability of Equipment
Provide a flow diagram{s) defining the treatment paths and the components of
the radioactive liquid, gaseous and solid waste management systems that are
to be maintained and used, pursuant to 10 CFR 50.36a, to meet Technical Specifications 3.11.1.3, 3.11.2.4 and 3.11.3.1. Subcomponents of packaged
equipment can be identified by a list. For operating reactors whose construction
permit applications were filed prior to January 2, 1971, the flow
diagram{s) shall be consistent with the infonnation prOYided in confonnance
with Section V.B.l of Appendix I to 10 CFR Part 50. For OL applications
whose construction permits were filed after January 2, 1971, the flow
diagram{s) shall be consistent with the infonnation provided in Chapter 11
of the Final Safety Analysis Report (FSAR) or amendments thereto.
Section 8 - Sample locations
Provide a map of the Radiological Environmental Monitoring Sample Locations
indicating the numbered sampling locations given in Table 3.12-1. Further
clarification on these numbered sampling locations can be provided by a list,
indicating the direction and distance from the center of the buil.ding complex
of the unit or station, and may include a discriptive name for identification
purposes.
[97].
APPENDIX C
GENERIC LETlER 89-01
IMPLEMENTATION OF PROGRAMMATIC CONTROLS FOR RADIOLOGICAL EFFLUENT
TECHNICAL SPECIFICATIONS IN THE ADMINISTRATIVE CONTROLS SECTION OF
THE TECHNICAL SPECIFICATIONS AND THE RELOCATION OF PROCEDURAL DETAILS
OF RETS TO THE OFFSITE DOSE CALCULATION MANUAL OR TO THE PROCESS
CONTROL PROGRAM
(98]
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C. 20555
January 31, 1989
lO ALL PO\IER REACTOR LICENSEES AHD l.PPLICANTS
SUBJECT: JMPLEME~T1'TION OF PROGRAMMATIC CONTROLS FOR RADIOLOGICAL EFFLUENT
TECHNICAL SPECIFICATIOriS JN TH£ ADMINISTRATIVE CONTROLS SECTION OF
THE TECHNICAL SPECIFICATIONS AND THE RELOCATION OF PROCEDURAL DETAILS
OF ~ETS TO THE OFFSITE DOSE CALCULATION MANUAL OR TO THE PROCESS
CO~TROL PROGRAH (GENERIC LETTER 89-01)
The HRC staff has examined the contents of the Radiological Effluent Technical
Specif1cot;ons (RETS) in relation to the Conniss1on's Interim Polfcy Statement
on Technical Specification lmprovernents. The staff has detennfned that progran1:
1atic controls can be implemented in the Administrative Controls section of
the Technical Specifications (TS) to satisfy existing regulatory reauirements
for RETS. At the same time, the procedural details of the current TS on radioactive
effluents and radiological environmental monitoring can be relocated to
the Offs1te Dose Calculation Manual (ODCM). like~ise, the procedural details
of the current TS on solid radioactive wastes can be relocated to the Process
Control Program (PCP). lhese actions sin1plif.Y the RETS, meet the regulator.Y
reauirements for radioactive effluents and radiological environmental monitoring,
and are provided as a line-item improven1ent of the TS, consistent with the
soals of the Policv Statement. ·
Wew progrannatic controls for radioactive effluents and radiological environmenta
1 11onitoring are incorporated 1n the TS to conform to the regulator.v
reauirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.361, and Appendil I
to 10 CFR Part 50. £listing progrannatic reauirements for the PCP are being
retained in the TS. The procedural details included 1n licensees' present TS
on radioactive effluents. solid radioactive wastes, env1ronmenta1 110nitoring,
and associated reporting reau1ranents will be relocated to the ODCM or PCP as
appropriate. licensees will handle future changes to these procedural details
in the ODCM and the PCP under the administrative controls for changes to the
ODCM or PCP. Finally, the definitions of the ODC~ and PCP are updated to
reflect these changes.
Enclosure 1 provides guidance for the preparation of a license amendment reauest
to implement these alternatives for RETS. Enclosure 2 provides a listing
of existing RETS and a description of how each ts addressed. Enclosure 3
provides model TS for progr111111atic controls for RElS and its associated reporting
reauirements. Finally, Enclosure 4 provides 110del specifications for
retaining existir.g reauirements for eiplosive gas monitoring tnstrumentation
reauirements that apply on a plant-specific basis. Licensees are encouraged to
propose changes to TS that are consistent with the guidance provtded tn the
enclosures. Conforming ar.endment reauests wf 11 be expeditiously revtewed by
[99]
Generic Letter 89-01 2 January 31, 1989
the NRC Project Manager for the fac;11ty. Proposed amendments that deviate
from th;s guidance will require a longer, more deta;led review. Please contact
the appropriate Project Manager if you have questions on this matter.
Enclosures:
l through 4 as stated
Sincerely,
Mark Hawes. fA..
Acting Associate D ctor for Projects
Office of Nuclear Reactor Regulat;on
[100]
Generic Letter 89-ol ENCLOSURE 1
GUIDANCE FOR THE IMPLEMENTATION OF PROGRAMMATIC CONTROLS FOR RETS
IN THE ADMINISTRATIVE CONTROLS SECTION OF TECHNICAL SPECIFICATIONS
AND THE RELOCATION OF PROCEDURAL DETAILS OF CURRENT RETS TO THE
OFFSITE DOSE CALCULATION MANUAL OR PROCESS CONTROL PROGRAM
INTRODUCTION
This enclosure provides guidance for the preparation of a license amendment
request to implement programmatic controls in Technical Specifications (TS)
for radioactive effluents and for radiological environmental monitoring conforming
to the applicable regulatory requirements. This will allow the relocation
of existing procedural details of the current Radiological Effluent
Technical Specifications (RETS) to the Offsite Dose Calculation Manual (ODCM).
Procedural details for solid radioactive wastes will be relocated to the
Process Control Program (PCP). A proposed amendment will (1) incorporate programmatic
controls in the Administrative Controls section of the TS that satisfy
the requirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR S0.36a. and
Appendix I to 10 CFR Part 50, (2) relocate the existing procedural details in
current specifications involving radioactive effluent monitoring instrumentation,
the control of liquid and gaseous effluents, equipment requirements for
liquid and gaseous effluents, radiological environmental monitoring, and radiological
reporting details from the TS to the ODCM, (3) relocate the definition
of solidification and existing procedural details in the current specification
on solid radioactive wastes to the PCP, (4) simplify the associated reporting
requirements, (5) simplify the administrative controls for changes to the ODCM
and PCP, (6) add record retention requirements for changes to the ODCM and PCP,
and (7) update the definitions of the ODCM and PCP consistent with these
changes.
The NRC staff's intent in recommending these changes to the TS and the relocation
of procedural details of the current RETS to the ODCM and PCP is to fulfill
the goal of the Commission Policy Statement for Technical Specification
Improvements. It is not the staff's intent to reduce the level of radiological
effluent control. Rather, this amendment will provide programmatic controls
for RETS consistent with regulatory requirements and allow relocation of the
procedural details of current RETS to the ODCM or PCP. Therefore, future
changes to these procedural details will be controlled by the controls for
changes to the ODCM or PCP included in the Administrative Controls section of
the TS. These procedural details are not required to be included in TS by
DISCUSSION
Enclosure 2 to Generic Letter 89- provides a summary listing of specifications
that are included under the heading of RETS in the Standard Technical
Specifications (STS) and their disposition. Most of these specifications will
be addressed by programmatic controls in the Administrative Controls section of
the TS. Some specifications under the heading of RETS are not covered by the
new programmatic controls and will be retained as requirements in the existing
plant TS. Examples include requirements for explosive gas monitoring instrumentation,
limitations on the quantity of radioactivity in liquid or gaseous
holdup or storage tanks or in the condenser exhaust for BWRs, or limitations on
explosive gas mixtures in offgas treatment systems and storage tanks.
[ 1 01]
Generic Letter 89- 01 - 2 - Enclosure 1
Licensees with nonstandard TS should follow the guidance provided in Enclo
·sure 2 for the disposition of similar requirements in the format of their TS.
Because solid radioactive wastes are addressed under existing programmatic
controls for the Process Control Program, which is a separate program from the
new programmatic controls for liquid and gaseous radioactive effluentsJ the
requirements for solid radioactive wastes and associated solid waste reporting
requirements in current TS are included as procedural details that will be
relocated to the PCP as part of this line-item improvement of TS. Also, the
staff has concluded that records of licensee reviews performed for changes made
to the ODCM and PCP should be documented and retained for the duration of the
unit operating license. This approach is in lieu of the current requirements
that the reasons for changes to the ODCM and PCP be addressed in the Semiannual
Effluent Release Report.
The following items are to be included in a license amendment request to imple- .
ment these changes. First, the model specifications in Enclosure 3 to Generic
Letter 89- should be incorporated into the TS to satisfy the requirements of
10 CFR 20.106, 40 CFR Part 190, 10 CFR S0.36a, and Appendix I to 10 CFR Part 50.
The definitions of the ODCM and PCP should be updated to reflect these changes.
The programmatic and reporting requirements are general in nature and do not
contain plant-specific details. Therefore, these changes to the Administrative
Controls section of the TS are to replace corresponding requirements in plant
TS that address these items. They should be proposed for incorporation into
the plant's TS without change in substance to replace existing requirements.
If necessary, only changes in format should be proposed. If the current TS
include requirements for explosive gas monitoring instrumentation as part of
the gaseous effluent monitoring instrumentation requirements, these requirements
should be retained. Enclosure 4 to Generic Letter 89- provides model
specifications for retaining such requirements.
Second, the procedural details covered in the licensee's current RETS, consisting
of the limiting conditions for operation, their applicability, remedial
actions, surveillance requirements, and the Bases section of the TS for these
requirements, are to be relocated to the ODCM or PCP as appropriate and in a
manner that ensures that these details are incorporated in plant operating procedures.
The NRC staff does not intend to repeat technical reviews of the relocated
procedural details because their consistency with the applicable regulatory
requirements is a matter of record from past NRC reviews of RETS. If
licensees make other than editorial changes in the procedural details being
transferred to the ODCM, each change should be identified by markings in the
margin and the requirements of new Specification 6.14a.(1) and (2) followed.
Finally, licensees should confirm in the amendment request that changes for
relocating the procedural details of current RETS to either the ODCM or PCP
have been prepared in accordance with the proposed changes to the Administrative
Controls section of the TS so that they may be implemented i1111ediately
upon issuance of the proposed amendment. A complete and legible copy of the
revised ODCM should be forwarded with the amendment request for NRC use as a
reference. The NRC staff will not concur in or approve the revised ODCM.
[102]
Generic Letter 89-01 - 3 - Enclosure l
licensees should refer to •Generic Letter 89· • fn the Subject line of license
amendment reauests implementing the guidance of this Generic Letter. This w;11
fac;litate the staff's tracking of licensees' responses to this Generic Letter.
SUMMARY
lhe license amendment reauest for the line-item improvements of the TS relative
to the RETS will entail (l) the incorporation of prograzrmatic controls for
radioactive effluents and radiological environmental monitoring in the Administrative
Controls section of the TS, (2) incorporatation of the procedural
details of the current RETS in the ODCM or PCP as appropriate, and (3) confirmation
that the guidance of this Generic Letter has been followed.
[103]
blSPOSITION OF SPECIFICATIONS AND ADMINISTRATIVE CONTROLS
INCLUDED UNDER THE HEADING OF RETS IN TRE STANDARb TECHNICAL SPEtlFIC~TJONS G"t
nt
- I
SPECIFICATION TITLE nlSPOSITION OF EXISTING SPECIFlCATlON .n.,t - ....
n
1.17 OFFSITE DOSE CALCULATION HANUAL Definition is updated to reflect the change 1n scope ,...
nt of the ODCM. r+
r+
nt
1.22 PROCESS CONTROL PROGRAM Definitfon ts updated to reflect the change in scope
.,
1.32 SOLIDIFICATION Def initfon ts relocated to the PCP. -
3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT Programnatic controls are included fn 6.8.4 g. Item t).
MONITORING INSTRUMENTATJON Existing specification procedural details are relocated
to the ODCM.
3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT Progrannatic controls are included in 6.8.4 g. Item t).
MONITORING 1NSTRUJ.1ENTATION Existing specification procedural details are relocated
to the ODCH. Existing reouf rements for explosive gas
,....., monitoring 1nstrumentat1on should be retained. Model __. specff icatfons for these reau1rements are provided in
0 Enclosure 4.
'"-"-"
3/4.11.1.1 LIQUID EFFLUENTS: CONCENTRATION Progrannatfc controls are included in 6.8.4 g. Items 2)
and 3). Exfstfng specification procedural details are
relocated to the ODCM.
3/4.11.1.2 LIQUID EFFLUENTS: DOSE Programnatfc controls are included fn 6.8.4 g. Items 4)
and 5). Existing spec1ffcat1on procedural details are
relocated to the OOCM.
3/4.11.1.3 LIQUID EFFLUEHTS: LIQUID Progrannatfc controls are included in 6.8.4 g. Item 6).
RADWASTE TREATMENT SYSTEM Existfnq speciffcatfon procedural details are relocated
to the ODCM.
"'
3/4.11.t.4 LIQUID HOLDUP TANKS Existing specification reaufrements to be retained. ::I
-n 0
.c", '
nt
"'
DISPOSITION OF SPECIFICATIONS ANO ADMINISTRATIVE CONTROLS
INCLUDED UNDER THEHEADJffG_OF RETS IN THE STANDARD TECHNICAL SPECIFICATIONS_{Cont.) G')
19
,::.:9,
SPECIFICATION TITLE DISPOSITION OF EXISTING SPECIFICATION - -.., n
3/4.11.2.1 GASEOUS EFFLUENTS: DOSE RATE Progrannatfc controls are fncluded fn 6.8.4 g. Items 3) ,...
ft)
and 7). Exfst1ng specification procedural details are ..........
relocated to the ODCM. .Cl,»
3/4.11.2.2 GASEOUS EFFLUENTS: DOSE-tlOBLE Progrannatfc controls are included in 6.8.4 g. Items 51 °'°' GASES and 8). Existing specification procedural details are -0' relocated to the ODCM.
3/4.11.2.3 GASEOUS EFFLUENTS: DOSE-- IODINE- Progrannatic controls are included 1n 6.8.4 g. Items 5)
131, IODINE-133, TRITIUM, AND and 9). Existing specification procedural details are
RADIOACTIVE MATERIAL IN PARTICU- relocated to the ODCM.
LATE FORM
3/4.11.2.4 GASEOUS EFFLUENTS: GASEOUS Progrannattc controls are tncluded tn 6.8.4 g. Item 6).
RADWASTE TREATMENT or Existing spectftcation procedural details are relocated
...-..-... VENTILATION EXHAUST TREATMENT to the ODCM • N 0 SYSTEM • U1
L..J 3/4.11.2.5 EXPLOSIVE GAS MIXTURE Existing specfffcatfon reauirements should be retained.
3/4.11.2.6 GAS STORAGE TANKS Exf stfng specf ficatton reauirements should be retained.
3/4.11.2.7 MAIN CONDENSER (DWP) Existing specfffcatfon reauirements should be retained.
..
3/4.U.2.8 PURGING AND.VENTING (BWR Mark II Progrannattc controls are included fn 6.8.4 g. lte• 10).
contain1nents) Existing specification procedural details are relocated
to the ODCM.
3/4.11.3 SOLID RADIOACTIVE WASTES Extsttng specification procedural details are relocated
to the PCP.
"~' 3/4.11.4 RADIOACTIVE EFFLUENTS: TOTAL Progrannatic controls are included in 6.8.4 g~ ltan 11). n- DOSE Existing specification procedural details are relocated . 0
to the ODCM. c."., '
m
"'
~ -------- -----~·----- -------- --------
blSPOSITION OF SPECIFICATIONS AND ADMINISTRATIVE CONTROLS
INCLUDED UNDER THE H[ADlNG_OF_RETS_JN_THE ~TANDARD TEtHNltAL seEtlflCATIONS_{Cont.) °t'D'
- s
f1> SPECIFICATION TITLE DISPOSITION OF E~ISTING_SPECIFICATION ...,. n
3/4.12.1 RADIOLOGICAL ENVIRONMENTAL Progrannattc controls are tncluded tn 6.8.4 h. Item t). r- MONITORING: MONITORING PROGRAM Extsttng spectftcatton procedural details are relocated "r+'
r+ to the OOCM. .",'
m
3/4.12.2 RADIOLOGICAL ENVIRONMENTAL Progrannattc controls are tncluded tn 6.8.4 h. Item 2). . '° I MONITORING: LAND USE CENSUS Existtng specification procedural details are relocated 0_ ,,
to the ODCM.
3/4.12.3 RADIOLOGICAL ENVIRONMENTAL Progrannattc controls are included fn 6.8.4 h. Item 3).
MONITORING: INTERLABORATORY Ex1st1ng specification procedural details are relocated
COMPARISON PROGRAM to the ODCM.
5.1.3 DESIGN FEATURES: SITE - MAP Existing spectftcatfon reauf rements should be retained.
DEFINING UNRESTRICTED AREAS ANO
SITE BOUNDARY FOR RADIOACTIVE • ....-..-.. GASEOUS AND LIQUID EFFLUENTS w
0
O' 6.9.1.3 REPORTING REQUIREMENTS: ANNUAL Specification sfl!plffied and existing reportfng details L......J RADIOLOGICAL ENVIRONMENTAL are relocated to the ODCM.
OPERATUIG REPORT
6.9.1.4 REPORTING REQUIREMENTS: SEMI- Specffication Si11Plffted and exfsting reporting details
ANNUAL RADIOACTIVE EFFLUENT are relocated to the ODCM or PCP as appropriate.
RELEASE REPORT
6.13 PROCESS CONTROL PROGRAM Specffication reaufrements are si1111>11f1ed.
6.14 OFFSITE OOSE CALCULATION MANUAL Specfftcatton reaufrewnents are sf1111>lifted.
6.15 MAJOR CHANGES TO LIQUID, GASEOUS, Existing procedural details are relocated to the ODCM or
AND SOLID RADWASTE TREATMENT PCP as appropriate. ":3' SYSTEMS n_, ,
0
..c"., '
N
Generic Letter 89~1 Enclosure 3
TECHNICAL SPECIFICATIONS TO BE REVISED
1.17 DEFINITIONS: OFFSITE DOSE CALCULATION MANUAL
1.22 DEFINITIONS: PROCESS CONTROL PROGRAM
6.8.4 g. PROCEDURES AND PROGRAMS: RADIOACTIVE EFFLUENT CONTROLS
6.8.4 h. PROCEDURES AND PROGRAMS: RADIOLOGICAL ENVIRONMENTAL MONITORING
6.9.1.3 REPORTING REQUIREMENTS: ANNUAL RADIOLOGICAL ENVIRONMENTAL
OPERATING REPORT
6.9.1.4 REPORTING REQUIREMENTS: SEMIANNUAL RADIOACTIVE EFFLUENT
RELEASE REPORT
6.10 RECORD RETENTION
6.13 PROCESS CONTROL PROGRAM {PCP)
6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)
MODEL TECHNICAL SPECIFICATION REVISIONS
(To supplement or replace existing specifications)
1.0 DEFINITIONS
OFFSITE DOSE CALCULATION MANUAL
1.17 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/Trip Setpoints, and in the conduct of the Environmental
Radiological Monitoring Program. The ODCM shall also contain (1) the
Radioactive Effluent Controls and Radiological Environmental Monitoring Programs
required by Section 6.8.4 and (2) descriptions of the information that
should be included in the Annual Radiological Environmental Operating and Semiannual
Radioactive Effluent Release Reports required by Specifications 6.9.1.3
and 6.9.1.4.
1.22 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas,
sampling, analyses, test, and determinations to be made to ensure that processing
and packaging of solid radioactive wastes based on demonstrated processing
of actual or simulated wet solid wastes will be accomplished in such a way as
to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations,
burial ground requirements, and other requirements governing the disposal of
solid radioactive waste.
[107]
Generic Letter 89- 01 - 2 - Enclosure 3
6.0 ADMINISTRATIVE CONTROLS
6.8 PROCEDURES AND PROGRAMS
6.8.4 The following programs shall be established, implemented, and maintained:
g. Radioactive Effluent Controls Program
A program shall be provided conforming with 10 CFR 50.36a for the
control of radioactive effluents and for maintaining the doses to
MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably
achievable. The program (1) shall be contained in the OOCM,
(2) shall be implemented by operating procedures, and (3) shall include
remedial actions to be taken whenever the program limits are
exceeded. The program shall include the following elements:
1) Limitations on the operability of radioactive liquid and gaseous
monitoring instrumentation including surveillance tests and setpoint
determination in accordance with the methodology in the
OOCM 1 .
2) Limitations on the concentrations of radioactive material
released in liquid effluents to UNRESTRICTED AREAS conforming to
10 CFR Part 20 1 Appendix B, Table II, Column 21
3) Monitoring, sampling, and analysis of radioactive liquid and
gaseous effluents in accordance with 10 CFR 20.106 and with the
methodology and parameters in the ODCM 1
4) Limitations on the annual and quarterly doses or dose commitment
to a MEMBER OF THE PUBLIC from radioactive materials in liquid
effluents released from each unit to UNRESTRICTED AREAS conforming
to Appendix I to 10 CFR Part 50,
5) Determination of cumulative and projected dose contributions
from radioactive effluents for the current calendar quarter and
current calendar year in accordance with the methodology and
parameters in the ODCM at least every 31 days.
6) Limitations on the operability and use of the liquid and gaseous
effluent treatment systems to ensure that the appropriate
portions of these systems are.used to reduce releases of radioactivity
when the projected doses in a 31-day period would
exceed 2 percent of the guidelines for the annual dose or dose
connitllent conforming to Appendix I to 10 CFR Part 50 1
7) Limitations on the dose rate resulting from radioactive material
released in gaseous effluents to areas beyond the SITE BOUNDARY
conforming to the doses associated with 10 CFR Part 20,
Appendix 81 Table II 1 Column 1,
[108]
Generic Letter 89~1 - 3 - Enclosure 3
ADMINISTRATIVE CONTROLS
6.8.4 g. Radioactive Effluent Controls Program (Cont.)
8)
9)
10)
Limitations on the annual and quarterly air doses resulting from
noble gases released in gaseous effluents from each unft to
areas beyond the SITE BOUNDARY conforming to Appendix I to
10 CFR Part SO,
Limitations on the annual and quarterly doses to a MEMBER OF
THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides
in particulate form with half-lives greater than 8 days
in gaseous effluents released from each unit to areas beyond the
SITE BOUNDARY conforming to Appendix I to 10 CFR Part SO,
Limitations on venting and purging of the Mark II containment
through the Standby Gas Treatment System to maintain releases
as low as reasonably achievable (BWRs w/Mark II containments),
and
11) 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 conforming to 40 CFR Part 190.
h. Radiological Environmental Monitoring Program
A program shall be provided to monitor the radiation and radionuclides
in the environs of the plant. The program shall provide
(1) representative measurements of radioactivity in the highest
potential exposure pathways, and (2) verification of the accuracy of
the effluent monitoring program and modeling of environmental exposure
pathways. The program shall (1) be contained in the ODCM,
(2) conform to the guidance of Appendix I to 10 CFR Part 50, and
(3) include the following:
l) Monitoring, sampling, analysis, and reporting of radiation and
radionuclides in the environment in accordance with the methodology
and parameters in the ODCM,
2) A Land Use Census to ensure that changes in the use of areas at
and beyond the SITE BOUNDARY are identified and that modifications
to the monitoring program are made if required by the
results of this census, and
3) Participation in 1 Interlaboratory Comparison Program to ensure
that independent checks on the precision and accuracy of the
measurements of radioactive materials in environmental sample
•atrices are performed as part of the quality assurance program
for environmental monitoring.
[109]
Generic Letter 89"1)1 - 4 - Enclosure 3
ADMINISTRATIVE CONTROLS
6.9 REPORTING REQUIREMENTS
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*
6.9.1.3 The Annual Radiological Environmental Operating Report covering the
operation of the unit during the previous calendar year shall be submitted
before May 1 of each year. The report shall include summaries, interpretations,
and analysis of trends of the results of the Radiological Environmental
Monitoring Program for the reporting period. The material provided shall be
consistent with the objectives outlined in (1) the ODCM and (2) Sections
IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part SO.
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT**
6.9.1.4 The Semiannual Radioactive Effluent Release Report covering the operation
of the unit during the previous 6 months of operation shall be submitted
within 60 days after January 1 and July l of each year. The report shall include
a summary of the quantities of radioactive liquid and gaseous effluents
and solid waste released from the unit. The material provided shall be
(1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance
with 10 CFR S0.36a and Section IV.B.1 of Appendix I to 10 CFR Part SO.
6.10 RECORD RETENTION
6.10.3 The following records shall be retained for the duration of the unit
Operating License:
o. Records of reviews performed for changes made to the OFFSITE DOSE
CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
6.13 PROCESS CONTROL PROGRAM (PCP)
Changes to the PCP:
a. Shall be documented and records of reviews performed shall be retained
as required by Specification 6.10.30. This documentation shall
contain:
1) Sufficient information to support the change together with the
appropriate analyses or evaluations justifying the change(s) and
- A single submittal may be made for a multi-unit station.
- A single submittal may be made for a multi-unit station. The submittal
should combine those sections that are common to all units at the station;
however, for units with separate radwaste systems, the submittal shall specify
the releases of radioactive material from each unit.
[ 11 0]
Generic Letter 89-01 - 5 - Enclosure 3
ADMINISTRATIVE CONTROLS
6.13 PROCESS CONTROL PROGRAM (PCP) (Cont.)
2) A determination that the change will maintain the overall conformance
of the solidified waste product to existing requirements
of Federal, State, or other applicable regulations.
b. Shall become effective after review and acceptance by the [URG] and
the approval of the Plant Manager.
6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)
Changes to the COCH:
a. Shall be documented and records of reviews performed shall be retained
as required by Specification 6.10.30. This documentation shall
contain:
1) Sufficient information to support the change together with the
appropriate analyses or evaluations justifying the change(s) and
2) A determination that the change will maintain the level of
radioactive effluent control required by 10 CFR 20.106, 40 CFR
Part 190, 10 CFR S0.36a, and Appendix I to 10 CFR Part SO and
not adversely impact the accuracy or reliability of effluent,
dose, or setpoint calculations.
b. Shall become effective after review and acceptance by the [URG] and
the approval of the Plant Manager. ·
c. Shall be submitted to the Commission in the form of a complete,
legible copy of the entire ODCM as a part of or concurrent with the
Semiannual Radioactive Effluent Release Report for the period of the
report in which any change to the ODCH was made. Each change shall
be identified by markings in the margin of the affected pages,
clearly indicating the area of the page that was changed, and shall
indicate the date (e.g .• month/year) the change was implemented.
r 1 1 1 i
G•meric Letter 89- 01
MODIFICATION OF THE SPECIFICATION FOR RADIOACTIVE GASEOUS
EFFLUENT MONITORING INSTRUMENTATION TO RETAIN REQUIREMENTS
FOR EXPLOSIVE GAS MONITORING INSTRUMENTATION
INSTRUMENTATION
EXPLOSIVE
RABi8A£;iYE GASESHS-EFFtHEN; MONITORING INSTRUMENTATION
LIMITING CONDITION FOR OPERATION
Enclosure 4
explosive
3.3.3.11 The radioactiYe gasecas-effiaent monitoring instrumentation channels
shown in Table 3.3-13 shall be OPERABLE with their Alarm/Trip Setpoints set to
ensure that the limits of Specifications-3~!!:!:!-and 3.11.2.5 are not
exceeded. ihe-Aiarmf;r;p-Setpo;nts·of-these·channeis-meet;ng·Spec;f;caticn
S:!i:2:i-shaii·be-determ;ned·and·adlasted-in-accordance-with-the·methodoica.y
and-parameters-in-the-BBEM:
APPLICABILITY: As shown in Table 3.3-13
ACTION:
explosive
a. With an radioacti•e gaseoas-effiaent monitoring instrumentation
channel Alarm/Trip Setpoint less conservative than required by the
above specification;-immediateiy-saspend-the-reiease-cf-radioacti•e
- aseoas·effiaents-monitored-by-the-affected-channei;-cr declare the
channel inoperable and take the ACTION shown in Table 3.3-13.
explosive
b. With less than the minimum number of radioactiYe gaseoas-effiaent
monitoring instrumentation channels OPERABLE, take the ACTION shown
in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE
status within 30 days and, if unsuccessful expiain-in-the-next-Sem;annaai
·Rad;oaeti•e-Effiaent-Reiease-Report prepare and submit a
Special Report to the Commission pursuant to Specification 6:9:!:4
6.9.2 to explain why this 4.noperability was not corrected in a timely
manner.
c. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS
explosive
4.3.3.11 Each radioaeti•e gaseoas-effiaent monitoring instrumentation channel
shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SBYREE
£HEEK; CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the
frequencies shown in Table 4.3-9.
Sample STS 3/4 3-(n)
[ 112]
TABLE 3.3-13
i-." .' ~E~X§PJLgO~S~IViEl v5 6AS59US Mark HawesbU~Nl MONITORING INSTRUMENTATION
"-4' MINIMUM CllANNCL~
Cit INSTRUMENT OPERABLE APPLICABILITY
1. (Not used)
2A. WASTE GAS HOLDUP SYSTEM Explosive Gas
Monitoring System (for systems designed
to withstand the effects of a hydrogen
explosion)
•• Hydrogen Monttor (Automatic Control) 1 ••
b. Hydrogen or Oxygen Monitor (Process) 1 ••
w ......... 28. WASTE GAS HOLDUP SYSTEM Explostve Gas w Monitoring System (for systetns not designed
-• to withstand the effects of a hvdrogen ,......, :s explosion) _.. .+.. _.. - w a. Hydrogen Monttors (Auto111ttc Control, 2 •• L-1 redundant)
b. Hydrogen or Oxygen Monttors (Process. 2 •• dual)
-ACTI-ON
49
49
50, 52
50
.,,
ID = .ID,
-'• n -"r+'
.r..+..
m
'°I
0.. ..
I
N
I
,.,
- J
.n.. . .0, .
.c..... .
Generic. ,le~~et, 8_9-i)l - 3.-
- (Not used)
- During WASTE GAS HOLDUP SYSTEM operation.
ACTION 45 - (Not used)
ACTION 46 - (Not used)
ACTION 47 - (Not used)
ACTION 48 - (Not used)
ACTION STATEMENTS
Enclosure.4
ACTION 49 - With the number of channels OPERABLE less than required by the
Minimum Channels OPERABLE requirement, operation of this WASTE
GAS HOLDUP SYSTEM may continue provided grab samples are .
collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the
following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 50 - With the number of channels OPERABLE one less than required by
the Minimum Channels OPERABLE requirement, operation of this
system may continue provided grab samples are taken and analyzed
at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With both channels inoperable,
operation may continue provided grab samples are taken and
analyzed at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations
and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations.
ACTION 51 - (Not used)
ACTION 52 - With the number of channels OPERABLE one less than required by
the Minimum Channels OPERABLE requirement, suspend oxygen
supply to the recombiner.
Sample STS 3/4 3-(n+2)
r 114 i
TAME 4.3-9
~ en • ,.
--El EXPLOSIVE ,:,:.I ~AQlQAGJIV~ GAS~OUC Mark Hawes 07:54, 10 May 2016 (EDT)U~Nl MONITORING INSTRUMENTATION SURVEl~LANCE REgUIREMENTS ..,
ftt -.,. n
-4 ,..
Cit fD CHANNEL MODES FOR WHICH r+
r+ CHAtlNEL SOURG~ CHANNEL OPERAT lOtlAL SURVEILLANCE ,...,
INSTRUMENT CHECK GN~GK CALIBRATION TEST IS REQUIRED - °' '°
(Not used) I 1. 0__ ,
2A. WASTE GAS HOLDUP SYSTEM Explostve
Gas Monitoring System (for systems
designed to withstand the effects
of a hydrogen explosion)
a. Hydrogen Monttor D II.A. Q(4) M ••
w (Automatic Control)
........ w b. Hydrogen or Oxygen Monitor 0 N.A. Q(4) or Q(5) " •• • .. ,...., -I (Process) ...... ~ ...... + <.Tl 28. WASTE GAS HOLDUP SYSTEM E1plostve -w '-' Gas Monitoring Svstem (for systems
not designed to withstand the effects
of a hydrogen explosion)
a. Hydrogen Monitors
(Automatic Control, redundant)
0 N.A. Q(4) M ••
b. Hydrogen or Oxygen Monttors
(Process, dual)
0 N.A. Q(4) or Q(S) M ••
,.,
- I
-n 0
c.". ,'
.fD.
G~neric Letter 89- 01
(Not used)
- 5 -
TABLE 4.3-9 (Continued)
TABLE NOTATIONS
During WASTE GAS HOLDUP SYSTEM operation.
(1) (Not used)
(2) (Not used)
(3) (Not used)
Enclosure 4
(4) The CHANNEL CALIBRATION shall include the use of standard gas samples
containing a nominal:
a. One volume percent hydogen, balance nitrogen, and
c. Four volume percent hydrogen, balance nitrogen.
(5) The CHANNEL CALIBRATION shall include the use of standard gas samples
containing a nominal:
a. One volume percent oxygen, balance nitrogen, and
b. Four volume percent oxygen, balance nitrogen.
Sample STS 3/4 3-(n+4)
[ 11 6]
NRC FORM 335
12-891
NRCM 1102,
3201. 3202
2. TITLE AND SUBTITLE
U.S. NUCLEAR REGULATORY COMMISSION
BIBLIOGRAPHIC DATA SHEET
(See instructions on the reverse}
Offsite Dose Calculation Manual Guidance: Standard
Radiological Effluent Controls for Boiling Water Reactors
Generic Letter 89-01, Supplement No. 1
5. AUTHOR(S)
W. Wayne Meinke and Thomas H. Essig
1. REPORT NUMBER
3.
(Al1lgned by NRC. Add Vol., Supp .. Rov.,
1nd Addendum Numbers, If eny.J
DATE REPORT PUBLISHED
MONTH 1 April YEAR 1991
N/A
6. TYPE OF REPORT
Industry Guidance
7. PERIOD COVERED llnclusive Dares!
N/A
B. PERFORMING ORGANIZATION - NAME AND ADDRESS !If NRC, provide Division, Office or Region, U.S. Nuclear Regulatory Commission, and mailing address; if contractor, provide
name and mailing address.)
Division of Radiation Protection and Emergency Preparedness
Off ice of Nuclear Reactor Regulation
U.S. Nuclear Regulatory Conunission
Washington, D.C. 20555
9. SPONSOR ING ORGANIZATION - NAME AND ADDRESS !If NRC, type "Same as above"; if contractor, provide NRC Division, Office or Region, U.S. Nuclear Regulatory Comminion,
and mailing address.}
Same as above
10. SUPPLEMENTARY NOTES
11. ABSTRACT 1200 words or less!
This report contains guidance which may be voluntarily used by licensees who choose
to implement the provision of Generic Letter 89-01, which allows Radiological Effluent
Technical Specifications (RETS) to be removed from the main body of the Technical
Specifications and placed in the Offsite Dose Calculation Manual (ODCM). Guidance is
provided for Standard Effluent Controls definitions, Controls for effluent monitoring
instrumentation, Controls for effluent releases, Controls for radiological environmental
monitoring, and the basis for Controls.
Guidance on the formulation of RETS has been available in draft form (NUREG-0472 and
-0473) for a number of years: the current effort simply recasts those RETS into
Standard Radiological Effluent Controls for application to the ODCM. Also included
for completeness are: (1) radiological environmental monitoring program guidance
previously which had been available as a Branch Technical Position (Rev. 1, November
1979): (2) existing ODCM guidance: and (3) a reproduction of Generic Letter 89-01.
12. KEY WORDS/DESCRIPTORS (List words or phrases that will assist researchers in locating the report.I
Licensee Guidance
Effluent Controls
Effluent Monitoring
Radiological Environmental Monitoring
Boiling Water Reactors
NRC FORM 335 (2-891
13. AVAILABILITY STATEMENT
Unlimited
14. SECURITY CLASSIFICATION
(This Page)
Unclassified
(This Report)
Unclassified
15. NUMBER OF PAGES
16. PRICE
THIS DOCUMENT WAS PRINTED USING RECYCLED PAPER