ML20141K133
| ML20141K133 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  (DPR-77-A-042, DPR-77-A-42, DPR-79-A-034, DPR-79-A-34) |
| Issue date: | 01/14/1986 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20141K136 | List: |
| References | |
| NUDOCS 8601220259 | |
| Download: ML20141K133 (110) | |
Text
$P%
UNITED STATES
]%
&8 NUCLEAR REGULATORY COMMISSION g
E WASHINGTON, D. C. 20555
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment to the Sequoyab Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-77 filed by the Tennessee Valley Authority (licensee), dated October 2 and November 7, 1984, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regulations of the Com-mission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; i
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and j
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is bereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is bereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 42 are bereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications.
l 8601220259 860114 PDR ADOCK 05000327 P
PDR l
. 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 8bSY 00 B. J Yo ngblood Director PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Appendix A Technical Specification Changes Date of Issuance: January 14, 1986 l
i
i ATTACHMENT TO LICENSE AMENDMENT N0. 42 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Replace the following pages of the Appendix "A " Technical' Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Amended Page 1-4 3/4 11-10 3/4 12-10 1-6 3/4 11-11 3/4 12-11 1-6a 3/4 11-12 B 3/4 11-1 3/4 3-69 3/4 11-13 8 3/4 11-2 3/4 3-71 3/4 11-14 B 3/4 11-3 3/4 3-74 3/4 11-15 B 3/4 11-4 3/4 3-77 3/4 11-16 B 3/4 11-5 3/4 8-15 3/4 11-17 8 3/4 12-1 3/4 8-16 3/4 11-18 5-2 3/4 8-17 3/4 11-19 6-12 3/4 11-1 3/4 11-20 6-15 3/4 11-?
3/4 11-21 6-15a 3/4 11-3 3/4 11-22 6-17 3/4 11-4 3/4 12-1 6-18 3/4 11-5 3/4 12-2 6-19 3/4 11-6 3/4 12-6 6-23 3/4 11-7 3/4 12-7 6-24 3/4 11-8 3/4 12-8 6-25 3/4 11-9 3/4 12-9 3
DEFINITIONS OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.15 The OFFSITE DOSE CALCULATION MANUAL shall contain the current methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid' effluent monitoring alarm / trip setpoints, and in the conduct of the environmental radio-logical monitoring program.
OPERABLE - OPERABILITY 1.16 A system, subsystem, train, or 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, a normal and an emergency electrical power source, 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 MODE - MODE 1.17 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.
PHYSICS TESTS 1.18 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 14.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.
PRESSURE BOUNDARY LEAKAGE 1.19 PRESSURE B0UNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.
PROCESS CONTROL PROGRAM (PCP) 1.20 The PROCESS CONTROL PROGRAM shall contain the current formula, sampling, analysis, tests, and determinations to be made to ensure that the processing and l
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 l
compliance with 10 CFR Part 20, 10 CFR Part 71, and federal and state regula-tions and other requirements governing the disposal of radioactive wastes.
PURGE - PURGING l
1.21 PURGE or ? URGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humi.dity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
SEQUOYAH - UNIT 1 1-4 Amendment No. 42 1
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l DEFINITIONS SOLIDIFICATION 1.28 SOLIDIFICATION shall be the conversion of wet radioactive wastes into a form that meets shipping and burial ground requirements.
SOURCE CHECK 1.29 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
~ ~~
STAGGERED TEST BASIS 1.30 A STAGGERED TEST BASIS shall consist of:
A test schedule for n systems, subsystems, trains or other designated a.
components obtained by dividing the specified test interval into n equal subintervals, b.
The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
THERMAL POWER 1.31 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
UNIDENTIFIED LEAKAGE 1.32 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.
VENTILATION EXHAUST TREATMENT SYSTEM 1.33 A VENTILATION EXHAUST TREATMENT SYSTE:4 is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).
Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
VENTING 1.34 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING.
Vent, used in system names, does not imply a VENTING process.
SEQUOYAH - UNIT 1 1-6 Amendment No. 42
DEFINITIONS SITE BOUNDARY 1.35 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee (see Figure 5.1-1).
UNRESTRICTED AREA 1.36 An UNRESTRICTED AREA shall be any area, at or beyond the site boundary to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the site boundary used for residential quarters or industrial, commer-cial, institutional, and/or recreational purposes.
MEMBER (S) 0F THE PUBLIC 1.37 MEMBERS OF THE PUBLIC shall include all individuals who are not occupa-tionally associated with the plant.
This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions.
This category does not include non employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.
l SEQUOYAH - UNIT 1 1-6a Amendment No. 42
INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shewn in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of-Specification 3.11.1.1 are not exceeded.
The alarm /
trip setpoints of these channels shall be determined in accordance with the methodology and the parameters in the OFFSITE DOSE CALCULATION MANUAL (00CM).
APPLICABILITY:
During releases via these pathways.
ACTION:
With a radioactive liquid effluent monitoring instrumentation channel a.
alarm / trip setpoint less conservative than required by the above specification, without delay 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.
Exert best effort to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semi-Annual Radioactive Effluent Release Report why the inopera-bility could not be corrected within 30 days.
c.
The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13.b are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.
I SEQUOYAH UNIT 1 3/4 3-69 Amendment No. 42 l
L
TABLE 3.3-12 (Continued)
TABLE NOTATION ACTION 30 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:
l At least two independent samples are analyzad in accordance a.
with Specification 4.11.1.1.1, and b.
At least two technically qualified mer:bers of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 31 -
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 analyzed for l
grgysradioactivitygammaatalimitofdetectionofatleast 10 microcuries/ gram:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of a.
the secondary coolant is greater than or equal to 0.01 microcuries/ gram DOSE EQUIVALENT I-131.
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when. the specific activity of the secondary coolant is less than or equal to 0.01 micro-curies / gram DOSE EQUIVALENT I-131.
ACTION 32 -
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 sanples are collected and analyzed for gross radjoactivitygammaatalimitofdetectionofatleast i
10 microcuries/ml.
t ACTION 33 -
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 l
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 curves may be used to estimate flow.
ACTION 34 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue provided the tank liquid level is estimated l
during all liquid additions to the tank.
i 1.
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l SEQUOYAH - UNIT 1 3/4 3-71 Amendment No. 42 l
l
INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.
The alarm /
trip setpoints of these channels shall be determined in accordance with the methodology and parameters in the ODCM.
APPLICABILITY:
As shown in Table 3.3-13 ACTION:
With a radioactive gaseous effluent monitoring instrumentation chan-a.
nel alarm / trip setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive gas-l eous effluents monitored by the affected channel, declare the channel inoperable, or change the setpoint so it is acceptably conservative.
l b.
With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.
Exert best efforts to return the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semi-Annual Radioactive Effluent Release Report why the opera-bility could not be corrected within 30 days.
c.
The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13.b are not applicable.
SURVEILLANCE REQUIREMENTS i
4.3.3.10 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 operations at the frequencies shown in Table 4.3-9.
SEQUOYAH - UNIT 1 3/4 3-74 Amendment No. 42
TABLE 3.3-13 (Continurd)
TABLE NOTATION
{
At all t*mes.
During waste gas disposal system operation.
- During shield building exhaust system operation.
ACTION 40 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior to initiat-l ing the release:
At least two independent samples of the tank's contents are a.
analyzed, and b.
At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 41 With the number of channels OPERABLE less than required by the l
Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least l
once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 42 With the number of channels OPERABLE less than requirec o,i 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 noble gas gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 43 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of this waste gas disposal system may continue provided grab samples are taken l
and analyzed either (1) every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations of the reactor coolant system, or (2) daily during other operations.
ACfl0N 44 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after j
the channel has been declared inoperable samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.
SEQUOYAH - UNIT 1 3/4 3-77 Amendment No. 42
i ELECTRICAL POWER SYSTEMS
}
3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.3.1 All containment penetration conductor overcurrent protective devices specified in appropriate plant instructions shall be OPERABLE.
)
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more of the containment penetration conductor overcurrent protective devices specified in appropriate plant instructions inoperable:
l Restore the protective device (s) to OPERABLE status or de-energize the a.
4 circuit (s) by tripping the associated backup circuit breaker within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verify the backup circuit breaker to be tripped at least once per 7 days thereafter; the provisions of Specification 3.0.4 are not applicable to overcurrent devices in circuits which have their backup circuit breakers tripped, or b.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
j SURVEILLANCE REQUIREMENTS i
4.8.3.1 All containment penetration conductor overcurrent protective devices l
specified in appropriate plant instructions shall be demonstrated OPERABLE:
1 j
a.
At least once per 18 months:
4 1.
For at least one 6.9 kV reactor coolant pump circuit, such that all reactor coolant pump circuits are demonstrated OPERABLE at
}
least once per 72 months, by performance of:
l (a) A CHANNEL CALIBRATION of the associated protective relays, j
Surveillance Instruction SNP SI-256, and l
l (b) An integrated system functional test which includes simulated 1
automatic actuation of the systern and verifying that each j
relay and associated circuit breakers and control circuits function as designed using Suvveillance Instruction SNP SI-257.
I SEQUOYAH - UNIT 1 3/4 8-15 Amendment No. 42 f
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ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
(c) For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 1 of the l
circuit breakers of the inoperable type shall aise ce functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested per Surveillance Instruction SNP SI-257.
2.
By selecting and functionally testing a representative sample of at least 10% of each type of lower voltage circuit breakers.
Circuit breakers selected for functional testing shall be selected on a rotating basis.
The functional test, Surveillance Instruction SNP SI-258, shall consist of injecting a current input at the specified setpoint to each selected circuit breaker and verifying that each circuit breaker functions as designed.
Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation.
For each circuit breaker found i
l inoperable during these functional tests an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.
3.
By selecting and functionally testing a representative sample of each type of fuse on a rotating basis.
Each representative sample of fuses shall include at least 10% of all fuses of that type.
The functional test, Surveillance Instruction SNP SI-270, shall consist l
of a non-destructive resistance measurement test which demonstrates that the fuse meets its manufacturer's design criteria.
Fuses found inoperable during these functional tests shall be replaced with OPERABLE fuses prior to resuming operation.
For each fuse found inoperable during these functional tests, an additional representative sample of at least 10% of all fuses of that type shall be functionally tested until no more failures are found or all fuses of that type have been functionally tested.*
b.
At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with Surveillance Instruction SNP SI-266 in conjunction with its manufacturer's recommendations.
i
- Surveillance requirement 4.8.3.1.a.3 may be suspended entil the completion of Cycle 2 provided that the following surveillance requirement is implemented:
A fuse inspection and maintenance program will be maintained to ensure that:
{
1.
The proper size and type of fuse is-installed.
2.
The fuse shows no sign of deterioration, and 3.
'The fuse connections are tight and clean.
SEQUOYAH - UNIT 1 3/4 8-16 Amendment No. 42 l
i
Pages 3/4 8-17 through 3/4 8-33 for Table 3.8-1 are deleted.
1 l
l l
SEQUOYAH - UNIT 1 3/4 8-17 Amendment No. 42 l
s
3/4.11 RADI0 ACTIVE EFFLUENTS
{
3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released to unrestricted areas (see Figure 5.1-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissgived or entrained noble gases, the concentration shall be limited to 2 x 10 microcuries/ml total activity.
APPLICABILITY:
At all times.
ACTION:
With the concentration of radioactive material released to unrestricted areas exceeding the above limits, without delay, restore the concentration to within the above limits.
SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.
2 i
4.11.1.1.2 The results of the radioactivity analysis shall be used in accor-dance with the methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Specification 3.11.1.1.
l l
l SEQUOYAH - UNIT 1 3/4 11-1 Amendment No.
TABLE 4.11-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Liquid Release Sampling Analysis Type of Activity Detection {LLD)
Type Frequency Frequency Analysis (pCi/ml)
A. Batch Waste P
P
-7 Release Each Batch Each Batch Principa) Gamna 5x10 d
Tanks Emitters
- 1. Waste Con-densate
-6 Tanks (3)
I-131 1x10
-5
- 2. Cask Decon-P M
Dissolved and 1x10 tamination One Batch /M Entrained Gases Tank (Gamma emitters)
- 3. Laundry Tanks (2) p g
H-3 1x10 b
- 4. Chemical Each Batch Composite
_7 Drain Tank Gross Alpha 1x10
- 5. Monitor Tank
- 6. Distillate Tanks (/)
-8 P
(
Sr-89, Sr-90 5x10 g
- 7. Condensatu Each Batch Composite-
-6 Demineralizer Fe-55 1x10 Waste Evaporator l
Blowdown Tank (1)
~7 l
B. Continuous' D
W Principa} Gamma 5x10 I
Releases Grab Sample Composite Emitters c
- 1. Steam l
h
-6 Generator I-131 1x10 Blowdown
-5 M
M Dissolved and 1x10 i
2.
Turbine Grab Sample Entrained Gases l
h Built.ing (Gamma Emitters)
I Sump
-5 D
M H-3 1x10 c
Grab Sample Composite
_y Gross Alpha 1x10 g
-8 D
Q Sr-89, Sr-90 5x10 c
Grab Sample Composite
-6 l
Fe-55 1x10 i
l l
l SEQUOYAH - UNIT 1 3/4 11-2 Amendment lio. 42 l
l
TABLE 4.11-1 (Continued)
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM i
I Minimum Lower Limit of Liquid Release Sampling Analysis Type of Activity Detection {LLD)
Type Frequency Frequency Analysis (mci /ml)
C. Periodic W
Principa} Gamma
'5x10-7 Continuous 9 c
Continuogsh Composite Emitters l
Releases
-6
- 1. Non-Reclaim-I-131 lx10 able Waste i
Tank M9
-5 M
Dissolved and lx10 j
Grab Sample Entrained Gases (Gamma Emitters)
- 2. High Crud i
-5 Tanks (2)
M H-3 lx10 Continuous 9 c
Composite i
- 3. Neutralizer Gross Alpha lx10_y j
qank
-8 j
\\
Q Sr-89, Sr-90 5x10
" Continuous 9 c
Composite
-6 Fe-55 lx10 1
i t
l l
l i
j SEQUOYAH - UNIT 1 3/4 11-3 Amendment No. 42
TABLE 4.11-1 (Continued) l TABLE NOTATION The LLD is defined for the purpose of these specifications as the smallest a.
concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability 4,
with only a 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 s LLD =
b E
V 2.22x10' Y " exp (-A.at)
~
Where:
i LLD is the "a priori" lower limit of detection as defined above i
in microcurie per unit mass or volume, l
l s
is the standara deviation of the background counting rate or of u
tMe counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency as counts per disintegration, l
l V is the sample size in units of mass or volume, j
2.22 x 105 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
4 l
A is the radioactive decay constant for the particular radionuclide, and i
at from plant effluents is the elapsed time between midpoint of. sample l
collection and time of counting (midpoint).
It should be recognized that the LLD is defined as an a priori (before I
the fact) limit representing the capability of a measurement system j
and not an'a posteriori (after the fact) limit fo" a particulate l
measurement.
l l
SEQUOYAH - UNIT 1 3/4 11-4 Amendment No.42
- =. _._ -..=-.-
TABLE 4.11-1 (Continued) f TABLE NOTATION b.
A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
Prior to analyses, all samples taken for the composite shall be c.
throughly mixed in order for the composite sample to be represen-
{
tative of the effluent release.
i d.
A batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in the ODCM, to j
assure representative sampling.
A continuous release is the discharge of liquid wastes of a nondiscrete e.
{
volume; e.g., from a volume of system that has an input flow during i
the continuous release.
i f.
The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:
Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 shall also be measured with an LLD of 5 x 10 s.
This list does not mean that only t
1 these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
g.
Releases from these tanks are continuously composited during releases.
i With the composite sampler or the sampler flow monitor inoperable, the sampling frequency shall be changed to require representive batch samples from each tank to be released to be taken prior to release i
and manually composite for these analyses.
I l
h.
Applicable only during periods of primary to secondary leakage or the release of radioactivity as detected by the effluent radiation monitor i
provided the radiation monitor setpoint i,s at a LLD of $1 x 10 s pCf/ml and allowing for background radiation during periods when primary to secondary leakage is not occurring.
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SEQUOYAH - UNIT 1 3/4 11-5 Amendment No. 42 I
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. -....._ _ _..____ _._____. _.~. _._ _ - - -.,. -.. _.._
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4 RADIOACTIVE EFFLUENTS l
DOSE LIMITING CONDITION FOR OPERATION j
3.11.1.2 The dose or dose commitment to a member of the public from radioactive
{
materials in liquid effluents released to unrestricted areas shall be limited from each reactor unit:
I a.
During any calendar quarter to less than or equal to 1.5 mrem to the
}
total body and to less than or equal to 5 mrem to any organ, and r
j b.
During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ, t
APPLICABILITY:
At all times.
ACTION:
i a.
With the calculated dose from t' a release of radioactive materials i
in liquid effluents exceeding any of the above limits, in lieu of a Licensee Event Report (LER), prepsre and submit to the Commission i
within 30 days, pursuaat to Specification 6.9.2, a Special Report
't which identifies the cause(s) for exceeding the limit (s) and defines I
the corrective actions that have been taken to reduce the releases j
and the proposed corrective actions to be taken to assure that subse-quent 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 j
on finished drinking water supplies with regard to the requirements of 40 CFR 141.*
b.
The provisions of specifications 3.0.3 and 3.0.4 are not applicable.
i I
I SURVEILLANCE REQUIREMENTS i
e i
j 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.
" Applicable only if drinking water supply is taken from the receiving water body within three miles downstream of the plant discharge.
I l
l SEQUOYAH - UNIT 1 3/4 11-6 Amendment No. 42 i
RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT l
LIMITING CONDITION F0P OPERATION 3.11.1.3 The liquid radwaste trest =cnt systeni shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the pro-fected doses due to the liquid effluent to unrestricted areas (see Figure 5.1-1) would exceed 0.06 mrem to the total body
- or 0.2 mrem to any organ
- in a 31-day period.
APPLICABILITY:
At all times.
ACTION:
With radioactive liquid waste being discharged without treatment and a.
in excess of the above limits, in lieu of an LER, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:
1.
Identification of the inoperable equipment or subsystems and the reason for inoper:bility, 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 Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS i
4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with the methodology and parameters in the ODCM.
l l
l i
l
- Per reactor unit SEQUOYAH - UNIT 1 3/4 11-7 Amendment No. 42
RADI0 ACTIVE EFFLUENTS LIQUID HOLDUP TANKS
~
LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the fol-lowing tanks shall be limited by the following expression:
concentration of isotope i y
,700
<6
. maximum permissible I concentration of isotope i excluding tritium and dissolved or entrained noble gases.
a.
Condensate Storage Tank b.
Steam Generator Layup Tank c.
Outside temporary tanks for radioactive liquid APPLICABILITY:
At all times.
ACT:0N:
With the quantity of radioactive material in any of the above listed a.
tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
I SEQUOYAH - UNIT 1 3/4 11-8 Amendment No. 42 L
RADI0 ACTIVE EFFLUENTS 3/4.11.2 GASE0US EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents to areas at or beyond the site boundary (unrestricted area) (see Figure 5.1-1) shall be limited to the following:
a.
For noble gases:
Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin, and b.
For Iodine-131, Iodine-133, Tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:
Less than or equal to 1500 mrem /yr to any organ.
APPLICABILITY:
At all times.
ACTION:
With the dose rate (s) exceeding the above limits, without delay restore the l
release rate to within the above limit (s).
SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.
4.11.2.1.2 The dose rate due to I-131, I-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 speci-fied in Table 4.11-2.
)
1
)
SEQUOYAH - UNIT 1 3/4 11-9 Amendment No. 42
I M
TABLE 4.11-2 RADI0 ACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Sampling Analysis Type of Detection (glD)
E Gaseous Release Type Frequency Frequency Activity Analysis (pCi/ml)
P P
-4 H
A.
Waste Gas Storage Each Tank Each Tank Principal Gamma Emitters 9 1x10 Tank Grab B. Containment pi Di Principal Gamma Emitters 9 1x10
- 1. Purge Each Purge Each Purge H-3 1x10 Grab Sample 1x10j
- 2. Vent Dj Dj Principal Gamma Emitters 9 Each Day Each Day H-3 1x10 R
C.
Noble Gases and M
M Principal Gamma Emitters 9 1x10-4 g
Tritium Grab i
1.CondensgrVacuum Sample
-6 H-3 1x10 Exhaust 2.Auxillagy, Building Exhaust '
- 3. Service Building Exhaust 4.Shieldgufiging Exhaust
- D.
Iodine and Parti-Continuous #
W I-131 1x10 d
-12 culates Sampler Charcoal l
- 1. Auxiliary Building Sample
, {
Exhaust f
d 9
-II Continuous W
Principal Gamma Emitters 1x10 R
- 2. Shield Building Sampler Particulate (I-131, Others)
E Exhaust Sample I
I g
TABLE 4.11-2 (Continued) g RADI0 ACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM s
ac Minimum Lower Limit of Sampling Analysis Type of Detection (glD) g Gaseous Release Type Frequency Frequency Activity Analysis (pCi/ml)
U Continuous #
M Gross Alpha 1x10"Il H
Composite Sampler Particulate Sample I
I Continuous Comp 9 site Sr-89, Sr-90 1x10 Sampler Particulate Sample E.
Noble Gases all Continuous #
Noble Gas Noble Gases 1x10-6 Releases types as Monitor Monitor Gross Beta or Gamma mg listed in C l
0 F
g-
TABLE 4.11-2 (Continued)
TABLE NOTATION The LLD is defined, for the purposes of these specifications, as the a.
smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% proba-bility with only a 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measure ~ent system (which may include radiochemical m
separation):
4.66 s LLD =
E V
2.22x106 Y
exp (A.at) l Where:
LLD is the "a priori" lower limit of detection as defined above in microcurie per unit mass or volume, I
is the standard deviation of the background counting rate or of s h tne counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collection and time of counting (midpoint).
It should be noted that the LLO is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
SEQUOYAH - UNIT 1 3/4 11-12 Amendment No. 42
Y TABLE 4.11-2 (Continued) i TABLE NOTATION b.
Sampling and analysis shall also be performed following shutdown, j
startup, or a thermal power change exceeding 15% of rated thermal power within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> unless (1) analysis shows that the dose equiva-lent I-131 concentration in the primary coolant has not increased more than a factor of 3 and (2) the noble gas activity monitor shows that the effluent activity has not increased by more than a factor of 3.
l c.
Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.
d.
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from
} -
sampler).
Sampling 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 2 days following each shutdown from 215% RATED THERMAL t
POWER, startup of 213% RATED THERMAL POWER or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in one hour and analyses shall l
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 j
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 LLD's may be increased j
by a factor of 10.
Tritium grab samples shall be taken at least once per 7 days from e.
the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
f.
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 s
]
calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.
i g.
The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for noble gases and Mn-54, Fe-59, I-131, j
Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for i
particulate principal gamma emitters.
This list does not mean that only these nuclides are to be detected and reported.
Other gamma l
peaks which are measureable and identifiable, together with the above nuclides, shall also be analyzed and reported in the Semi-annual l
Radioactive Effluent Release Report pursuant to Specification 6.9.1.12.
]
h.
During releases via this exhaust system.
i.
Purging - Applicable in MODES 1, 2, 3 and 4, the upper and lower com-i partments of the containment shall be sampled prior to PURGING.
Prior I
to breaking containment integrity in MODE 5 or 6, the upper and lower i
compartments of the containment shall be sampled.
The incore instru-I ment room purge sample shall be obtained at the shield building exhaust between 20 and 25 minutes following initiation of the incore instrument l
room purge.
I SEQUOYAH - UNIT 1 3/4 11-13 Amendment No. 42
...-,.,.,.--,,,._,,,_,,...,..,.,,n.m--,v.,,.
n,,,.
o.,,,e,-,,.
+ m n e..
,,n,..-..e.-,--,,,,,.o,,
..r.
i TABLE 4.11-2 (Continued)
TABLE NOTATION
~j.
Venting - Applicable in MODES 1, 2, 3, and 4; the containment will be vented to the containment annulus and then to the auxiliary building via containment annulus fans.
The lower containment compartment shall be sampled daily when venting is to occur to account for the radio-activity being discharged from the venting process.
1 a
i i
i t
l SEQUOYAH - UNIT 1 3/4 11-14 Amendment No. 42 l
t RADI0 ACTIVE EFFLUENTS DOSE - NOBLE GASES i
LIMITING CONDITION FOR OPERATION l
3.11.2.2 The air dose due to noble gases released in gaseous effluents from l
each reactor unit to areas at or beyond the site boundary (see Figure 5.1-1)
[
shall be limited to the following:
l a.
During any calendar quarter:
Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, 1
i b.
During any calendar year:
Less than or equal to 10 mrad for gamma
}
radiation and less than or equal to 20 mrad for beta radiation.
l APPLICABILITY: At all times.
i l
ACTION 1
i a.
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of a Licensee Event Report (LER), prepare and submit to the Commission within i
30 days, pursuant to Specification 6.9.2, a Special Report which I
identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and l
the proposed corrective actions to be taken to assure that subsequent j
releases will be in compliance with the above limits.
i b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
i
)
i l
SURVEILLANCE REQUIREMENTS l
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.
4 l
i "Per reactor unit.
l l
I l.
SEQUOYAH - UNIT 1 3/4 11-15 Amendment No. 42 l
-w-,7-nc-,,,,-7..-4--.-,,=~m-m---gw-r--
e-.'-,yv,rr
-w-,,rw,.,weg-,--w m pw-
.--w, + =
,,,,,emer--www,-ww.,--g-#w-wey-eve y.cww w w-m e v.---twew, w
-,w i r, e vw,vrv wweven u
- RADIOACTIVE EFFLUENTS DOSE - I-131, I-133, TRITIUM, AND RADIONUCLIOES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from I-131, I-133, Tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at or beyond the site boundary (see Figure 5.1-1) shall be limited to the following from each reactor unit:
a.
During any calendar quarter:
Less than or equal to 7.5 mrem to any organ and, b.
During any calendar year:
Less than or equal to 15 mrem to any organ.
APPLICABILITY:
At all times.
ACTION:
With the calculated' dose from the release of I-131, I-133, tritium, a.
and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of an LER, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases 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 Specifications 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 I-131, I-133, tri, tium, and radionuclides in particu-late form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the 00CM at least once per 31 days.
SEQUOYAH - UNIT 1 3/4 11-16 Amendment No. 42 l
l
RADIOACTIVE EFFLUENTS GASE0US RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASE0US RA0 WASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases to areas at or beyond the site boundary (see Figure 5.1-1), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation
- and 0.4 mrad for beta radiation.* The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be ue:d to reduce radioactive mate-rials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases to areas at or beyond the site boundary (see Figure 5.1-1) when averaged over 31 days would exceed 0.3 mrem to any organ.*
APPLICABILITY:
At all times.
l ACTION:
With the gaseous waste being discharged without treatment for more a.
than 31 days and in excess of the above limits, in lieu of a Licensee Event Report (LER), prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:
1.
Identification of the inoperable equipment or subsystems and 1
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 Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the methodology and parameters in 1
the 00CM.
"These doses are per reactor unit.
SEQUOYAH - UNIT 1 3/4 11-17 Amendment No. 42
RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by voluma.
APPLICABILITY:
At all times.
ACTION:
With the concentration of oxygen in a waste gas holdup tank greater a.
than 2% by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
b.
With the concentration of oxygen in a waste gas holdup tank greater than 4% by volume and the hydrogen concentration greater than 2% by volume, without delay suspend all additions of waste gases to the l
affected waste gas holdup tank and reduce the concentration of oxygen to less than or equal to 2% by volume without delay.
l The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentration of hydrogen and oxygen in the waste gas holdup system shall be determined to be within the above limits by monitoring the waste gas additions to the waste gas holdup system with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10.
SEQUOYAH - UNIT 1 3/4 11-18 Amendment No.
42
.__ _ ____=_.
r RADI0 ACTIVE EFFLUENTS GAS DECAY TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas decay tank shall I
be limited to less than or equal to 50,000 curies of noble gases (considered as Xe-133).
I APPLICABILITY:
At all times.
l ACTION:
With the quantity of radioactive material in any gas decay tank a.
exceeding the above limit, without delay suspend all additions of l
radioactive material to the tank and within 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />'s reduce the tank contents to within the lir.it.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas decay tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank.
i 4
i 1
i I
i j
SEQUOYAH - UNIT 1 3/4 11-19 Amendment No. 42
RADIOACTIVE EFFLUENTS 3/4.11.3 SOLID RADI0 ACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3 The solid radwaste system shall be used in accordance with a PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet shipping and burial ground requirements.
APPLICABILITY: At all times.
ACTION:
With the provisions of the Process Control Program not satisfied, a.
suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site.
~
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SEQUOYAH - UNIT 1 3/4 11-20 Amendment No. 42
RADI0 ACTIVE EFFLUENTS SURVEILLANCE REQUIREMENTS (Continued) 4.11.3.1 THE PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICA-TION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions).
If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICA-a.
TION of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION.
SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM.
b.
If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate SOLIDIFICATION.
The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste.
t SEQUOYAH - UNIT 1 3/4 11-21 Amendment No. 42
1 j
RADIOACTIVE EFFLUENTS i
3/4.11.4 TOTAL DOSE f
LIMITING CONDITION FOR OPERATION 1
3.11.4 The annual (calendar year) dose or dose commitment to any member of the l
public, due to releases of radioactivity from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem).
APPLICABILITY:
At all times.
i ACTION:
With the calculated doses from the release of radioactive materials a.
in liquid or gaseous effluents exceeding twice the limits of Specifica-l tions 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a 3.11.2.2.b, 3.11.2.3.a, or 1'
3.11.2.3.b, calculations should be made to determine if the above
}
limits have been violated.
If such is the case, in lieu of an LER, prepare and submit a Special Report to the Director, Nuclear Reactor 1
Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.11.4.
This Special Report, as defined in 10 CFR 20.405c shall include an analysis which estimates the radia-l tion exposure (, dose) to a member of the public from uranium fuel cycle 1
sources (including all effluent pathways and direct radiation) for a calendar year that includes the release (s) covered by this report.
If i
the estimated dose (s) exceeds the limits of Specification 3.11.4, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the S;scial Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of g 190.11(b).
Submittal of i
the report is considered a timely request, and a variance is granted until staff action on the request is complete.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
4 SURVEILLANCE REQUIREMEhis 4.11.4 Cumulative dose contributions from liquid and gaseous. effluents shall i
be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the 00CM.
1
)
SEQUOYAH - UNIT 1 3/4 11-22 Amendment No. 42 i
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.
j APPLICABILITY:
At all times.
i ACTION:
g
)
With the radiological environmental monitoring program not being con-a.
ducted as specified in Table 3.12-1, in lieu of a LER, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of ^he reasons for not conducting the program as required and the plans for preventing a recurrence.
b.
With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 3.12-2 when averaged over any j
calendar quarter, in lieu of any other report required by Specifica-tion 6.9.1, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter a Report pursuant to Speci-fication 6.9.2, a special report that identifies the cause(s) for ex-ceeding 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 specifications of 3.11.1.2, 3.11.2.2, and 3.11.2.3.
When more than one of the radionuclides in Table 3.12-2 is detected in the sampling medium, this report shall be submitted if:
concentration (1) concentration (2) + ***> 1.0
{
limit level (1) limit level (2)
When radionuclides other than those in Table 3.12-2 are detected and are the result of' plant effluents, this report shall be submitted if the potential annual dose to a member of the public is equal to or l
4 greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.
This report is not required if the measured level of radicactivity 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.
c.
With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1, identify loca-tions for obtaining replacement samples and add them to the radio-logical environmental monitoring program within 30 days.
The specific locations from which samples sere unavailable may then be deleted from the monitoring program.
In lieu of a Ifcensee event report (LER) and pursuant to Specification 6.9.2, identify the cause(s) of the unavailablity of samples and identify the new locations for obtaining i
SEQUOYAH - UNIT 1 3/4 12-1 Amendment No. 42
=-
RADIOLOGICAL ENVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION (Continued) replacement samples in the Annual Radiological Environmental Operat-ing Report.
A revised figure (s) and table (s) for the 00CH reflecting the new location (s) shall be included in the next annual radiological effluent release repurt pursuant to Specification 6.9.1.9.
d.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
4 SURVEILLANCE REQUIREMENTS i
i 4.12.1 The radiological environmental monitoring samples shall be co71ected pursuant to Table 3.12-1 from the locations given in the table and figJre in the ODCM and shall be analyzed pursuant to the requirements of Table 3.12-1 j
and the detection capabilities required by Table 4.12-1.
l 1
i 1
l i
f l
4 1
i 1
I i
j i
I SEQUOYAH - UNIT 1 3/4 12-2 Amendment No. 42 1
=
t TABLE 3.12-2 E
REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONNENTAL SAMPLES 8
5 2
Reporting Levels E
Water Airborne Particulate Fish Milk Food Products y
Analysis (pCf/1) or Gases (pCf/m )
(pC1/Kg, wet).
(pci/1)
(pCf/Kg, wet) 8 (a)
N-3 2 x 104 N.A.
N.A.
N.A.
N.A.
Mn-54 1 x 108 N.A.
3 x 104 N. A.
N.A.
1 Fe-59 4 x 102 N.A.
1 x 104 N.A.
N.A.
Co-58 1 x 108 N.A.
3 x '104 N.A.
N.A.
Co-60 3 x 102 N.A.
- 1 x 104 N. A.
N.A.
9 Zn-65 3 x 102 N.A.
2 x 104 N.A.
N.A.
i m
Zr-Nb-95 4 x 102 N.A.
N.A.
N.A.
N.A.
q I-131 2(b) 0.9 N.A.
3 1 x 102 Cs-134 30 10 1 x 108 60 1 x 103 j
Cs-137 50 20 2 x 108 70 2 x 103 Ba-La-140 2 x 102 N.A.
N.A.
3 x 102 N.A.
i
.N 1
=
(a) For drinking water samples.
This is 40 CFR Part 141 value.
If no drinking water pathway exists, I
a value of 30,000 pCi/1 may be used.
s.
(b) If no drinking water piathway exists, a value of 20 pCi/1 may be used.
?.
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TABLE 4.12-1 MAXINUN VALUES FOR THE LOWER LINITS OF DETECTION (LLD)a,b l.
S!N Airborne Particulate Water or Gas Fish Milk Food Products Sediment E
Analysis (pC1/1)
(pCi/m )
(pCi/kg, wet)
(pCf/1)
(pCf/kg, wet)
(pci/kg, dry) 2 Q
gross beta 4
1 X 10-2 N.A.
N.A.
N.A.
N.A.
s H-3 2000*
N.A.
N.A.
N.A.
N.A.
N.A.
l Mn-54 15 N.A.
130 N.A.
N.A.
N.A.
Fe-59 30 N.A.
260 N.A.
N.A.
N.A.
Co-58,60 15 N.A.
130 N.A.
N.A.
N.A.
Zn-65 30 N.A.
260 N.A.
N.A.
N.A.
Zr-95 30 N.4.
N.A.
N.A.
N.A.
N.A.
u Nb-95 15 N.A.
N.A.
N.A.
N.A.
N.A.
an I-131 1
7 X 10 2 N.A.
1 60 N.A.
l Cs-134 15 5 X 10-2 130 15 60 150 Cs-137 18 6 X 10-2 150 18 80 180 Ba-140 60 N.A.
N.A.
60 N.A.
N.A.
La-140 15 N.A.
N.A.
15 N.A.
N.h.
R
- If no drinking water pathway exists, a value of 3000 pCf/1 may be used.
,a.
- If no drinking water pathway exists, a value..' 15 pC1/1 may be used.
5
.E
TABLE 4.12-1 (Continued)
TABLE NOTATION The LLD is defined, for the purposes of these specifications, as the a.
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 a 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66sb LLO = E V
2.22 Y
exp(-A.at)
Where:
LLD is the "a priori" lower limit of detection as defined above in picocurie per unit mass or volume, l
is the standard deviation of the background counting rate or ss of the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency as counts per disintegration, V is the sample size (in units of mass or volume),
2.22 is the number of disintegrations per minute per picocurie, l
Y is the fractional radiochemical yield (when applicable),
A is the radioactive decay constant for the particular radionuclide, and at for environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of counting.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analysis will be performed in such a manner that the stated LLDs will be achieved under routine conditions.
SEQUOYAH - UNIT 1 3/4 12-8 Amendment No.
42
TABLE 4.12-1 (Continued)
/
TABLE NOTATION 4
i I' (
b.
Other peaks which are measurable and identifiable, together with the radionuclides in Table 4.12-1, shall be identified and reported.
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$EQUDYAN - UNIT 1
'3/4 12-9 Amendment No. 42 1
t e
e
RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERAT!0N 3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden
- of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.
(For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.)
APPLICABILITY:
At all times.
l ACTION:
With a land use census identifying a location (s) which yields a a.
calculated dose or dose commitment greater than the maximum values currently being calculated in Specification 4.11.2.3.1, in lieu of a licensee event report (LER), identify the new location (s) in the next Annual Radiological Environmental Operating Report pursuant to specification 6.9.1.7.
b.
With a land use census identifying a location (s) which yields a cal-culated dose or dose commitment (via the same exposure pathway) 20 percent greater than the highest calculated dose or dose coinmit-ment at a location from which samples are currently being obtained in accordance with Specification 3.12.1, in lieu of a licensee event re-port (LER) identifying the new location (s) in the Annual Radiological Environmental Operating Report and include the revised ODCM table (s) and figure (s).
The new location shall be added to the radiological environmental monitoring program within 30 days, if the owner consents.
The sampling location, excluding the control station location, having the lowest calculated dose or dose commitment (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.
The provisions cf Specifications 3.0.3 and 3.0.4 are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted at least once per calendar year between the dates of April 1 and October 1 using the following techniques:
1.
Within a 2 mile radius from the plant or within the 15-arem/ year isodose line, whichever is larger, enumeration by a door-to-door or equivalent counting technique.
2.
Within a 5-mile radius from the plant, enumeration by using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or-other reliable sources.
" Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.
SEQUOYAH - UNIT 1 3/4 12-10 Amendment No. 42
i q
i RADIOLOGICAL ENVIRONMENTAL MONITORING
)
3/4.12.3 INTERLABORATORY COMPARISON PROGRAM l.
LIMITING CONDITION FOR OPERATION I
3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.
~
APPLICABILITY:
At all times.
i ACTION:
)
With analyses not being performed as required above, report the a.
corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
t b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS i
4.12.3 A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with the ODCM shall be j
included in the Annual Radiological Environmental Operating Report.
i I
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i SEQUOYAH - UNIT 1 3/4 12 *'
Amendment No. 42 i
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3/4.11 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 LIOUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radio-active materials released in liquid waste effluents to unrestricted areas will l
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 l
result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR 50, to a member of the public and (2) the limits of 10 CFR 20.106(e) to
[
the population.
The concentration limit for dissolved or entrained noble gases l_
is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
~-
i 3/4.11.1.2 DOSE This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50.
The Limiting Condition for Operation implements the guides set forth in Section II. A of Appendix I.
The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of Appendix I to 4
assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable".
Also, for fresh water sites with drinking water supplies which 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 wter that are in excess of the requirements of 40 CFR 141.
The dose calculations 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 procedares based on models and data, such that the actual exposure of a member of the public through l
appropriate pathways is unlikely to be substantially underestimated.
The equa-tions 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 Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
This specification applies to the release of liquid effluents from each 1
reactor at the site.
For units with shared radwaste treatment systems, the
(
liquid effluents from the shared system are proportioned among the units sharing that system.
SEQUOYAH - UNIT 1 B 3/4 11-1 Amendment No.42
RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1.3 LIQUID WASTE TREATMENT The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable".
This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of the liquid radwaste treat.nent 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.
3/4.11.1.4 LIQUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.
3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure t!.: 1
, ie dose at any time at the site boundary from gaseous effluents from all un:., on the site will be within the annual dose limits of 10 CFR Part 20.
The annual dose limits are the doses l
associated with the concentrations of 10 CFR Part 20, ap;endix B, Table II, Column 1.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the expcsure of a member of the public, either within or outside the site boundary, to ennual average con-centrations exceeding the Ifmits 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 l
within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary.
The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an in-dividual at or beyond the site boundary to less than or equal to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year to the skin.
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to less than or equal to 1500 mrem / year for the nearest cow to the plant.
i SEQUOYAH - UNIT 1 B 3/4 11-2 Acu% nt Wo. 42 i
RADI0 ACTIVE EFFLUENTS BASES This specification applies to the release of gaseous effluents from all reactors 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.
3/4.11.2.2 DOSE, N0BLE GASES This specification is provided to implement the requirements of Sections II.8, III.A and IV.A of Appendix I, 10 CFR Part 50.
The Limiting Condition for Opera-tion implements the guides set forth in Section II.B of Appendix I.
The ACTION statements provide the required operating flexibility and at the same time im-piement the guides set forth in Section IV. A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable".
The Surveillance Requirerents implement the require-ments in Section III. A of Appendix I that conformance with the guides of Appendix I be sMwn by calculational procedures based on models and data such that the actual exposure of a member of the public through appropriate pathways l
is unlikely to be substantially underestimated.
The dose calculations estab-lished in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the meth-odology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Com-pliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regula-tory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors,"
Revision 1, July 1977.
The ODCM equations provided for determining the air doses at the site boundary are based upon the historical average atmospheric conditions.
3/4.11.2.3 DOSE - IODINE-131, TRITIUM, AND RADIONUCLIDES This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50.
The Limiting Conditions for Opera-tion are the guides set forth in Section II.C of Appendix I.
The ACTION state-ments provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reason-ably achievable".
The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that con-formance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.
The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodologies provided in NUREG/CR-1004, "A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides," October 1979 and SEQUOYAH - UNIT 1 8 3/4 11-3 Amendment No. 42
(
RADI0 ACTIVE EFFLUENTS BASES Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Re-l 1 eases 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 Efflu-ents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.
These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.
The re1 case rate specifications for I-131, Tritium, and Radionuclides in particulate form with half-lives greater than 8 days are dependent on the existing radionuclide pathways to man, beyond the site boundary.
The pathways which were examined in the development 3
of these calculations were:
- 1) individual inhalation of airborne radionuclides,
- 2) deposition of radionuclides onto green leafy vegetation with subsequent con-i sumption 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.
3/4.11.2.4 GASEOUS RADWASTE TREATMENT 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".
3 This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50.
The specified ifmits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of poten-tially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen.
Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled j
in conformance with the requirements of General Design Criterion 60 of Appendix A i
to 10 CFR Part 50.
l 4
1 SEQUOYAH - UNIT 1 B 3/4 11-4 Amendment No. 42 i
RADIOACTIVE EFFLUENTS BASES 3/4.11.2.6 GAS DECAY TANKS Restricting the quantity of radioactivity contained in each gas decay tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the i
nearest exclusion area boundary will not exceed 0.5 rem.
This is consistent with Standard Review Plan 15.7.1, " Waste Gas System Failure".
3/4.11.3 SOLID RADIOACTIVE WASTE This specification implements the requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50.
The process para-meters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste / liquid / solidification agent / catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.
3/4.11.4 TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR 190.
The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I.
For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level.
The Special Report will describe a course of action which should result in the limitation of dose to a member of the public i
for 12 consecutive months to within the 40 CFR 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 5 miles must be considered.
4
}
SEQUOYAH - UNIT 1 B 3/4 11-5 Amendment No. 42
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BA5ES 3/4.12.1 MONITORING PROGRAM The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure path-ways and for those radionuclides, which lead to the highest potential radiaticn exposures of individuals resulting from the station operation.
This monitoring program 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 measure-ments and modeling of the environmeltal exposure pathways.
The initially speci-fied monitoring program will be effective for at least the first three years of commercial operation.
Following this period, program changes may be initiated based on operational experience.
The LLDs required by Table 4.12-1 are considered optimum for routine l
environcantal measurements in industrial laboratories.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routir.e conditions.
Occasionally background fluctuations, unavoidably small sample sizes, the pre-sence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors will be iden-tified and described in the Annual Radiological Environmental Operating Report.
4 3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this census.
The best survey information from the door-to-door, aerial or 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 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.
To determine this minimum garden size, the following assumptions were used,
- 1) that 20% of the garden was used for growing broad leaf vegetation (i.e.,
similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter.
SEQUOYAH - UNIT 1 8 3/4 12-1 Amendment No.
42
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ADMINISTRATIVE CONTROLS The Site Radiological Emergency Plan and implementing procedures at e.
least once per 12 months.
f.
The Plant Physical Security Plan, the Safeguards Contingency Plan, and implementing procedures at least once per 12 months.
g.
Any other area of unit operation considered appropriate by the NSRB or the Manager of Power.
h.
The Facility Fire Protection Program and implementing procedures at least once per 24 months.
i.
An independent fire protection and loss prevention program inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.
j.
An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
k.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
1.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
m.
The PROCESS CONTROL PROGRAM and implementing procedures for SOLIDIFICATION of radioactive wastes at least once per 24 months.
The performance of activities required by the Quality Assurance n.
Program to meet the criteria of Regulatory Guide 4.15, December 1977 or Regulatory Guide 1.21, Rev. 1, 1974 and Regulttory Guide 4.1, Rev.1,1975, at least once per 12 months.
AUTHORITY 6.5.2.9 The NSRB shall report to and advise the Manager of Power on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Records of NSRB activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each NSRB meeting shall be prepared, approved and forwarued to the Manager of Power within 14 days following each meeting.
b.
Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Manager of Power within 14 days following completion of the review.
SEQUOYAH - UNIT 1 6-12 Amendment No. 42
ADMINISTRATIVE CONTROLS c.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the PORC.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, the NSRB and the Director, Nuclear Power Division within 14 days of the violation.
6.8 PROCEDURES & PROGRAMS 6.6.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.
b.
Refueling operations.
c.
Surveillance and test activities of safety-related equipment.
d.
Plant Physical Security Plan implementation.
e.
Site Radiological Emergency Plan implementation.
f.
Fire Protection Program implementation.
g.
PROCESS CONTROL PROGRAM implementation.
h.
Quality Assurance Program for effluent monitoring, using the guidance contained in Regulatory Guide 4.15, December 1977, or Regulatory Guide 1.21, Rev. 1, 1974 and Regulatory Guide 4.1, Rev. 1, 1975.
6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the PORC and approved by the Plant Superir.tendent prior to implementation and reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered, b.
It'e change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
The change is documented, reviewed by the PORC and approved by the c.
Plant Superintendent within 14 days of implementation.
6.8.4 Written procedures shall be established, implemented and maintained by the Radiological Hygiene Branch covering the activities below:
a.
OFFSITE DOSE CALCULATIONAL MANUAL implementation.
SEQUOYAH - UNIT 1 6-15 Amendment No.
42
ADMINISTRATIVE CONTROLS b.
Quality Assurance Program for environmental monitoring, using the guidance contained in Regulatory Guide 4.15, December 1977.
Surveillance requirements and environmental monitoring requirements c.
shown in Table 6.1-1.
6.8.5 The following programs shall be established, implemented, and maintained:
a.
Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.
The systems include the charging system, safety injection system, residual heat removal syst o, chemical and volume control system, containment spray system, iodine cleanup system, and hydrogen recombiner system.
The program shall include the following:
(i) Preventive maintenance and periodic visual inspection requirements, and (ii)
Integrated leak test requirements for each system at refueling cycle intervals or less.
b.
In-Plant Radiation Monitoring A program which will ensure the capability to accurately deterr.;ine the airborne iodine concentrations in vital areas under accident conditions.
This program shall include the following:
(i), Training of personnel,
^
(ii) Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analysis equipment.
c.
Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation.
This program shall include:
(i) Identification of a sampling schedule for the critical variables and control points for these variables, (ii) Identification of the procedures used to measure the values of the critical variables, (iii) Identification of process sampling points, SEQUOYAH - UNIT 1 6-15a Amendment No.
42
ADMINISTRATIVE CONTROLS l
ANNOALREPORTS1/
}
6.9.1.4 Annual reports covering the activities of the unit as described below 4
for the previous calendar year shall be submitted prior to March 1 of each i
i year. The initial report shall be submitted prior to March 1 of the year following initial criticality.
~
3 6.9.1.5 Reports required on an annual basis shall include a tabulation on an j
annual basis for the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mre
[
manremexporureaccordingtoworkandjobfunctions,gyrandtheirassociated e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.
The dose assignment i
to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be A
assigned to specific major work functions.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORTS!
1 i
6.9.1.6 The radiological environmental operating reports covering the i
operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.
~
6.9.1.7 The annual radiological environmental operating reports shall include summaries, interpretations, and an anlysis of trends of the results of the l
radiological environmental surveillance activities for the report period, including a comparision with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment 1
of the observed impacts of.the plant operation on the environment.
The reports shall also include the results of land use censuses required by Specification 3.12.2 and a listing of the new locations for dose calculations and/or environ-mental monitoring identified by the land use census.
If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problems and a planned course of action to alleviate 4
the problem.
1/ A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the station.
4 2/ This tabulation supplements the requirements of 9 20.407 of 10 CFR Part 20.
j 3/ A single submittal may be made for a multiple unit station.
The submittal i
should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall l
specify the releases of radioactive material from each unit.
SEQUOYAH - UNIT 1 6-17 Amendment No.42
i ADMINISTRATIVE CONTROLS The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
The reports shall also include the following:
a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3.
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORTM 6.9.1.8 The semiannual radioactive effluent release report covering the opera-l tion of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.
The period of the first report shall begin with the date of initial criticality.
6.9.1.9 Semiannual radioactive effluent release reports shall include a summary l
of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evalua-ting, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis fol-lowing the format of Appendix B thereof.
The annual radioactive ef fluent release report (Radiological Impact) to be sub-l mitted 60 days after January 1 of each year shall include an annual summary of hourly ueteorological data collected over the previous year.
This annual summary may b.e either in the form of an hour-by-hour listing of wind speed, wind direc-tion, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.* This same report shall include an assessment of the l
radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.
This same rr. port shall also include an assessment of the radintion doses from radioactive liquid and gaseout effluents to members of the public due to their activities inside the site boundary (Figure 5.1-1) during the report period.
All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports.
The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as y
A single submittal may be made for a multiple 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.
- In lieu of submission with the annual radioactive effluent release report, this summary of required meteorological data may be retained on site in a file that shall be provided to NRC upon request.
I SEQUOYAH - UNIT 1 6-18 Amendment No.42 L
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ADMlNISTRATIVE CONTROLS determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses.
The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
The annual radioactive effluent release report to be submitted after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed members of the public from reactor releases and other nearby ura-nium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Op-eration. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1.
The semiannual radioactive effluent release reports shall include the following information for each type of solid waste identified in Regulatory Guide 1.21, Rev. 1, Table 3, Part A, which is shipped offsite during the report period:
a.
Total volume of containers, b.
Total curie quantity (sr.ecify whether determined by measurement or estimate),
Principal radionuclides (specify whether determined by measurement c.
or estimate),
d.
Type of quantity (e.g., LSA, Type A, Type B, etc.)
The semiannual radioactive effluent release reports shall include unplanned re-leases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis and shall include any changes to the PROCESS CONTROL PROGRAM (PCP) and the Offsite Dose Calculation Manual (ODCM) made during the reporting period.
It shall include the type of solidification agent used, if applicable.
MONTHLY REACTOR OPERAITNG REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or Safety Valves, shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C.
- 20555, with a copy to the Regional Office of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.
Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective.
In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by the PORC.
SEQUOYAH - UNIT 1 6-19 Amendment No.42
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8 ADMINISTRATIVE CONTROLS 6.10.2 The following records shall be retained for the duration of the Unit Operating License:
a.
Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.
b.
Records of r.ew and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c.
Records of radiation exposure for all individuals entering radiation control areas.
d.
Records of gaseous and liquid radioactive material released to the environs.
e.
Records of transient or operational cycles for those unit components identified in Table 5.7-1.
f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the unit staff, h.
Records of in-service inspections performed pursuant to these Technical Specifications.
i.
Records of Quality Assurance activities required by the Operational Quality Assurance Manual.
J.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the PORC, RARC, and the NSRB.
1.
Records of analyses required by the radiological environmental monitoring program.
Records of secondary water sampling and water quality.
m.
Records of the service life monitoring of all safety related n.
hydraulic and mechanical snubbers, required by T/S 3.79, including the maintenance performed to renew the service life.
o.
Records for Environmental Qualification which are covered under the provisions of Paragraph 2.c.(12)(b) of License No. DPR-77.
l 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
i SEQUOYAH - UNIT 1 6-23 Amendment No. 42
ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signel" required by paragraph 20.203(c) (2) of 10 CFR 20, each high radiation area in which the intensity of radiation is great.er than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Special (Radiation)
Work Permit *.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the arsa has been established and personnel have been made knowledgeable of them.
~
An individual qualified in radiation protection procedures who is c.
equipped with a radiation dose rate monitoring device.
This ir.dividual shall be responsible for providing positive control over the activities within the area and shall perform control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Special (Radiation) Work Permit.
6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Engineer on duty and/or the Health Physicist.
6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 Licensee initiated changes to the PCP:
1.
Shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change (s) was made.
This submittal shall contain:
sufficiently detailed information to totally support the rationale a.
for the change without benefit of additional or supplemental information,
" Health Physics personnel or personnel escorted by Health Physics personnel in accordance with approved emergency procedures, shall be exempt from the SWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
SEQUOYAH - UNIT 1 6-24 Amendment No.42
i ADMINISTRATIVE CONTROLS b.
a determination that the change did not reduce the overall con-formance of the solidified waste product to existing criteria for solid wastes; and c.
documentation of the fact that the change has been reviewed and found acceptable by the PORC.
2.
Shall become effective upon review and acceptance by the PORC.
6.14 0FTSITE DOSE CALCULATION MANUAL (0DCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Licensee initiated changes to the ODCM:
1.
Shall be submitted to the Commission in the next Semi-Annual Radio-active Effluent Release Report pursuant to Specification 6.9.1.9.
This submittal shall contain:
a.
sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.
Information submitted shoeld consistent of a package of those pages of the ODCM to be changes with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);
b.
a determination that the change will.not reduce the accuracy or reliability of dose calculations or setpoint determinations; and c.
documentation of the fact that the change has been reviewed and found acceptable by the RARC.
2.
Shall become effective upon review and acceptance by the RARC.
6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous I
and Solid) 6.15.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid):"
1.
Shall be reported to the Commission in the Semi-/nnual Radioactive Effluent Release Report for the period in which the evaluation was reviewd by the PORC.
The discussion of each change shall contain:
A summary of the ev'aluation that led to the determination that a.
the change could be made in accordance with 10 CFR 50.59;
- Submittal of information required by this section may be made as part of the i
annual FSAR update.
SEQUOYAH - UNIT 1 6-25 Amendment No. 42
s TABLE 3.2-1 DNB PARAMETERS
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LIMITS C
E 4 Loops In
]
PARAMETER Operation Reactor Coolant System T,yg 5 583*F Pressurizer Pressure
> 2220 psia *
" Limit not applicable during either a THERMAL POWER ramp in excess of 5% RATED THERMAL POWER w1 per minute or a THERMAL POWER step in excess of 10% RATED THERMAL POWER, physics test, or performance of surveillance requirement 4.1.1.3.b.
m b
t a
t a
F b
f m
ATTACHMENT TO LICENSE AMEN 0 MENT NO. 34 FACILITY OPERATING LICENSE NO. OPR-79 DOCKET NO. 50-328 Replace the following pages of the Appendix "A " Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Amended Page 1-4 3/4 11-9 3/4 12-10 1-6 3/4 11-10 B 3/4 11-1 1-7 3/4 11-11 B 3/4 11-2 3/4 3-68 3/4 11-12 8 3/4 11-3 3/4 3-71 3/4 11-13 8 3/4 11-4 i
3/4 3-76 3/4 11-14 B 3/4 11-5 3/4 3-79 3/4 11-15 B 3/4 12-1 1
3/4 8-16 3/4 11-16 5-2 3/4 8-17 3/4 11-17 6-15 3/4 8-18 3/4 11-18 6-18 3/4 11-1 3/4 11-19 6-19 3/4 11-2 3/4' 12-1.
6-22 3/4 11-3 3/4 12-?
6-23 3/4 11-4 3/4 12-6 6-24 3/4 11-5 3/4 12-7 6-29 3/4 11-6 3/4 12-8 6-30 3/4 11-8 3/4 12-9 6-31 l
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'o UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
g
- E WASHINGTON, D. C. 20555
'+9.....,o TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
34 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment to the Sequoyab Nuclear Plant, Unit 2 i
(the facility) Facility Operating License No. DPR-79 filed by the Tennessee Valley Authority (licensee), dated October 2 and November 7 1984, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regulations of the Com-mission; C.
There is. reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is bereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license imendnient, and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is bereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 34 are bereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications.
l l
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This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
[/
3 fV. h B.
.Yungbloo[ Director PW Pr,iect Di ectorate #4 Division of PWR Licensing-A
Attachment:
Appendix A Technical Specification Changes Date of Issuance: January 14, 1986 i
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DEFINITIONS OFFSITE 00SE CALCULATION MANUAL 1.15 The 0FFSITE DOSE CALCULATION MANUAL shall contain the current methodology l
and parameters used in the calculation of offsite doses due to radioactive gas-eous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints and in the conduct of the radiological environ-l mental monitoring program.
OPERABLE - OPERABILITY 1.16 A system, subsystem, train, or component or device shall be OPERABLE or i
have OPERAILITY when it is capable of performing its specified function (s),
and when all necessary attendant instrumentation, controls, a normal and an emergency electrical power source, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, com-ponent or device to perform its function (s) are also capable of performing their related support function (s).
OPERATIONAL MODE - MODE 1.17 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.
PHYSICS TESTS 1.18 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 14.0 of the FSAR, 2) authorfzed under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.
PRESSURE BOUNDARY LEAKAGE 1.19 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.
PROCESS CONTROL PROGRAM (PCP) 1.20 The PROCESS CONTROL PROGRAM shall contain the current formula sampling, analysis tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Part 20, 10 CFR Part 71, and federal and state regulations and other requirements governing the disposal of radioactive wastes.
SEQUOYAH - UNIT 2 1-4 Amendment No. 34
DEFINITIONS SHUTDOWN MARGIN 1.27 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.
SOLIDIFICATION 1.28 SOLIDIFICATION shall be the conversion of wet radioactive wastes into a form that meets shipping and burial ground requirements.
SOURCE CHECK 1.28 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
STAGGERED TEST BASIS 1.29 A STAGGERED TEST BASIS shall consist of:
A test schedule for n systems, subsystems, trains or other designated a.
components obtained by dividing the specified test interval into n equal subintervals, b.
The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
THERMAL POWER 1.31 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
UNIDENTIFIED LEAKAGE 1.32 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.
(
34 SEQUOYAH - UNIT 2 1-6 Amendment No.
i 4
i DEFINITIONS l
VENTILATION EXHAUST TREATMENT SYSTEM 1.33 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing fodines or partic-ulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).
Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
VENTING 1.34 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, ib such a manner that replacement air or gas is not j
2 provided or required during VENTING.
Vent, used in system names, does not j
imply a VENTING process.
i SITE BOUNDARY 1.35 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee (see figure 5.1-1).
UNRESTRICTED AREA 1.36 An UNRESTRICTED AREA shall be any area, at or beyond the site boundary to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the site boundary used for residential quarters or industrial, commer-j cial, institutional, and/or recreational purposes.
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MEMBERS OF THE PUBLIC 1.37 MEMBERS OF THE PUBLIC shall include all individuals who are not occupa-tionally associated with the plant.
This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, i
occupational, or other purposes not associated with plant functions.
This 1
i category does not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter an area that is controlled by the licensee for purposes of protection of individ-i uals from exposure to radiation and radioactive materials.
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SEQUOYAH - UNIT 2 1-7 Amendment No. 34 i
INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.
The alarm /
trip setpoints of these channels _shall be determined in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (00CM).
l APPLICABILITY:
During releases via these pathways.
l ACTION:
With a radioactive liquid effluent monitoring instrumentation channel a.
alarm / trip setpoint less conservative than required by the above spe-cification, without delay, 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.
Exert best effort to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semi-Annual Radioactive Effluent Release Report why the inoper-ability could not be corrected within 30 days, c.
The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13.b are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECX, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.
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SEQUOYAH - UNIT 2 3/4 3-68 Amendment No. 34 l
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1 TABLE 3.3-12 (Continued)
TABLE NOTATION ACTION 30 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:
l At least two independent samples are analyzed in accordance a.
with Specification 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.
ACTION 31 -
With the number of channels OPERABLE less than requ; red by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed j
for gross radioactivity gamma at a limit of detection of at 4
7 least 10 microcuries/ gram:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of l
a.
the secondary coolant is greater than 0.01 microcuries/ gram DOSE EQUIVALENT I-131.
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 micro-curies / gram DOSE EQUIVALENT I-131.
ACTION 32 -
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 gross radioactivity gamma at a limit of detection of at least 10 7 microcuries/ml.
ACTION 33 -
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 l
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 curves may be used to estimate flow.
ACTION 34 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue provided the tank liquid level is estimated l
during all liquid additions to the tank.
SEQUOYAH - UNIT 2 3/4 3-71 Amendment No. 34
INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.
The alarm / trip setpoints of these channels shall be determined in accordance with the ODCM.
APPLICABILITY:
As shown in Table 3.3-13 ACTION:
With a radioactive gaseous effluent monitoring instrumentation channel a.
alarm / trip setpoint less conservative than required by the above Spe-cification, without delay 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.
Exert best efforts to rturn the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semi-Annual Radioactive Effluent Release Report why the opera-bility could not be corrected within 30 days.
c.
The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13.b are not applic?ble.
SURVEILLANCE REQUIREMENTS 4.3.3.10 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 l
in Table 4.3-9.
l SEQUOYAH - UNIT 2 3/4 3-76 Amendment No. 34
TABLE 3.3-13 (Continued)
TABLE NOTATION At all times.
During waste gas disposal system operation.
- During shield building exhaust system operation.
ACTION 40 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environrent provided that prior l
to initiating the release:
At least two independent samples of the tank's contents a.
are analyzed, and b.
At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 41 -
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 l
at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 42 -
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 noble gas gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 43 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of this waste gas disposal system may continue provided grab samples are taken and analyzed either (1) every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations of the reactor coolant system or (2) daily during other operations.
ACTION 44 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> l
after the channel has been declared inoperable samples are con-tinuously collected with auxiliary sampling equipment as required in Table 4.11-2.
SEQUOYAH - UNIT 2 3/4 3-79 Amendment No. 34 i
)
ELECTRICAL POWER SYSTEMS 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.3.1 All containment penetration conductor overcurrent protective devices specified in appropriate plant instructions shall be OPERABLE.
l APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more of the containment penetration conductor overcurrent protective devices specified in appropriate plant instructions inoperable:
Restore the protective device (s) to OPERABLE status or de-energize the a.
circuit (s) by tripping the associated backup circuit breaker within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verify the backup circuit breaker to be tripped at least once per 7 days thereafter; the provisions of Specification 3.0.4 are not applicable to overcurrent devices in circuits which have their backup circuit breakers tripped, or b.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.8.3.1 All containment penetration conductor overcurrent protective devices specified in appropriate plant instructions shall be demonstrated OPERABLE:
l a.
At least once per 18 months:
1.
For at least one 6.9 kV reactor coolant pump circuit, such that all reactor coolant pump circuits are demonstrated OPERABLE at least once per 72 months, by performance of:
(a) A CHANNEL CALIBRATION of the associated protective relays, Surveillance Instruction SNP SI-256 l
(b) An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits l
function as designed using Surveillance Instruction SNP SI-257.
SEQUOYAH - UNIT 2 3/4 8-16 Amendment No. 34
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
(c) For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 1 of the curcuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested per Surveillance Instruction SNP SI-257.
2.
By selecting and functionally testing a representative sample of at least 10% of each type of lower voltage circuit breakers.
Circuit breakers selected for functional testing shall be selected on a rotating basis.
The functional test, Surveillance Instruction SNP SI-258, shall consist of injecting a current input at the spe-cified setpoint to each selected circuit breaker and verifying that each circuit breaker functions as designed.
Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation.
For each circuit breaker found inoperable during these functional tests, an additional representa-tive sample of at least 10% of all the circuit breakers of the in-operable type shall also be functionally tested until no more fail-ures are found or all circuit breakers of that type have been func-tionally tested.
3.
By selecting and functionally testing a representative sample of each type of fuse on a rotating basis.
Each representative sample of fuses shall include at least 10% of all fuses of that type.
The functional test, Surveillance Instruction SNP SI-270, shall consist of l
a non-destructive resistance measurement test which demonstrates that the fuse meets its manufacturer's design criteria.
Fuses found in-operable during these functional tests shall be replaced with OPERABLE fuses prior to resuming operation.
For each fuse found inoperable during these functional tests, an additional representative sample of at least 10% of all fuses of that type shall be functionally tested until no more failures are found or all fuses of that type have been functionally tested.*
b.
At least once per 60 months by subjecting each circuit breaker to an in-spection and preventive maintenance in accordance with Surveillance In-struction SNP SI-266 in conjunction with its manufacturer's recommendations.
- Surveillance requirement 4.8.3.1.a.3 may be suspended until the completion of Cycle 2, provided that the following surveillance requirement is implemented:
l A fuse inspection and maintenance program will be maintained to ensure that:
1.
the proper size and type of fuse is installed, 2.
the fuse shows no sign of deterioration, and 3.
the fuse connections are tight and clean.
SEQUOYAH - UNIT 2 3/4 8-17 Amendment No. 34
.ai.
1 1
PAGES 3/4 8-18 thrcugh 3/4 8-32 for Table 3.8-1 are deleted.
i I
i
'l 4
i i
4 i
i i
4 I
I 1
i i
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I I
i 1
i SEQUOYAH - UNIT 2 3/4 8-18 Amendment No.
34 i
l I
s
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,,,,n,,,,,..,.,a
3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released to unrestricted areas (see Figure 5.1-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 4 microcuries/ml total activity.
APPLICABILITY:
At all times.
ACTION:
With the concentration of radioactive material released to unrestricted areas exceeding the above limits, without delay restore the concentration to within the above limits.
SURVEILLANCE REQUIREMENTS 4.11.1.1.1 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 analysis shall be used in accordance with the methods in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.
I l
1 i
l SEQUOYAH - UNIT 2 3/4 11-1 Amendment No.
34
_ _. _ _ _ _ -.. - ~
1 j
TABLE 4.11-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of 4
Liquid Release Sampling Analysis Type of Activity Detection {LLD)
Type Frequency Frequency Analysis (pCi/ml)
A. Batch Waste P
P Release Each Batch Each Batch Principa} Gamma 5x10 7 d
j Tanks Emitters 1
j
- 1. Waste Con-j densate I-131 1x10 8 Tanks (3)
- 2. Cask Decon-P M
Dissolved and 1x10 5 tamination One Batch /M Entrained Gases Tank 7
(Gamma emitters) i j
- 3. Laundry l
Tanks (2)
P M
H-3 1x10 s D
1
- 4. Chemical Each Batch Composite f
j, Drain Tank Gross Alpha 1x10 7 1
- 5. Monitor Tank
- 6. Distillate P
Q Sr-89, Sr-90 5x10 8 b
Tanks (2)
Each Batch Composite f
- 7. Condensate Fe-55 1x10 8 Demineralizer Waste i
Evaporator i
Blowdown Tank (1)
=
1
- 8. Continuous' D
W Principa 5x10 7 Emitters} Gamma c
j Releases Grab Sample Composite I
h
- 1. Steam j
Generator I-131 1x10.s
~
Blowdown M
M Dissolved and 1x10 5 l
h
- 2. Turbine Grab Sample Entrained Gases Building (Gamma Emitters)
Sump D
M H-3 1x10 s I
Grab Sample Compositec Gross Alpha 1x10 7 I
D Q
Sr-89, Sr-90 5x10 s l
I Grab Sample CompositeC l
Fe-55 1x10 8 i
i l
l
)
SEQUOYAH - UNIT 2 3/4 11-2 Amendment No. 34 i
i
1 TABLE 4.11-1 (Continued)
RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Liquid Release Sampling Analysis Type of Activity Detection {LLD)
Type Frequency Frequency Analysis (pCi/ml)
C. Periodic W
Principal Gamma 5x10 7 Continuous Composite Emitters #
Continuous 9 c
Releases,h e
- 1. Non-Reclaim-I-131 1x10 8 able Waste Tank M9 M
Dissolved and 1x10 s Grab Sample Entrained Gases
- 2. High Crud (Gamma Emitters)
Tank (2)
M H-3 1x10 s Continuous 9 c
Composite Gross Alpha 1x10 7
- 3. Neutralizer Tank Q
Sr-89, Sr-90 5x10 8 Continuous 9 c
Composite Fe-55 1x10 8 TABLE NOTATION a.
The LLD is defined for the purpose of these specifications as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with only a 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 s LLD =
E V
2.22x106 Y
exp (-A.at) l Where:
LLD is the "a priori" lower limit of detection as defined above in microcurie per unit mass or volume, s
is the standard deviation of the background counting rate or of h
tne counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 108 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
SEQUOYAH - UNIT 2 3/4 11-3 Amendment No. 34
k TABLE 4.11-1 (Continued}
TABLE NOTATION' A is the radioactive decay constant for the particular radionuclide, and at from plant effluents is the elapsed time between midpoint of sample collection and time of counting (midpoint)'
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particulate measurement.
b.
A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
Prior to analyses, all samples taken for the composite shall be c.
throughly mixed in order for the composite sample to be represen-tative of the effluent release, d.
A batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in the CDCM, to assure representative sampling.
e.
A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release.
f.
The principal gamma emitters for which the LLD soecification applies exclusively are the following radionuclides:
Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141.
Ce-144 shall also be measured, with an LLD of 5 x 10 8 This list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
g.
Releases from these tanks are continuously composited during releases.
With the composite sampler or the sampler flow monitor inoperable, the sampling frequency shall be changed to require representative l
batch samples from each tank to be released to be taken prior to release and manually composite for these analyses.
l h.
Applicable only during periods of primary to secondary leakage or the t
release of radioactivity as detected by the effluent radiation monitor provided the radiation monitor setpoint is at a LLD of < 1 x 10 s pCi/ml and allowing for background radiation during perTods when primary to secondary leakage is not occurring.
i l
l SEQUOYAH - UNIT 2 3/4 11-4 Amendment No.34
- -.. _ ~,,
RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas (see Figure 5.1-1) shall be limited from each reactae unit:
During any calendar quarter to less than or equal to 1.5 mrem to the a.
total body and to less than or equal to 5 mrem to any organ, and b.
During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
APPLICABILITY:
At all times.
~
ACTION:
With the calculated dose from the release of radioactive materials a.
in liquid effluents exceeding any of the above limits, in lieu of a licensee event report (LER), prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that havs been taken to reduce the releases and the proposed corrective actions to be taken to assure that sub-sequent 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 141.*
b.
The provisions of specifications 3.0.3 and 3.0.4 are not applicable.
I SURVEILLANCE REQUIREMENTS 4.11.1.2 lumulativedosecontributionsfromliquidefflbentsforthecurrent calendar quarter and the current calendar year shall be determined in accordance with the methodology and paramete"s in the ODCM at least once per 31 days.
- Applicable only if drinking water supply is taken from the receiving water body within three miles downstream of the plant discharge.
SEQUOYAH - UNIT 2 3/4 11-5 Amendment No.34
RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the pro-jected doses due to the liquid effluent to unrestricted areas (see Figure 5.1-1) when averaged over 31 days, would exceed 0.06 mrem to the total body
- or 0.2 mrem to any organ
- in a 31 day period.
1 APPLICABILITY:
At all times.
ACTION:
a.
With radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of an LER, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes tne 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 Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to licuid releases shall be projected at least once per 31 days, in accordance with the methodology and parameters in the 00CM.
- Per reactor unit SEQUOYAH - UNIT 2.
3/4 11-6 Amendment No. 34 i
l
-,..------------r---
- - - - - ~ ~ - -
- ~ ~ - - - - -
RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents to areas at or beyond the site boundary (see Figure 5.1-1) shall be l
limited to the following:
a.
For noble gases:
Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin, and b.
For Iodine 131, Iodine 133, tritium, and for all radionuclides in particulate form with half lives greater than 8 days:
Less than or equal to 1500 mrem /yr to any organ.
APPLICABILITY:
At all times.
ACTION:
With the dose rate (s) exceeding the above limits, without delay restore the release rate to within the above limit (s).
SURVEILLANCE REQUIREMENTS 1
4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.
4.11.2.1.2 The dose rate due to I-131, I-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 meth-odology and parameters in the 00CM by obtaining representative samples and per-forming analyses in accordance with the sampling and analysis program specified in Table 4.11-2.
SEQUOYAH - UNIT 2 3/4 11-8 Amendment No. 34
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TABLE 4.11-2 S
S E
Minimum Lower Limit of-Sampling Analysis Type of Detection (gLD) i g
Gaseous Release Type Frequency Frequency Activity Analysis (pCi/ml) i Continuous a
Sr-89, Sr-90 1x10 11 Composite m
Sampler Particulate Sample E.
Noble Gases all Continuous #
Noble Gas Noble Gases 1x10 8 Releases types as Monitor Monitor Gross Beta or Gamma listed in C l
e.
a ae
TABLE 4.11-2 (Continued)
TABLE NOTATION The LLD is defined, for the purposes of these specifications, as the smallest a.
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 a 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 lb0
- E V
2.22x106 Y
exp (-A.at)
Wnere:
LLD is the "a priori" lower limit of detection as defined above in microcurie per unit mass or volume, s
is the standard deviation of the background counting rate or of h
tne counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 108 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
A is the radioactive decay constant for the particular radionuclide, and at for plant effluents.is the elapsed time between midpoint of sample collection and time of counting (midpoint).
It should be noted that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular, measurement.
b.
Sampling and analysis shall also be performed following shutdown, startup, or a thermal power change exceeding 15% of rated thermal power within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> unless (1) analysis shows that the dose equiva-lent I-131 concentration in the primary coolant has not increased more than a factor of 3 and (2) the noble gas activity monitor shows that the effluent activity has not increased by more than a factor of 3.
SEQUOYAH - UNIT 2 3/4 11-11 Amendment No. 34
J l
TABLE 4.11-2 (Continuzd)
TABLE NOTATION I
Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when c.
the refueling canal is flooded.
i d.
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler).
Sampling 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 2 days following each shutdown from >15% RATED THERMAL POWER, startup to >15% RATED THERMAL POWER or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in one hour and analyses shall i
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 LLD's may be increased by a factor of 10.
j Tritium grab samples shall be taken at least once per 7 days from e.
the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
f.
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 Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.
g.
The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for noble gases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate principal gamma emmitters.
This list does not mean that only these nuclides are to be detected and reported.
Other gamma peaks which are i
measureable and identifiable, together with the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.12.
1 h.
During releases via this exhaust system.
j i.
Purging - Applicable in MODES 1, 2, 3, and 4, the upper and lower i
compartments of the containment shall be sampled prior to PURGING.
l Prior to breaking containment integrity in MODE 5 or 6, the upper and lower compartments of the containment shall be sampled.
The incore instrument room purge sample shall be obtained at the shield t
building exhaust between 20 and 25 minutes following initiation of the incore instrument room purge.
j.
Venting - Applicable in MODES 1, 2, 3, and 4, the containment shall be vented to the containment annulus and then to the auxiliary build-ing via containment annulus fans.
The lower containment compartment shall be sampled daily when venting is to occur to account for the i
radioactivity being discharged from the venting process.
i l
SEQUOYAH - UNIT 2 3/4 11-12 Amendment No. 34
1 RADI0 ACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents from each reactor unit to areas at or beyond the site boundary (see Figure 5.1-1) l shall be limited to the following*:
4 a.
During any calendar quarter:
Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, I
b.
During any +alendar year:
Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
APPLICABILITY: At all times.
j ACTION
~
With the calculated air dose from radioactive noble gases in gaseous a.
effluents exceeding any of the above limits, in lieu of a Licensee Event Report (LER), prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent i
releases will be in compliance with the above limits.
t b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and i
current calendar year for noble gas shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
.l l
j i
"Per reactor unit.
i f
SEQUOYAH - UNIT 2 3/4 11-13 Amendment No. 34 1
_ - - -. ~ _ _.
i' RADI0 ACTIVE EFFLUENTS l
DOSE - I-131, I-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM l
t l
LIMITING CONDITION FOR OPERATION
}
3.11.2.3 The dose to a MEMBER OF THE PUBLIC from I-131, I-133, tritium and j
radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at or beyond the site boundary (see Figure 5.1-1)
{
shall be limited to the following from each reactor unit:
i a.
During any calendar quarter:
Less than or equal to 7.5 mrem to any organ and, j
b.
During any calendar year:
Less than or equal to 15 mrem to any j
organ.
APPLICABILITY:
At all times.
ACTION:
a.
With the calculated dose from the release of I-131, I-133, tritium, and radionuclides in particulate form with half-lives greater than i
8 days, in gaseous effluents exceeding any of the above limits, in lieu of a License Event Report (LER), prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special j
Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the j
releases and the proposed corrective actions to be taken to assure j
that subsequent releases will be in compliance with the above units.
l b.
The provisions of Specifications 3.(T.3 and 3.0.4 are not applicable.
i l
SURVEILLANCE REQUIREMENTS I
j 4.11.2.3 Cumulative dose contributions fo: the current calendar quar'.er and current calendar year for I-131, I-133, tritium, and radionuclides in par-l ticulate 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 l
31 days.
I i
i l
~
l SEQUOYAH - UNIT 2 3/4 11-14 Amendment No. 34
- it RADI0 ACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous
[
waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site (see Figure 5.1-1), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation
- and 0.4 mrad l
for beta radiation *.
The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases to areas at or beyond the site boundary (see Figure 5.1-1) when j
averaged over 31 days would exceed 0.3 mrem to any organ.*
APPLICABILITY:
At all times.
ACTION:
With the gaseous waste being discharged without treatment fur more a.
than 31 days and in excess of the above limits, in lieu of a licensee event report (LER), prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:
1.
Identification of the irtoperable 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 Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once par 31 days, in accordance with the methodology and parameters in the ODCM.
"These doses are per reactor unit.
SEQUOYAH - UNIT 2 3/4 11-15 Amendment No. 34
s i
l RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2% by volume whenever the hydrogen concen-tration exceeds 4% by volume, i
APPLICABILITY:
At all times.
ACTION:
With the concentration of oxygen in a waste gas holdup tank greater a.
than 2% by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
b.
With the concentrution of oxygen in a waste gas holdup tank greater than 4% by volume and the hydrogen concentration greater than 2% by volume, without delay suspend all additions of waste gases to the l
affected waste gas holdup tank and reduce the concentration of oxygen to less than or equal to 2% by volume without delay.
l The provisions of Specifications 3.0.3 and 3.0.4 are not app,licable.
c.
SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentration of hydrogen and oxygen in the waste gas holdup system shall be determined to be within the above limits by monitoring the l
waste gas additions to the waste gas' holdup system with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10.
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SEQUOYAH - UNIT 2 3/4 11-16 Amendment No. 34
)
RADI0 ACTIVE EFFLUENTS GAS DECAY TANKS LIMITING CONDITION FOR OPERATION i
3.11.2.6 The quantity of radioactivity contained in each gas decay tank shall be limited to less than or equal to 50,000 curies of noble gases (considered as Xe-133).
APPLICABILITY: At all times.
~
ACTION:
With the quantity of radioactive material in any gas decay tank a.
i exceeding the above limit, without delay suspend all additions of l
j radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.
i b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable, j
SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas decay tank shall be determined to be within the above limit at least once per 24
)
hours when radioactive materials are being added to the tank.
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I SEQUOYAH - UNIT 2 3/4 11-17 Amendment No.34 t
u, RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLIO RADI0 ACTIVE WASTE i
LIMITING CONDITION FOR OPERATION 3.11.3 The solid radwaste system shall be used, as applicable in accordance with a PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet shipping and burial ground requirements.
APPLICABILITY:
At all times.
ACTION:
With the provisions of the process control program not satisfied, a.
I suspend shipments of defectively processed, or defectively packaged solid radioactive wastes from the site.
b.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.3.1 THE PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICA-j TION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions),
If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICA-a.
TION of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test veriffes SOLIDIFICATION.
SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM.
b.
If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION,,the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each I
consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate SOLIDIFICATION.
The i
PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste.
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SEQUOYAH - UNIT 2 3/4 11-18
. Amendment No. 34
I RADI0 ACTIVE EFFLUENTS 3/4.11.4 TCTAL DOSE 1
i LIMITING CONDITION FOR OPERATION l
i 3.11.4 The annual (calendar year) dose or dose commitment to any member of l
the public, due to releases of radioactivity from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or any i
organ (except the thyroid, which shall be limited to less than or equal to 75 mrem).
l APPLICABILITY:
At all times.
ACTION:
With the calculated doses from the release of radioactive materials 4
a.
in liquid or gaseous effluent, exceeding tw;ce the limits of Specifica-tions 3.11.1.2.a, 3.11.1.2.b, 5.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a or i
3.11.2.3.b, calculations should be made to determine if the above limits have been violated.
If such is the case, in lieu of an LER, prepare and submit a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the l
limits of Specification 3.11.4.
This Special Report as defined in 10 CFR 20.405c shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluent pathways and ofre:t radiation) for a calendar year period that includes the release (s) covered by this i
report.
If the estimated dose (s) exceeds the limits of Specifica-tion 3.11.4, and if the release condition resulting in violation of j
40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions i
of 40 CFR 190 and including the specified information of S 190.11(b).
4 b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS i
4.11.4 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCH.
1
)
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SEQUOYAH - UNIT 2 3/4 11-19 Amendment No. 34 1
}'
3/4.12 RADf0 LOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORIM PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.
APPLICABILITY:
At all times.
ACTION:
With the radiological environmental monitoring program not being a.
conducted as specified in Table 3.12-1, in lieu of a LER, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the
~
program as required and the plans for preventing a recurrence.
b.
With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, in lieu of any other report required by Specifica-tion 6.9.1, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter a Report pursuant to Speci-ficiation 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 specifications of 3.11.1.2, 3.11.2.2, and 3.11.2.3.
When more than one cf the raoionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:
concentration (14~
- concentration (2) +.. 1 1.0 limit level (1) limit level (2)
When r 11onuclides other than those in Table 3.12-2 are detected and are the fasult of plant effluents, this report shall be submitted if the potantial annual dose to a member of the public is equal to or j
greater tnan the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.
This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
c.
With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.
The specific locations from which samples were unavailable may then be SEQUOYAH - UNIT 2 3/4 12-1 Amendment No. 34 l
+
1 RADIOLOGICAL ENVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION (Continued) deleted from the monitoring program.
In lieu of a Ifcensee event report (LER) and pursuant to Specification 6.9.2, identify the cause(s) of the unavailability of samples and identify the new locations for obtaining replacement samples in the Annual Radiological Environmen-tal Operating Report.
A revised figure (s) and table (s) for the ODCM reflecting the new location (s) shall be included in the next annual radiological effulent release report pursuant to Specification 6.9.1.9.
d.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the locations given in the table and figure 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.
l SEQUOYAH - UNIT 2 3/4 12-2 Amendment No. 34
I TABLE 3.12-2
- E REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 85 I
Reporting Levels 4
1 E
Water Airborne Particulate Fish Milk Food Products y
Analysis (pCi/1) or Gases (pCi/m )
(pCi/Kg, wet)
(pCi/1)
(pCf/Kg, wet)
~
3 ro i
(a)
H-3 2.x 104 N.A.
N.A.
N.A.
N.A.
Mn-54 1 x 103 N.A.
3 x 104 N.A.
N.A.
l Fe-59 4 x 102 N.A.
1 x 104 N.A.
N.A.
Co-58 1 x 103 N.A.
3 x 104 N.A.
N.A.
i Co-60 3 x 102 N.A.
I x 104 N.A.
N.A.
y Zn-65 3 x 102 N.A.
2 x 104 N.A.
N.A.
m Z r-Nb-95 4 x 102 N. A.-
N.A.
N.A.
N.A.
I-131 2(b) 0.9 N.A.
3 1 x 102 Cs-134 30 10 1 x 103 60 1 x 103 Cs-137 50 20 2 x 103 70 2 x 103 Ba-La-140 2 x 102 N.A.
N.A.
3 x 102 N.A.
=
(a) For drinking water samples.
This is 40 CFR Part 141 value.
If no drinking water pathway exists, I
a value of 30,000 pCi/1 may be used.
(b) If no drinking water pathway existsi a value of 20 pCi/1 may be used.
3 E
i TABLE 4.12-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,b h
SEN Airborne Particulate Water or Gas Fish Milk Food Products Sediment E
Analysis (pCi/1)
(pCi/m3)
(pCf/kg, wet)
(pCi/1)
(pCi/kg, wet)
(pCi/kg, dry)
U N
gross beta 4
1 X 10-2 N.A.
N.A.
N.A.
N.A.
H-3 2000*
N.A.
N.A.
N.A.
N.A.
N.A.
Mn-54 15 N.A.
130 N.A.
N.A.
N.A.
Fe-59 30 N.A.
260 N.A.
N.A.
N.A.
Co-58,60 15 N.A.
130 N.A.
N.A.
N. A.
w1 Zn-65 30 N.A.
260 N.A.
N.A.
N.A.
Zr-95 30 N.A.
N.A.
N.A.
N.A.
N.A.
Nb-95 15 N.A.
N.A.
N.A.
N.A.
N.A.
- a I-131 1
7 X 10-2 N.A.
1 60 N.A.
Cs-134 15 5 X 10-2 130 15 60 150 Cs-137 18 6 X 10-2 150 18 80 180 1
Ba-140 60 N.A.
N.A.
60 N.A.
N.A.
La-140 15 N.A.
N.A.
15 N.A.
N.A.
g S
E
- 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.
5 Y
TABLE 4.12-1 (Continued)
TABLE NOTATION The LLD is defined for the purposes of these specifications, as the a.
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 a 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
.LD = E exp(-A.at) l V
2.22 Y
l Where:
LLD is the "a priori" lower limit of detection as defined above in picocurie per unit mass or volume, l-is the standard deviation of the background counting rate or s
s oY the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),
1 A is the radioactive decay constant for the particular radionuclide, i
and at for environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of counting.
It should be recognized that the LLD is defined as a a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular i
measurement.
Analysis will be performed in such a manner that the stated LLDs will be achieved under routine conditions.
b.
Other peaks which are measurable and identifiable, together with the radionuclides in Table 4.12-1, shal,1 be identified and reported.
SEQUOYAH - UNIT 2 3/4 12-8 Amendment No. 34 4
__._,_.__,_..__t.
- -. - _ ~ _ _
RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A Land Use Census shall be conducted and shall identify within a dis-tance of 8 km (5 miles) the location in each of the 16 meteorological sectors the nearest milk animal, the nearest residence and the nearest garden
- of greater than 50 m2 (500 ft2) producing fresh leafy vegetation.
APPLICABILITY:
At all times.
ACTION:
With a Land Use Census identifying a location (s) which yields a calcu-a.
lated dose or dose commitment 20% greater than the values currently being calculated in Specification 4.11.2.3, identify the new locations (s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.
~
b.
With a Land Use Census identifying a location (s) which yields a calcu-lated 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 Specification 3.12.1, add the new loca-tion (s) within 30 days to the Radiological Environmental Monitoring Program given in the 00CM, if samples are available.
The sampling location, 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 Speci-fication 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 00CM reflecting the new loca-tion (s) with information supporting the change in sampling locations.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
c.
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, mail survey, telephone survey, aerial survey, or by consulting local agriculture authorities.
The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.
" Broad leaf vegetation sampling of at least three different kinds of vegeta-tion 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.
Spect-fications for broad leaf vegetation sampling in Table 3.12-1.4c shall be followed, including analysis of control samples.
SEQUOYAH - UNIT 2 3/4 12-9 Amendment No. 34
RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.
APPLICABILITY:
At all times.
ACTION:
With analyses not being performed as required above, report the a.
corrective actions taken to prevent a recurrence to the Commission i_
in the Annual Radiological Environmental Operating Report, b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.3 A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with the 00CM shall be included in the Annual Radiological Environmental Operating Report.
4 1
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SEQUOYAH - UNIT 2 3/4 12-10 Amendment No. 34
3/4.11 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radio-active materiais released in liquid waste effluents from the site will be less than the concent.ation 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 to unrestricted areas will result l
in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR 50, to a member of the public and (2) the limits of 10 CFR 20.106(e) to
[
the population.
The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
3/4.11.1.2 DOSE This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50.
The Limiting Condition for Operation implements the guides set forth in Section II. A of Appendix I.
The ACTION 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 will be kept "as low as is reasonably achievable".
Also, for fresh water sites with drinking water supplies which 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 141.
The dose calculations in the 00CM implement the requirements in Section III.A nf 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 l
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 Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, Octobar 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluants from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
This specification applies to the release of liquid effluents from each reactor at the site.
For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.
SEQUOYAH - UNIT 2 8 3/4 11-1 N endment No. 34
RADI0 ACTIVE EFFLUENTS BASES i
3/4.11.1.3 LIQUID WASTE TREATMENT The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable".
This specification implements the requirements of 10 CFR aart 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 ligold effluents.
3/4.11.1.4 LIQUID HOLDUP TANKS J
Restricting the quantity of radioactive material contained in the specified I
tanks provides assurance that in the event of an uncontrolled release of the i
tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.
3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 The annual dose limits are the doses l
associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a member of the public, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix 8, Table II of 10 CFR l
Part 20 (10 CFR Part 20.106(b)).
For members of the public who may at times be l
within the site bo/ndary, the occupancy of the individual will be sufficiently i
low to compensate for any increase in the atmospheric diffusion factor above i
that for the site boundary.
The specified release rate Ifmits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem /
i year to the total body or to less than or equal to 3000 mrem / year to the skin.
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-allk-infant pathway to less than or equal to 1500 mrem / year for the nearest cow to the plant.
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SEQUOYAH - UNIT 2 8 3/4 11-2 Amendment No. 34
RADI0 ACTIVE EFFLUENTS BASES DOSE RATE (Continued)
This specification applies to the release of gaseous effluents from all reactors 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.
3/4.11.2.2 DOSE, NOBLE GASES This specification is provided to implement the requirements of Sections II.8, III.A and IV.A of Appendix I, 10 CFR Part 50.
The Limiting Condition for Oper-ation implements the guides set forth in Section II.B of Appendix I.
The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as
~
low as is reasonably achievable".
The Surveillance Requirements implement the l
requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a member of the public through appropriate pathways is unlikely to be substantially underestimated.
The dose calculations 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 Ruutine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors,"
Revision 1, July 1977.
The ODCM equations provided for determining the air doses at the site boundary are based upon the historical average atmospheric i
conditions.
3/4.11.2.3 DOSE - 10 DINE-131, IODINE-133, TRITIUM AND RADIONUCLIDES This specification is provided to implement the requirements of Sections II.C.
III. A and IV. A of Appendix I,10 CFR Part 50.
The Limiting Conditions for Opera-tion are the guides set forth in Section II.C of Appendix I.
The ACTION state-ments provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reason-c ably achievable".
The 00CM calculational methods specified in the Surveillaace 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 exposere of a member of the public through appropriate pathways is unlikely to be substantially underesti-mated.
The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the method-ologies provided in NUREG/CR-1004, "A Statistical Analysis of Selected Param-eters for Predicting Food Chain Transport and Internal Dose of Radionuclides,"
October 1979 and Regulatory Guide 1.109, " Calculation of Annual Doses to SEQUOYAH - UNIT 2 8 3/4 11-3 Amendment No. 34
RADI0 ACTIVE EFFLUENTS BASES l
DOSE - 10 DINE-131, IODINE-133, TRITIUM AND RADIONUCLIDES 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 Dis-persion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.
These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.
The release rate specifications for I-131, I-133, tritium, and radionuclides in i
particulate form with half-lives greater than 8 days are dependent on the existing radionuclide pathways to man, in the unrestricted area.
The pathways which were examined in the development of these calculations were:
- 1) indi-vidual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition i
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, t
3/4.11.2.4 GASEOUS RADWASTE TREATMENT The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive i
l materials in gaseous effluents will be kept "as low as is reasonably achiev-able".
This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50.
The speci-fied ifmits governing the use of appropriate portions of the systems were j
specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
4 3/4.11.2.5 EXPLOSIVE GAS MIXTURE I
l i
This specification is provided to ensure that the concentration of poten-i i
tially explosive gas mixtures contained in the waste gas holdup system ir maintained below the flammability limits of hydrogen and oxygen.
Maintaining the concentration of hydrogen and oxygen below their flammability limits pro-1 vides assurance that the releases of radioactive materials will be controlled i
in conformance with the requirements of General Design Criterion 60 of Appendix A j
to 10 CFR Part 50.
i i
j SEQUOYAH - UNIT 2 8 3/4 11-4 Amendment No. 34
1 e
e RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.6 GAS DECAY TANKS Restricting the quantity of radioactivity contained in each gas decay tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem.
This is consistent with Standard Review Plan 15.7.1, " Waste Gas System Failure".
3/4.11.3 SOLIO RADI0 ACTIVE WASTE This specification implements the requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50.
The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste / liquid / solidification agent /
catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.
3/4.11.4 TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR 190.
The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I.
For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level.
The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for 12 consecutive months to within the 40 CFR 190 limits.
For tne 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 5 miles must be considered.
SEQUOYAH - UNIT 2 B 3/4 11-5 Amendment No. 3'
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM
\\
The radiological monitoring program required by this specification pro-vides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation.
This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive mater-fals and levels of radiation are not higher than expected on the basis of the i
effluent measurements and modeling of the environmental exposure pathways.
The initially specified monitoring program will be effective for at least the first three years of commercial operation.
Following this period, program changes may be initiated based on operational experience.
The 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 a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.
Analyses ihall be performed in such a manner that the stated LLDs will be achieved under routine conditions.
Occa-siona11y background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors will be identified l
and described in the Annual Radiological Eavironmental Operating Report.
3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of unre-stricted areas are identified and that modifications to the monitoring program are made if required by the results of this census.
The best survey informa-tion from the door-to-door, aerial or consulting with local agricultural 1
authorities shall be used.
This census satisifes the requirements of section IV.B.3 of Appendix I to 10 CFR Part 50.
Restricting the census to gardens of 1
greater than 500 square feet provides assurance that significant exposure path-ways 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 i
vegetables assumed in Regulatory Guide 1.109 for consumption by a child.
To determine this minimum garden size, the following assumptions were used,
- 1) that 20% of the garden was used for growing broad leaf vegetation (!.e.,
i I
similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square
- meter, t
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i SEQUOYAH - UNIT 2 B 3/4 12-1 Amendment No. 34 l
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ADMINISTRATIVE CONTROLS The Site Radiological Emergency Plan and implementing procedures at e.
least once per 12 months.
f.
The Plant Physical Security Plan, the Safeguards Contingency Plan, and implementing procedures at least once per 12 months.
g.
Any other area of unit operation considered appropriate by the NSRB l
or the Manager of Power.
h.
The Facility Fire Protection Program and implementing procedures at least once per 24 months.
i, An independent fire protection and loss prevention program inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.
j.
An inspection and audit of the fire protection and loss prevention program shall be performed t/ an outside qualified fire consultant at intervals no greater than 3 years.
k.
The radiological environmental monitoring program and the results i
thereof at least once per 12 months.
1.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
The PROCESS CONTROL PROGRAM and implementing procedures for m.
SOLIDIFICATION of radioactive wastes at least once per 24 months.
The performance of activities required by the Quality Assurance n.
Program to meet the criteria of Regulatory Guide 4.15, December 1977 or Regulatory Guide 1.21, Rev.1,1974 and Regulatory Guide 4.1, Rev. 1, 1975, at least once per 12 months.
AUTHORITY 4
i 6.5.2.9 The NSRB shall report to and advise the Manager of Power on those j
areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Records of NSRB activities shall be prepared, approved and distributed as indicated below:
l Minutes of each NSRB meeting shall be prepared, approved and forwarded a.
to the Manager of Power within 14 days following each meeting.
I b.
Reports of reviews encompassed by Sect. ion 6.5.2.7 above, shall be prepared, approved and forwarded to the Manager of Power within l
14 days following completion of the review.
i SEQUOYAH - UNIT 2 6-15 Amendment No. 34
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ADMINISTRATIVE CONTROLS A Safety Limit Violation Report shall be prepared.
The report shall c.
be reviewed by the PORC.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, the NSRB and the Director, Nuclear Power Division within 14 days of the violation.
6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
The applicable procedures recommended in Appendix "A" of Regulatory a.
Guide 1.33, Revision 2, February 1978.
b.
Refueling operations.
Surveillance and test activities of safety related equipment.
c.
d.
Plant Physical Security Plan implementation, Site Radiological Emergency Plan implementation.
e.
f.
Fire Protectior. Program implementation.
g.
PROCESS CONTROL PROGRAM implementation.
h.
Quality Assurance Program for effluent monitoring, using the guidance contained in Regulatory Guide 4.15, December 1977 or Regulatory Guide 1.21, Rev. 1, 1974 and Regulatory Guide 4.1, Rev. 1, 1975.
6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the PORC and approved by the Plant Superintendent prior to implementation and reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
The change is documented, reviewed by the PORC and approved by the c.
Plant Superintendent within 14 days of implementation.
SEQUOYAli - UNIT 2 6-18 Amendment No. 34
ADMINISTRATIVE CONTROLS 6.8.4 Written procedures shall be established, implemented and maintained by the Radiological Hygiene Branch covering the activities below:
a.
OFFSITE DOSE CALCULATIONAL MANUAL implementation.
b.
Quality Assurance Program and environmental monitoring, using the l
guidance contained in Regulatory Guide 4.15, December 1977.
c.
Surveillance requirements and environmental monitoring requirements shown in Table 6.1-1.
6.8.5 The following programs shall be established, implemented, and maintained:
a.
Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.
The systems include the safety injection system, residual heat removal system, chemical and volume control system, containment spray system, and RCS sampling system.
The program shall include the following:
(i) Preventive maintenanc.e and periodic visual inspection requirements, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.
b.
In-Plant Radiation Monitorino A program which will ensure the capability to accurately determine the airborne iodine concentrations in vital areas under accident conditions. This program shall include the following:
(i) Training of personnel, (ii) Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analysis equipment.
c.
Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation.
This program shall include:
(i) Identification of a sampling schedule for the critical variables and control points for these variables, (ii) Identification of the procedures used to measure the values of the critical variables, (iii) Identification of process sampling points,
\\
SEQUOYAH - UNIT 2 6-19 Amendment No. 34
a ADMINISTRATIVE CONTROLS ANNUAL REPORTSM 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.
The initial report shall be submitted prior to March 1 of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include a tabulation on an annual basis for the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mre manremexposureaccordingtoworkandjobfunctions,gyrandtheirassociated e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.
The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORTE 6.9.1.6 The radiological environmental operating report covering the operation of the~ unit during the previous calendar year shall be submitted prior to May 1 of each year.
6.9.1.7 The annual radiological environmental operating reports shall include summaries, interpretations, and an analysis of trends of the results of the radiologica.1 environmental surveillance activities for the report period, including a comparisen with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.
The reports shall also include the results of land use censuses required by Specification 3.12.2, and a listing of the new locations for dose calculations and/or environmental monitoring identified by the land use census.
If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problems and a planned course of action to alleviate the problem.
-1/ A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the station.
g This tabulation supplements the requirements of S 20.407 of 10 CFR Part 20.
-3/ A single submittal may be made for a multiple 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.
SEQUOYAH - UNIT 2 6-22 Amendment No. 34
ADMINISTRATIVE CONTROLS The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
The reports shall also include the following:
a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3.
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REFORTM 6.9.1.8 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 1 of each year.
The period of the first report shall begin with the date of initial criticality.
6.9.1.9 Semiannual radioactive effluent release reports shall include a summary l
of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio-active Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.
The annual radioactive effluent release report (Radiological Impact) to be l
submitted 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year.
This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.* This same report shall include an l
assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.
This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary (Figure 5.1-1) during the report period.
All assumptions used in making these assessments (i.e., specific activity, 1/
A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the stations.
however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
In lieu of submission with the annual radioactive effluent release report this summary of required meteorological data may be retained on site in a file that shall be provided the NRC upon request.
SEQUOYAH - UNIT 2 6-23 Amendment No. 34
1
.e ADMINISTRATIVE CONTROLS exposure time and location) shall be included in these reports.
The mete-orological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measure-1 ment) shall be used for determining the gaseous pathway doses.
The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE i
CALCULATION MANUAL (00CM).
The annual radioactive effluent release report to be submitted after January 1 of each year shc11 also include an assessment of radiation doses to the likely most exposed metbers of the public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Ragnlatory Guide 1.109, Rev. 1.
The semiannual radioactive effluent release reports shall include the following information for each type of solid waste identified in Regulatory Guide 1.21, Rev.1, Table 3, Part A, which is shipped offsite during the report period:
a.
Total volume of containers, b.
Total curie quantity (specify whether determined by measurement or estimate),
Principal radionuclides (specify whether determined by measurement c.
or estimate),
d.
Type of quantity (e.g., LSA, Type A, Type B, etc.)
The semiannual radioactive effluent release reports shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis, and shall include any changes to the PROCESS CONTROL PROGRAM (PCP) and the Offsite Dose Calculation Manual (ODCM) made during the reporting period.
It shall include the type of solidification agent used, if applicable.
MONTHLY REACTOR OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or Safety Valves, shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C.
- 20555, with a copy to the Regional Office of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.
Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective.
In addition, a report of any major changes to the radioactive waste treatment l
systems : hall be submitted with the Monthly Operating Report for the period in l
which the evaluation was reviewed and accepted by the PORC.
l SEQUOYAH - UNIT 2 6-24 Amendment No. 34
ADMINISTRATIVE CONTROLS 6.10.2 (Continued)
Records of secondary water sampling and water quality.
m.
Records of the service life monitoring of all safety-related hy-n.
draulic and mechanical snubbers, required by T/S 3.7.9, including the maintenance performed to renew the service life.
o.
Records for environmental qualification which are covered under the provisions of paragraph 2.C.(10)(b) of license No. DPR-79.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6,12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 100) mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controllea by requifing issuance of a Special (Radiation)
Work Permit *.
Any' individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
A radiation monitoring device which continuously indicates the a.
radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.
An individual qualified in radiation protection procedures who is c.
equipped with a radiation dose rate monitoring device.
This individual' shall be responsible for providing positive control over the activities within the area and shall perform control over the activities within the area and shall perforbi periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Special (Radiation) Work Permit.
" Health Physics personnel or personnel escorted by Health Physics personnel in accordance with approved emergency procedures, shall be exempt from the SWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
4 SEQUOYAH - UNIT 2 6-29 Amendment No. 34
ADMINISTRATIVE CONTROLS 6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Engineer on duty and/or the Health Physicist.
6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 Licensee initiated changes to the PCP:
1.
Shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change (s) was made. This submittal shr.ll contain:
a.
sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information, b.
a determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria
~
for solid wastes; and c.
documentation of the fact that the change has b~en reviewed and e
found acceptable by the PORC.
2.
Shall become effective upon review and acceptance by the PORC.
6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Licensee initiated changes to the 00CH:
1.
Shall be submitted to the Commission in the next Semi-Annual Radioactive Effluent Release Report pursuant to Specification 6.9.1.9.
This submittal shall contain:
sufficiently detailed informatjon to totally support the rationale a.
for the change without benefit of additional or supplemental information.
Information submitterl ;hould consistent of a package of those pages of the ODCM to be changes with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);
b.
a determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and c.
documentation of the fact that the change has been reviewed and found acceptable by the RARC.
l SEQUOYAH - UNIT 2 6-30 Amen,dment No. 34 i
~
s ADMINISTRATIVE CONTROLS 2.
Shall become effective upon review and acceptance by the RARC.
6.15' MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous and Solid) 6.15.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid):*
1.
Shall be reported to the Commission in the Semi-Annual Radioactive Effluent Report for the period in which the evaluation was reviewed by the PORC.
The discussion of each change shall contain:
a.
A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; b.
sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; c.
a detailed description of the equipment, components and proces-ses involved and the interfaces with other plant systems; d.
an evaluation for the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; e.
an evaluation of the change which shows the expected r.aximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto; f.
a comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; g.
an estimate of the exposure to plant operating personnel as a result of the change; and h.
documentation of the fact that the change was reviewed and found acceptable by the PORC.
2.
Shall become effective upon review and acceptance by the PORC.
Submittal of information required by this section may be made as part of the annual FSAR update.
34 SEQUOYAH - UNIT 2 6-31 Amendment No.
.