ML20141M853
| ML20141M853 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/20/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20141M854 | List: |
| References | |
| NUDOCS 8602280456 | |
| Download: ML20141M853 (13) | |
Text
.
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 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 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 inoperable during these functional tests a.. 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 functi.onally 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 p
Instruction SNP SI-266 in conjunction with its manufacturer's recommendations.
^$urveillance requirement 4.8.3.1.a.3 may be suspended until the completion of the NRC generic study, provided the following surveillance requirement is i
implemented:
A fuse inspection and maintenance program will be maintained to ensure that:
1.
The proper size and type of fuse is-installed.
l 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 (Corrected page) 0602200456 860220 PDR ADOCK 05000327 p
PDR w_--_____.
Pages 3/4 8-17 through 3/4 8-33 for Table 3.8-1 are deleted.
~~
SEQuoYAH - UNIT 1 3/4 8-17 (Corrected go. 42 Amendment age).
I TABLE 4.11-1 (Continued)
TABLE NOTATION b.
A composite sample is one in which the quantity of Ifquid 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 ODCM, to assu.e 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 the continuous release.
f.
The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-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 representive batch samples from each tank to be released to be taken prior to release and manually composite for these analyses, h.
Applicable only during periods of primary to secondary leakage or the release of radioactivity as detected by the effluent radiation monitor provided the radiation monitor setpoint is at a LLD of 11 x 10 8 pCf/ml and allowing for background radiation during periods when primary to secondary leakage is not occurring.
l SEQUOYAH - UNIT 1 3/4 11-5 Amendment No. 42 (Corrected page)
M TABLE 4.11-2 S
RADI0 ACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM S
3C Minimum Lower Limit of Sampling Analysis Type of Detection (glD)
E Gaseous Release Type Frequency Frequency Activity Analysis (pCi/ml)
P P
~4
~
A.
Waste Gas Storage Each Tank Each Tank Principal Gamma Emitters 9 1x10 Tank Grab Di Principal Gamma Emitters 9
- 8. Containment Pi 1x10
- 1. Purge Each Purge Each Purge H-3 1x10 Grab Sample
- 2. Vent Dj Dj Principal Gama Emitters 9 1x10 Each Day Each Day H-3 1x10 R
C.
Noble Gases and M,
M Principal Gama Emitters 9
-4 1x10 g
Tritium Grab 1.CondensgrVacuum Sample H-3 1x10
-6 Exhaust 2.Auxili g, Building Exhaust
- 3. Service Building Exhaust '
4.Shieldguj1ging Exhaust D.
Iodine and Parti-Continuous #
W I-131 1x10 d
-I2 g;y culates Sampler Charcoal o@
- 1. Auxiliary Building Sample gg Exhausi.
Continuous #
W Principal Gamma Emitters d
9 1x10 '
,q g
- 2. Shield Building Sampler Particulate (I-131, Others)
Exhaust Sample E.*
50
_ RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMirING 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 of the nearest milk animal the nearest residence and the nearest' garden
- of E
greater than 50 m2 (500 ft ) producing fresh leafy vegetables.
APPLICABILITY: At all times.
ACTION:
With a Land Use Census identifying a location (s) that 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 loca-tion (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) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the n;w location (s) within 30 days to the Radiological Environmenta-1 Moni-toring Program given in the ODCM, if samples are available.
The sampling locaticn(s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same expo-sure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted.
Pursuant to Specification 6.14, submit in the next Semiannual Radio-active Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflect-ing the new location (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 cond'ucted during the growing season at
,~
least once per 12 months using that information that will provide the best i
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.
- 8 road leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE B0UNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census.
Speci-fications for broad leaf vegetation sampling in Table 3.12-1.4c. shall be followed, including _ analysis of control samples.
SEQUOYAH - UNIT 1 3/4 12-10 Amendment No.42 (Corrected page)
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
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gaseous effluents from the shared system are proportioned among the units sharing that system.
3/4.11.2.2 00SE, 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 Opera-tion implements tne 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 Requirements implement the require-ments_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 l
is unlikely to be substantially underestimated.
The dose calculations estab-lished in the ODCM for calculating the doses due to the actual releas,e 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 - 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-ably achievable".
The 00CM 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 B 3/4 11-3 Amendment No. 42 (Corrected page)
RADIOACTIVE EFFLUENTS BASES Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Re-leases of R2. actor Effluents for the Purpose of Evaluating Complian'ce 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 release rate specifications for I-131, I-133, 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 of these calculations were:
- 1) individual inhalation of airborne radionuclides,
- 2) deposition of radionuclides onto green leafy vegetation with subsequent con-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 b'e used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous 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 objectives given in Section II.D of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections 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 helow their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Apperdix A j
to 10 CFR Part 50.
1 SEQUOYAH - UNIT 1 B 3/4 11-4 Amendment No. 42 (Corrected page)
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 ACTIDN 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 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.
i SEQUOYAH - UNIT 2 3/4 3-76 Amendment No. 34 (Corrected page)
b 4
i ELECTRICAL POWER SYSTEMS 1
l 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 representativa sample of at i
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-P.
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-i 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-l 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 l
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 i
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 l
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-l 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 the NRC generic study, 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 4
3.
the fuse connections are tight and clean.
SEQUOYAH - UNIT 2 3/4 8-17 Amendment No. 34 (Corrected page) a
., _.,... -. _ - - - ~.. _ _
t b
Y g
TABLE 4.11-2 g
RADI0 ACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM
'a
>z Minimum Lower Limit of Sampling Analysis Type of Detection (gtD) g Gaseous Release Type Frequency Frequency Activity Analysis (pCi/ml) i U
P P
i N
A.
Waste Gas Storage Each Tank Each Tank Principal Gamma Emitters 9 1x10 4 Tank Grab Sample B.
Containment Pi Di i
1.
Purge Each Purge Each Purge Principal Gamma Emitters 9 1x10 4 Grab Sample H-3 1x10 8 2.
Vent Dj Dj Each Day Each De/
Principal Gamma Emitter 1 x 10 4 w)
Grab Sample H-3 1 x 10 s y
C.
Noble Gases and M
M Principal Gamma Emitters 9 1x10 4 i
to Tritium
' Grab 4
j
- 1. Condenser Vacuum Sample H-3 1x10 8 Exhaust 2.Auxiliap'r, Building Exhaust
- 3. Service Building Exhaust 4.Shieldguf1 Jing Exhaust I
D.
Iodine and Parti-Continuous
/
I-131 1x10 12 3
culates Sampler Charcoal 8k
- 1. Auxiliary Building Sample 2=
Exhaust P, k Continuous
/
Principal Gamma Emitters 9 1x10 11 f
E.g
- 2. Shield Building Sampler Particulate (I-131, Others)
Exhaust Sample m z S
l
%o f
Continuous M
Gross Alpha 1x10 11 7
Composite Sampler Particulate Sample
TABLE 4.11-2 (Continued)
_ TABLE NOTATION 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.
d.
Samples shall be changed at least once per 7 days and a alyses 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 RXTED THERMAL POWER in one hour and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.
When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased 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 calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.
The principal gamma emitters for which the LLD specification applies g.
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, Co-58, Co-60, 2n-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 2
peaks which are measureable and identifiable, together with the above nuclides, shall also be analyzed and reported in the Semiannual Radio-active 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 compartments of the containment shall be sampled prior to PURGING.
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 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 radioactivity being discharged from the venting process.
SEQUOYAH - UNIT 2 3/4 11-12 Amendment No. 34 l
(Corrected page)
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TABLE 4.12-1 (Continued) 0 l
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 LLD _ E exp(-A.at) l V
2.22 Y
Where:
i 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 sh oT 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, 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 1
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.
b.
Other peaks which are measurable and identifiable, together with the radionuclides in Table 4.12-1, shall be identified and reported.
SEQUOYAH - UNIT 2 3/4 12-8 Amendment No. 34 (Corrected Page)
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