ML20065K193
| ML20065K193 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/12/1994 |
| From: | NEBRASKA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20065K188 | List: |
| References | |
| NSD940383, NUDOCS 9404190208 | |
| Download: ML20065K193 (9) | |
Text
.
Attachment to NSD940383 April 12.1994 MAltKED UP AFFECTED TECilNICAL SPECIFICATION PAGES 9404190208 940412 PLR ADOCK 05000298 P
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s W.A Salidification SOLIDIFICATION shall be the conversion of radioactive vastes from liquid systems to a solid which is as uniformally distributed as reasonably achievable with definite volume and shape, bounded by a stable surface of distine' outline on all sides (free-standing).
X.
Ep h 1 Reload - Pertains to the spiral reloading of the core with fuel, at lent 50% of which has previously accumulated a minimum exposure of 1000 MWD /T.
Y.
Sntveillance Frequencv - Surveillance requirements shall be applicable during the operational conditions associated with individual LCO's unless otherwise stated in an individual Surveillance Requirement.
Each Surveillance Requirement shall be performed ' within the specified surveillance interval with a maximum allowable extension not to exceed 25% of 4
the specified surveillance interval.
h Perf ormance of a Surveillance Requirement within the specified time interval shall constitute compliance with operability requirements for an LCO unless otherwise required by the specification.
The Surveillance Frequency establishes the limit for which the specified time g
interval for Surveillance Requirements raay be extended.
It pe rmit - an g
allowable extension of the normal surveillance interval to facilitate p-surveillance schedule and consideration of plant operating conditions that j
may not be suitable for conducting the surveillance; e.g.,
conditions or other ongoing survc111ance or maintenance activities. It also
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provides flexibility to accommodate the length of a fuel cycle for surveillance that are performed at each refueling outage and are specified with an 18 month surveillance interval.
It is not intended that this y
provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed
),
during refueling outages.
The limitation of this definition is based on
(
engineering judgement and the recognition that the most probable result of any particular surveillance being performed is the-verification of f
conformance with the Surveillance Requirements. This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.
Z.
Surveillanca Interval - The surveillance interval is the calendar time between surveillance tests, checks, calibrations and examinations to be performed upon an instrument or component when it is required to be operable.
These tests may be waived when the instrument, componen't or system is not required to be operable, but the instrument, component or system shall be tested prior to being declared operable or as practicable following its return to service.
Z.A Ventina Venting is the controlled process of discharging air or gas from a confinement to establish 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.
Z.B of fsite offsite means outside of the exclusion area as defined in'10CFR Part 100.3.
The exclusion area boundary around Cooper Station is defined in Figure l'.1 and may also be teferred to as the Site Boundary.
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Z.C Member of the o blic - A Member of the Public is a person 2-u e: cur ti4>ei4y ;;;; inted ith " PPD cH un "::: m: m:: ally fr:quent th:
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AA.. Gor,tJ)peratinc Limits Renora
't he Core operating Limits Iteport. in the unit specific document that providos core operating limits for the current reload cycle. These cycle-specific core operatitig limits shall he determined for each relonet cycle in accordance with ftpecification 6,5.1.0.
-Plant operation within these core operating limits is aciriressed in individual specifications.
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l LIMITING CCNDITION FOR OPERATI'ON SURVEILLANCE REQUIREMENTS 3.21 (Cont'd) 4.21 (Cont'd)
B.
Liquid Effluents B.
Liquid Ef fluents i
Concenjlr[atjpn[;))l, Applicability:
At all times.
1.
Specification:
a.
Radioactive liquid wastes shall be sampled and analyzed accord-1.
Concentration 0.13 0 3L ing to Table 4.21.B.1.
a.
The concentratici of radioactive b.
The' analytical results shall-material in wat.r6]f_fsitcJ be used with methods in the (Figure 1.1) di e to radioactive ODAM to verify that the average liquid effluen. shall not exceed
_ concentration beyond the the concentrat [on specified in lihoundari)does not exceed 10 CFR Part 2d.!Ca for radio-Specification 3.21.B.I.a.
nuclides other than dissolved when Sr-89. Sr-90 and Fe-55 or entrained nobic gases.
For concentrations are averaged t
dissolved or entrained noble over no more than 3 months gases, the concentration shall and other radionuclide not exceed 2 x 10 " pC1/ml concentrations are averaged-
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total activity, over no more than 31 days.
b.
With the concentration of radio- /
active material released (Dffsite )
gI;Qggj (Au cms) exceeding'the limit, atten'd to the cause without delay and restore the concentration within M
the above limit.
c.
The provisions of Specification 6.5.2 do not apply.
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l 3.21 5 4.21 BASES 3.21.A 6 4.21.A INSTRUMENTATION J.21.A.1 & 4.21.A.1 Liquid Effluent Monitoring The radioactive liquid effluent instrumentation is provided to monitor and control, as
')
applicable, the release of radioactive material in liquid effluents.
The OPERABILITY and use of these instruments implements the requirements of 10 CFR Part 50, Appendix A, General Design Criteria 60, 63, and 64.
The alarm and/or trip setpoints for these r
instruments are calculated in the manner described in the ODAM to assure that the alarm i
and/or trip will occur before the limit specified in 10 CFR Part 20..
is exceeded.
I Control of the normal 11guld discharge pathway is assured by station p ocedures e
governing locked discharge valves and valve line-up verification, l *3O g]
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3.21.A.2 & 4.21.A.2 Gaseous Effluent Monitoring The radioactive gue.cous effluent instrumentation is provided to monitor and control, as
! applicabic, the releases of radioactive materials in gaseous effluents during actual 6 or potential releases of gaseous effluents. The location of this instrumentation is l Indicated by a Figure in the ODAM, a simplified flow diagram showing gaseous effluent i treatment and monitoring equipment. The alarm / trip setpoints for these instruments shall I be calculated in accordance with methods in the ODAM, which have been reviewed by NRC, I to ensure that the alarm will occur prior to exceeding the limits of 10 CFR Part 20.
The process monitoring instrumentation includes provisions for monitoring the concentra.
tions of potentially explosive gas mixtures'in the augmented offgas treatment system. Th'e
- OPERABILITY and use of this instrumentation is consistent with the requirements of
! General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
j In the event no flow rate measurement device is operable on a gaseous stream, alternative i
l 24-hour estimates are adequate sin e the system design is constant flow and loss of flow I l
is alarmed in the control room.
30.110Y Mk 3.21.B 6 4.21.B LIQUID EFFLUENTS 3 0.11 0 1 0e X A M
'q 3.21.B.1 & 4.21.B.1 Concentration -
1301 dt 2sure that the concentrat on of radioactive materials i j'l 1 This specification is'provi
} released in liquid waste fluents from the site to unrestr ~ cted areas will be less j than the concentratio levels specified in 10 CFR Part 20.
This limitation provides j' additional assuran that the IcVels of radioactive materials in bodies of water outside i the site will no result in exposures within (1) the Section IV.A guides on technical specifications 1 Appendix I, 10 CFR Part 50, for an individual and (2) the limits of 10 CFR Part 2". 5 N to the population. The concentration limit for 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.
Since/Mrvicy/ Inter)is not a normal or expected source of significant radioactive release, vndinncH vity is precautionary. An activity con-routine samplitig and gonitoring [for centration of 3 x 10- uCi/mi in 3"ervice n ter) effluent is diluted in the discharge
- canal to about 1.5% of the 10 CFR 20 Appendix B Table 2 Column 2 concentration with only norine.norr i Station operation the dilution one circulating water pump operating.[/ervicefaterleffluent continuously for radio-would be even greater.
By monitoring 3I activity and by confirmatory sampling weekly, reasonable assurance that its activity
- concentration can be kept to a small fraction of the 10 CFR Part 20de6p limit and within the Specificat_fon 3.21.B.2.a limit is provided.
g By monitor 1ngbrvice Michcontinuously and liquid radwaste continuously durin c.harge with the monitor set to alarm or trip before the limit specified in 10 CFR 20A l
1s exceeded, reasonable assurance of compliance with Specification 3.21.B.1.2 is provided.
t Verification that radioactivity in liquid effluent averaged only a small fraction of the i concentration limit is provided by calculations demonstrating compliance with Specifica-tion 3.21.B.2.a.
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Attachment to NSD940383 April 12,1994 REVISED AFFECTED TECilNICAL SPECIFICATION PAGES r_ g,J*
W.A ' Soli.dificatiga - SOLIDIFICATION shall be the conversion of radioactive wa'stes from liquid systems to a solid which is as uniformally distributed as reasonably achievable with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).
X.
Sniral Reload - Pertains to the spiral reloading of the core with fuel, at least 50% of which has previously accumulated
'a minimum exposure of 1000 MVD/T.
Y, Surveillance Freauency - Surveillance requirements shall be applicable during the operational conditions assani~ ted with individual LCO's unless ott o wise stated in an individual Survelfl e - Requirement.
Each surveillance Requirement thril be performed within.the specified-surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.
Performance of a Surveillanco Requirement within the specified time interval shall constitute compliance with operability requirements for an LCO unless otherwise required by the specification.
~
The Surveillance Frequency establishes the limit for which the specified time interval for Surveillance Requirements may be extended.
It permits an -
allowable extension of the normal surveillance interval to facilitate surveillance schedule and consideration of-plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions-or other ongoing surveillance or maintenance activities.
It also provides flexibility to accommodate the length of a-fuel cycle for surveillance that are performed at each refueling outage and are specified with an 18 month 2.
surveillance interval.
It is not intended that this provision l be used.
repeatedly as a convenience to extend surveillance - intervals beyond that specified for surviellances that are not performed during refueling outages.
The limitation of this definition is based on engineering judgement and the-recognition that the most probable result of any particular surveillance being.
performed is the verification of conformance with the Surveillance Requirements.
This provision is sufficient to ensure that the reliability-ensured through survie11ance activities is not significantly degraded beyond that obtained from the specified surveillance interval.
Z.
Surveillance Interval - The surveillance interval is the calendar time between surveillance tests, checks, calibrations and examinations to be performed upon a
an instrument or component when it is required to be operable. These tests may be waived when the instrument, component or system is not required to be operabic, but the instrument, component or system shall be tested prior to being declared operable or as practicable following its return to service.
Z.A Venting Venting is the controlled process of discharging air or gas from a confinement to establish temperature, pressure, )3umidity, concentration or other operating condition, in such a manner that rWplacement air or gas is not provided or required during venting.
Vent, used in system names, does not imply a venting process.
Z.B offsite - Offsite means outside of the exclusion area as defined in 10,CFRf Par,t 100.3.
The exclusion area boundary around Cooper Nuclear Station.ls' l
defined in Figure 1.1 and may also be referred to as the Site Boundary.
Z.C tiember of the Public - A Member of the Public is a person in a controlled or unrestricted area who does not receive an occupational dose, s
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LIMITING CONDITION FOR OPERATION SURVETilANCF PFOUTPFMFNTS
' 3. 21. (Corit ' d) 4.21 (Cont'd)
B.
Linuid Effluents B.
Liquid Effluenen
. 6p211cabilltv:
/.t all times.
1.
Concentration Specification:
a.
Radioactive liquid wastes shall be sampled and analyzed according to 1.
Concentration Table 4.21.B.l.
n.
The concentration of b.
The analytical results shall be used-radioactive material in water with methods-in the ODAM to verify l
OFFSITE (Figure 1.1) due to that the average concentration radioactive liquid effluent beyond the SITE BOUNDARY does ' not l
shall not exceed the exceed Specification 3.21.B.1.a.
concentration specified in when Sr 89, Sr-90 and Fe-55 l
10 CFR Part 20.1302 for concentrations are averaged over no radionuclides other than more than 3
months and other dissolved or entrained noble radionuclide concentrations are gases.
For dissolved or averaged over no more than 31 days.
entrained noble gases, the concentration shall not 4
exceed 2 x 10 pC1/ml total
- activity, b.
With the concentration of radioactive material released l
OFFSITE exceeding the limit, attend to the cause without delay and
- restore the concentration within the above limit.
c.
T Fi e provisions of Specification 6.5.2 do not apply.
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3.21 & 4,21 BASES 3.217A 6 4.21.A INSTRUMFNTATION 3.21.A.1 6 4.21.A.1 Liauld Effluent Monitoring The radioactive liquid effluent instrumentation is provided to monitor and control, as applicabic, the release of radioactive material in liquid effluents. The OPERABILITY and use of these instruments implements the requirements of 10 CFR Part 50, Appendix A, General Design Criteria 60, 63, and 64.
The alarm and/or trip setpoints for these instruments are calculated in the manner described in the ODAM to assure that the alarm
)
and/or trip will occur before the limit specified in 10 CFR Part 20.1302 is exceeded. l Control of the normal liquid discharge pathway is assured by station procedures governing locked discharge valves and valve line-up verification.
3.21.A.2 & 4.21.A 2 Gaseous Effluent Monitoring The radioactive gaseous effluent instrumentation is provided to monitor and control, as.
applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.
The location of this instrumentation is simplified flow diagram showing gaseous effluent indicated by a Figure in the ODAM, a treatment and monitoring equipment. The alarm / trip setpoints for these instruments shall be calculated in accordance with methods in the ODAM, which have been reviewed by NRC, to ensure that the alarm will occur prior to exceeding the limits of 10 CFR Part 20.
The process monitoring instrumentation includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the augmented offgas treatment system, The OPERABILITY and use of this instrumentation is consistent with the requirements of General l
Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
2.
In the event no flow rate measurement device is operable on a gaseous stream, alternative 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> estimates are adequate since the system design is constant flow and loss of flow is alarmed in the control room.
3.21.B & 4.21.B LIOUID EFFLUFRS 3.21.B.1 6 4.21.B.1 Concentration This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20,1302.
This limitation provides l' additional assurance that the levels of radioactive materials in bodies of water outside the-site will not result in exposures within (1) the Section IV. A guides on : technical specifications in Appendix I, 10 CFR Part 50, for an individual and (2) the limits of 10 CFR Part 20.1301 and 20.1302(h)(2)(1) to the population. The concentration limit for l-nobic 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.
Since Service Water is not a normal or expected source of significant radioactive release, l
routine sampling and mgnitoring for radioactivity is precautionary.
An activity concentration of 3 x 10 pCi/ml in Service Water effluent is diluted in the discharge l l,
canal to about 1.5% of the 10 CFR 2D Appendix B Table 2 Column 2 concentration with only one'eirculating water pump operating. During normal Station operation the dilution would be even greatvr. By monitoring Service Water effluent continuously for radioactivity and l by confirmatory supling weeklv, reasonable assurance that its activity concentration can be kept to a small fraction of the 10 CFR Part 20.1302 limit and within the specification 3.21.B.2.s limit is provided.
By monitoring Service Water cont inuously and liquid radwaste continuously during discharge w! t'1 the monitor set to alats or trip before.the limit specified in 10 CFR 20.1302 is exceeded, reasonable assurance of compdanceiwith Specification 3.21.B.l.2 is provided.
Verification that radioactivity in liquid effluant-averaged only a small fraction of the '
4 c.ncentration limit is provided by calculations demonstrating compliance with Specification 3.21.B.2.a.
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