ML20062B031
| ML20062B031 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/12/1990 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20062B033 | List: |
| References | |
| NUDOCS 9010240002 | |
| Download: ML20062B031 (9) | |
Text
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,it INSTRUMENTATION i
BASES-
.3/4.3'.3.9-RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMEN The radioactive' gaseous ef fluent -instrumentation is' provided to monitor and control,-as applicable, the releases of radioactive materials in gaseous effluents during actual. or potential releases 'of gaseous ef fl uent s'.
The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology'and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of Specification 3 ll.2.1.a based on average annual'X/Q.
The i
OPERABILITY and usefof this instrumentation is consistent with'the requirements of. General Design Criteria 60, 63, and 64 of Appendix A to i
'10 CFR 50, 3/4.3.3.10- RADIOACTIVE L10010 EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases'of radioactive materials in
' liquid effluents during actual or potential releases of liquid effluents.
The alarm / trip setpoints for these instruments.shall-be calculated and adjusted in accordance with the methodology and-parameters in the 00CM to ensure that:the alarm /tip will occur prior to exceeding the limits of.10
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CFR Part 20.
The OPERABILITY.and use of this-instrumentation is consistent with the requirements of General Design Criteria 60, 63, and
-64 of Appendix A to 10 CFR 50.
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CALVERT CLIFFS - UNIT 1 B 3/4 3-4 Amendment No.105
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. ADMINISTRATIVE CONTROLS a.'
SEMIANNUAL RADIOACTIV'E EFFLUENT RELEASE REPORT (ContinuedU The radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses-to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and~other_ nearby uranium fuel; cycle sources. including doses-e from primary effluent pathways and direct radiation, for the previous calendar year to.show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation.
Acceptable methods for calculating the dose contribution from liquid and gaseoas.
effluents are given _in Regulatory Guide 'l.109,'Rev.1, 0ctober 1977, and NUREG-0133, " Preparation of Radiological Effluent Technical 3
Specifications for Nuclear Power Plants".
j The Radioactive Effluent Release Reports shall ' include the following information for each class-of solid waste (as defined by 10 CFR Part 61).
shipped offsite during the' report period:
a.
Container volume, b.
Total curie' quantity (specify whether determined by measurement
'{
or estimate),
}
c._
Principal radionuclides (specify whether determined by measurement.or estimate),
d.
Source of waste and processing employed (e.g., dewatered spent i
resin,-compacted' dry waste, evaporator bottoms),
Solidification agent or absorbent (e.g., cement).
e.
The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of L
radioactive materials in gaseous and liquid effluents made during the n
reporting period.-
The Radioactive Effluent Release Reports shall include any-changes made during the reporting period to the PROCESS CONTROL PROGRAM-(PCP), and to the OFFSITE DOSE CALCULATION MANUAL (00CM), as well~as a listing of new locations for dose calculations identified by the annual land use census E
pursuant to Specification 3.12.2, a
SPECIAL REPORTS-1 o
6.9.2 Special reports shall be submitted to the Regional Administrator of the NRC Regional Office 'within the time period specified for each h
l4 report. These reports shall be submitted covering the activities
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identified below pursuant to the requirements of the applicable reference specification:
u CALVERT CLIFFS - UNIT 1 6-18 Amendment No. U#f,105 T
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' TABLE'3.3-10
- POST-ACCIDENT MONITO_R_JNG INSTRUMENTATION.
9 G
g MINIMUM
-4 CHANNELS
.p INSTRUMENT OPERABLE ACTION m
y.
1.
Containment' Pressure 2-
. 31' j
2.
Wide Range Logarithmic Neutron' Flux Monitor 2
31' I
E 3.
Reactor Coolant Outlet Temperature 2 [
-4.
Pressurizer Pressure 2
31 5.
Pressurizer Level 2
31:
6.
' Steam Generator Pressure 2/ steam' generator 31 i
i-7.
Steam Generator Level (Wide Range) 2/ steam generator J31 g
8.
Auxiliary feedwater Flow Rate-2/ steam generator 31
_[
9.
RCS Subcooled Margin Monitor; I
31-
- 10. PORV/ Safety Valve Acoustic Flow Monitoring.
-1/ valve
'31 11.
PORV' Solenoid. Power Indication 1/valwe 31
- 12. Feedwater Flow 2
31
- 13. Containment Water Level _(Wide Range) 2-32, 33.
j
- 14. Reactor Vessel Water Level-2*
34, 35-
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l ~k A channel has eight sensors in'a probe.- A channel is operable :if four or more sensors, one or more in-i
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[gg the upper three and three or more in the lower five, are operable.
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TABLE 3.3-10 (Continued)
- E ACTION STATEMENTS
- ACTION 31'
- Withithe number of OPERABLE post accident monitoring channels ~less than required by-Table 3.3-10, either restore the inoperable channel to OPERABLE status within 30 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 32 -
With the number of OPERABLE post-accident monitoring channels one less-than the minimum channel operable requirement in Table.3.3-10, operation may proceed provided
-the inoperable channel is restored to OPERA 8LE status at the next outage of' sufficient duration.
ACTION 33 - With the number of OPERABLE post-accident monitoring channels two less than required by Table 3.3-10, either restore one inoperable channel to OPERABLE status within-30 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 34 - With the number of OPERA 8LE Post-Accident Monitoring Channels one less than the minimum Channel OPERABLE requirement in Table 3.3-10, either restore the system to OPERABLE status within 7 days-if repairs are feasible without shutting down or prepare and submit a Special Report
-to the Commission pursuant to Specification 6.9.2 within 30 days following the event, outlining the action taken, the
. cause of the inoperability and the plans and -schedule for-restoring the system to OPERABLE status.
ACTION 35 - With the, number of OPERABLE Channels two less than required bycTable 3.3-10, either restore the inoperable channel (s).to OPERABLE status within 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />s-if repairs are feasible l without shutting down or:-
1.
Initiate an alternate method of monitoring for core and reactor coolant system voiding; 2.
Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the-system to OPERABLE status;:and' 3.
Restore the system to OPERA 8LE status at the next
- scheduled refueling.
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CALVERT CLIFFS - UNIT 2 3/4 3-41a Amendment No. ##,128
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. f, TABLE 4.3 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w
.n-CHANNEL CHANNEL C
~ INSTRtMENT CHECK CALIBRATION Q
7 1.
Containment Pressure M
R g
2.
Wide Range. Logarithmic Neutron Flux Monitor-M-
N.A.
Q 3.
Reactor Coolant Outlet Temperature M
R 4.
' Pressurizer Pressure M
R 5.
Pressurizer ~ Level M'
R 6.
Steam Generator Pressure M
R 7.
Steam Generator Level-(Wide Range)
M R
,1 8.
Auxiliary feedwater Flow Rate M
P.
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9.
RCS Subcooled Margin Monitor M
R 10.
PORV/ Safety Valve Acoustic Monitor N.A.
R-
- 11. PORV Solenoid' Power Indication M.A.
N.A.
12.
Feedwater Flow M
R d
13.
Containment Water Level (Wide Range)
M R
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N.A.
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' INSTRUMENTATION C.[
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Y 3/4.3.3,6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of-the post-accident instrumentation ensures that 1
3 sufficient'information is available on selected' plant parameters to monitor and assess these variables following -an accident.
This-capability -is consistent with the recommendations of-Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled ~ Nuclear. Plants to--
Assess Plant Conditions During and Following an Accident," December 1975, and HUREG-0578,-
"THI-2 Lessons Learned Task Force Status Report and Short Term Recommendations."
i The subcooled Margin Monitor (SMM), the Heated Junction Thermocouple (HJTC), and the Core Exit Thermocouples (CET) : comprise the -Inadequate' i
Core Cooling (ICC) instrumentation required by Item II.F.2 NUREG-0737, the Post TMI-2 Action Plan.. The function of the ICC instrumentation is to enhance the ability of the plant operator to diagnose the approach to,
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and-recovery from, ICC. Additionally, they aid in tracking reactor coolant inventory.
These instruments are included.i n the Technical Speci_fications at the request o f. NRC Generic Letter 83-37.
These 4
instruments are not required by the accident analysis. nor.to' bring the plant to HOT STAND 8Y or COLD SHUTDOWN.
In the event more than four sensors in a Reactor Vessel Level channel are inoperable, repairs may only be possible during.an extended l
COLD SHUTDOWN. This is because the sensors are accessible only after-the plant has been cooled-down and drained, and the missile shield has' been.
moved.
If only one-channel is inoperable, it should be restored to' OPERABLE status in accordance with the schedule outlined in a Special Report.
If both channels are inoperable, the system shall be restored to OPERABLE status in the next refueling outage.
3/4.3.3.7 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that-
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adequate warning capability is available for the prompt detection of-4 fires.
This capability is required in-order to detect and locate fires in their early stages.-
Prompt detection of fires will. reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.
In the event that a portion of the fire detection instrumentation is
-inoperable, the establishment of frequent fire patrols in the affected' areas is required to provide detection capability until the inoperable instrumentation is restored to operability.
CALVERT CLIFFS - UNIT 2 B 3/4 3-3 Amendment No. JJ#####J,128 l
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sh INSTRUMENTATION BASES.
'3/4.3!329 RADI0 ACTIVE'GASE0US EFFLUENT MONITORING INSTRUMENTATION Thef radioactive gaseous effluent instrumentation-is provided to monitor'
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and control, asl applicable, the releases-of radioactive materials in--
' gaseous effluents during actual or potential releases of gaseous
-)
e f fluent s.
The alarm / trip setpoints-for thest: h truments:shall be Lcalculated and adjusted in accordance with:the methooulc9y and parameters-
-in the ODCM to ensure that.the alarm / trip will occur prior to exceeding t
the ltmits' of: Specification 3.11.2.1.a based on average annual X/Q.
The' i
'OPERABILITYi and use'of this instrumentation is consistent with the requirements of' General Design' Criteria; 60, 63, and 64 of Appendix A to 10 CFR Part.50.
3/4.3.3.10 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor 1
and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The alarm / trip setpoints for these instruments shall be calculated'and adjusted'in accordance with the methodology and parameters in the 00CM to ensure that the alarm /tip will occur prior to exceeding the' limits of ~
10 CFR Part 20. The OPERABILITY and use of this instrumentation'is consistent with the requirements of General Design Criteria 60, 63,- and 64 of-Appendix'A to 10 CFR Part 50.
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.CALVERT CLIFFS - UNIT 2 B 3/4 3-4 Amendment No. 86 A
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-@MINISTRATIVE CONTROLS '
'y'g rW SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued) i The radioactivs Effluent. Release Report' to be submitted'60 days after-January 1 of each year shall also1 include:an asstssment of radiation-doses to the likely..most exposed MEMBER OF THE PUBLIC from reactor releases,and other nearby uranium fuel cycle sources,= including doses from-pr.imary effluent pathways and calendar year to show conformance:w. direct radiation,~ for the ' previous ith!40.CFR Part 190, Environmental I
Radiation Protection Standards for Nuclear Power Operation'. -Acceptable 1
methods'for calculating the dose contribution from liquid and gaseous
'I
' effluents are given t in Regulatory Guide 1.109, Rev.1, October 1977, and NUREG-0133, " Preparation of Radiological Effluent Technical
' Specifications-for Nuclear Power Plants".
,'j The' Radioa'ctive Effluent Release Reports shall include the following
.information for:each class.of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report. period:
a.-
Container volume, b.
Total curie quantity (specify whether determined by measurement 1
or estimate),
Principal radionuclides (specify whether determined by c.
measurement or estimate),
d.
Source ~of waste and processing employed (e.g., dewatered spent resin,compacteddry. waste,evaporatorbottoms),
Solidification agent or absorbent (e.g., cement).
e.
g The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of i
i radioactive' materials in gaseous-and liquid effluents made during the i
reporting period..
The Radioactive Effluent Release' Reports shall include any' changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP), and to the'0FFSITE DOSE CALCULATION MANUAL (00CM),-as well as a listing of new
= locations for' dose calculations identified by the annual land use census pursuant to Specification 3.12.2.
SpECIAL REPORTS 6.9.2 Special reports shall be submitted to.the Regional Administrator "of the NRC Regional 10ffice within the time period specified for each 1
-report. These reports shall be' submitted covering the activities identified below pursuant to the : requirements of the applicable reference specification:
CALVERT CLIFFS - UNIT 2 6-18 Amendment No. # / U,.86
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ADMINISTRATIVE CONTROLS 2
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ECCSActuation,-Spectfthations3.5.2and3.5.3-9 L.
- b..
L! c,
Inoperable Seismic' Monitoring Instrumentation, Specification 3.3.3.3.
_c.
Inoperable' Meteorological-Instrumentation, Specification 3.3.3.4.-
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d.
Seismic event analysis, Specification 4.3.3.3.2.
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Core Barrel Movement, Specification'3.4.11.-
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Fire Detection Instrumentation, Specification 3.3.3.7.
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Fire Suppression-Systems, Specifications 3.7.11.1, 3.7.11.2, 3.7.11.3,.3.7.11.4, :nd 3.7.11.5.
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Penetration Fire Barriers, Specification 3'.7.12.
i.
Steam Generator Tube Inspection Results, Specification 4.4.5.5.a and c.
j.
Specific Activity of Primary Coolant,-Specification 3.4.8.
- k.
Containment Structural Integrity, Specification 4.6.1.6.
1.
- Radioactive Effluents - Calculated Dose and Total Dose, j
Specifications 3.11.1.2, 3.11.2.2,;3.11.2.3, and 3.11.4.
i Radioactive Effluents - Liquid Radwaste, Gaseous Radwaste ~ and -
m.
Ventilation Exhaust Treatment Systems Discharges, Specifications 3.11.1.3 and 3.11.2.4.-
4 n.
Radiological Environmental Monitoring Program, m
Specification 3.12.1.
Radiation Monitoring Instrumentation, Specification 3.3.3.1 o.
(Tabic 3.3-6).
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Overpressuie Protection Systems Specification 3.4.9.3.
q.-
Hydrogen Analyzers, Specification 3.6.5.1.
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Post-Accident Instrumentation, Specification 3.3.3.6
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CALVERT CLIFFS - UNIT 2 6-18a Amendment No. #/5/##/75,128 g
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