ML20064B205
| ML20064B205 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/28/1990 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064B206 | List: |
| References | |
| NUDOCS 9010150239 | |
| Download: ML20064B205 (19) | |
Text
. -
[ya me:qk UNITED STATES NUCLEAR REGULATORY COMMISSION l
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BALTIMORE GAS AND. ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT-CLIFFS. NUCLEAR POWER PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.147 License No. DPR-53 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated July 10, 1987, as supplemented on August 31, 1989, and August 3, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the l
Comission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorized I
by this amendment can be conducted without endangering the health l
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 common l
defense and security or to the health and safety raf the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part i
51 of the Comission's regulations and all applicable requirements have been satisfied.
i 2.
Accordingly, the license is amended by changes to the Technical
-j Specifications as indicated in the attachment to this license
'j amendment, and paragraph 2.C.(2) of Facility Operating License I
No. DPR-53 is hereby amended to read as follows:
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L 9010150239 900920 I
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2 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.147, are I
hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION l
l-
% Robert A. Capra, Direc or Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 28, 1990 i
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W NUCLEAR REGULATORY COMMISSION 2
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b BALTIMORE GAS.AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS WUCLEAR POWER PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 148 License No. DPR-69 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (thelicensee)datedJuly 10, 1987, as supplemented on August 31, 1989,'and August 3, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will o>erate in conformity with the application, the provisions of t1e Act, and the rules and regulations of the Comission-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; 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical' Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Facility Operating License No.
DPR-69'is hereby amended to read as follows:
4
---t
2 (2). Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.148, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION h v:
Y g Robert A. Capra, Director
~
Project Directorate I.1 Division of Reactor Projects. I/II Office of Nuclear Reactor Regulation-
Attachment:
Changes to the Technical Specifications i
Date of Issuance:
September 28, 1990 i
h ATTACHNENT.TO. LICENSE.AMENDNENTS ANENDNENT.WO. 147.. FACILITY.0PERATING. LICENSE.NO. DPR-53 AMENDNENT NO.-148. FACILITY.0PERATING LICENSE.NO. DPR.69 j
DOCKET.NOS. 50-317 AND 50-318 Revise Appendix A as follows:
Remove.Pages Insert.Pages 3/4 3-41 3/4 3-41 3/4 3-41a 3/4 3-41a 3/4 3-42 3/4 3-42 B 3/4 3-3 8 3/4 3-3 4
B 3/4 3-4*
B 3/4 3-4*
6-18*
6-18*
6-18a 6-18a
- Pages that did not change, but are overleaf i
4-y w
a
TABLE 3.3-10 POST-ACCIDENT MONITORING INSTRUMENTATION nNM g3 MINIMUM CHANNELS
[3 INSTRUMENT OPERABLE ACTION m
US 1.
Containment Pressure 2
31
[_
2.
Wide Range Logarithmic Neutron Flux Monitor 2
31
!)
3.
Reactor Coolant Outlet Temperature 2
31 4.
Pressurizer Pressure 2
31 5.
Pressurizer Level 2
31 6.
Steam Generator Pressure 2/ steam generator 31-7.
Steam Generator Level (Wide Range) 2/ steam generator 31 j$
8.
Auxiliary Feedwater Flow Rate 2/ steam generator 31 y
9.
RCS Subcooled Margin Monitor 1
31-
$5 10.
PORV/ Safety Valve Acoustic flow Monitoring 1/ valve 31 11.
PORY Solenoid Power Indication 1/ valve 31-12.
Feedwater Flow 2
31
- 13. Containment Water level (Wide Range) 2 32, 33 g
14.
34, 35 EY E.
r
.E DD 2'%u
+
_, st
'A channel has eight sensors in a probe. A channel is oper able if four or more sensors, one or more in g;U the upper three and three or more in the lower five, are operable.
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TABLE 3.3-10 (Continued)
ACTION STATEMENTS ACTION 31 - With:the 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 OPERABLE status at the next outage of sufficient duration.
ACTION 33 - With the number of OPERABLF post-accident monitoring channels two less than requi ed by Table 3.3-10, either restore one inoperable channe; 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 OPERABLE 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 by Table 3.3-10, either restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if repairs are feasible 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 OPERABLE status at the next scheduled refueling.
CALVERT CLIFFS - UNIT 1 3/4 3-41a Amendment No. JJ7, 147 l
TABLE 4.3-10 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
=
w CHANNEL CHANNEL n
k INSTRUMENT CHECK CALIBRATION n
7
-1.
Containment Pressure M
R g
2.
Wide Range Logarithmic Neutron Flux Monitor M
N.A.
Z 3.
Reactor Coolant Outlet Temperature M
R
~
4.
Pressurizer Pressure M
R 5.
Pressurizer Level M
R l
6.
Steam Generator Pressure M
R 7.
Steam Generator Level (Wide Range)
.M R
m1 8.
Auxiliary Feedwater Flow Rate M
R
[
9.
RCS Subcooled Margin Monitor M
R
~
10.
PORV/ Safety Valve Acoustic Monitor N.A.
R 11.
PORV Solenoid Power Indication N.A.
N.A.
12.
Feedwater Flow M
R
- 13. Containment Water Level (Wide. Range)
M R
[
14.
Reactor. Vessel Water Level M
N.A.
E
!!a F.
PhR RkB 1.
h----------------- ------------------------- ------------
INSTRUMENTATION BASES 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post accident instrumentation ensures that 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 NUREG 0578, "THI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."
The subcooled Margin Monitor (SMM), the Heated Junction Thermocouple (HJTC), and the Core Exit Thermocouples (CET) comprise the Inadequate Core Cooling (ICC) instrumentation required by Item II.F.2 NUREG-0737, the Post THI-2 Action Plan.
The function of the ICC instrumentation is to enhance the ability of the plant operator to diagnose the approach to, and recovery from, ICC. Additionally, they aid in tracking reactor coolant inventory.
These instruments are included in the Technical Specifications at the request of NRC Generic Letter 83-37.
These instruments are not required by the accident analysis, nor to bring the plant to HOT STANDBY 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 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 adequate warning capability is available for the prompt detection of 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 1 B 3/4 3-3 Amendment No. 2E/JJ/SS/JpJ,147
INSTRUMENTATION-I BASES 3/4.3.3.9 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor l
and control, as applicable, the-releases of radioactive materials in gaseous effluents during actual:or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of Specification 3.11.2.1.a based on average annual X/Q.
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.
3/4.3.3.10 RADI0 ACTIVE LIOUID 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.
1 The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to l
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 I
consistent with the requirements of General Design Criteria 60, 63, and j
-64 of Appendix A to 10 CFR 50.
I 1
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l CALVERT CLIFFS - UNIT 1 B 3/4 3-4 Amendment No. 106 l
1:
.[1
ADMINISTRATIVE CONTROLS SEMIAMNUAL RADIDACTIVE EFFLUENT RELEASE REPORT (Continued)
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 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 gaseous effluents are given in Regulatory Guide 1.109, Rev.1, October 1977, and NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants".
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 resin, compacted dry waste, evaporator bottoms),
e.
Solidification agent or absorbent (e.g., cement).
The Radioactive Effluent Release Reports shall include a list and description of unplanned releases-from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the 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 (ODCM), 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 Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference u
L specification:
l i
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CALVERT CLIFFS - UNIT 1 6-18 Amendment No ##f,165 l
L
'~
I
.o ADMINISTRATIVE CONTROLS L*
l a.
ECCS Actuation, Specifications 3.5.2 and 3.5.3 b.
Inoperable Seismic Monitoring Instrumentation, i
j_
Specification 3.3.3.3.
Inoperable Meteorological Instrumentation, L
c.
L Specification 3.3.3.4.
d.
Seismic event analysis, Specification 4.3.3.3.2.
j e.
Core Barrel Movement, Specification 3.4.11.
f.
Fire Detection Instrumentation, Specification 3.3.3.7.
g.
Fire Suppression Systems, Specifications 3.7.11.1, 3.7.11.2, t
3.7.11.3, 3.7.11.4, and 3.7.11.5.
h.
Penetration Fire Barriers, Specification 3.7.12.
E 1.
Steam Generator Tube Inspection Results, Specification l
4.4.5.5.a and c.
j.
Specific Activity of Primary Coolant, Specification 3.4.8.
1 k.
Containment Structural Integrity, Specification 4.6.1.6.
1.
Radioactive Effluents - Calculated Dose and Total Dose, Specifications 3,11.1.2, 3.11.2.2, 3.11.2.3, and 3.11.4.
m.
Radioactive Effluents - Liquid Radwaste, Gaseous Radwaste and Ventilation Exhaust Treatment Systems Discharges, Specifications 3.11.1.3 and 3.11.2.4.
n.
Radiological Environmental Monitoring Program, Specification 3.12.1.
o.
Radiation Monitoring Instrumentation, Specification 3.3.3.1 (Table 3.3-6).
p.
Overpressure Protection Systems, Specification 3.4.9.3.
q.
Hydrogen Analyzers, Specification 3.6.5.1.
r.
Post-Accident Instrumentation, Specification 3.3.3.6 CALVERT CLIFFS - UNIT 1 6-18a Amendment No. JJ/#f/JS HJJ7, 147 nj
~
-TABLE 3.3-10 POST-ACCIDENT MONITORING INSTRUMENTATION 9
r-5 MINIMUM 4
5 CHANNELS
.n INSTRUMENT OPERABLE ACTION 3
1.
Containment Pressure 2'
31 2.
Wide Range Logarithmic Neutron Flux Monitor 2
31 e
E 3.
Reactor Coolant Outlet Temperature 2
31
[
4.
Pressurizer' Pressure 2
31 5.
Pressurizer Level 2
31 6.
Steam Generator Pressure 2/ steam generator 31 7.
Steam Generator Level (Wide Range) 2/ steam generator 31 i
q 8.
Auxiliary Feedwater Flow Rate 2/ steam generator
~ 31
[
9.
RCS Subcooled Margin Monitor 1
31
- 10. PORV/ Safety Valve Acoustic Flow Monitoring 1/ valve 31
- 11. PORV Solenoid Power Indication 1/ valve 31
- 12. Feedwater Flow 2
31
- 13. Containment Water Level (Wide Range) 2 32, 33 14.
34, 35 E
e
.E OM
' g' A channel has eight sensors in a probe. A channel is operable if four or more sensors, one or more-in i
$g the upper three and three or more in the lower five, are operable.
i E4 b
~.
L..
TABLE 3.3-10 (Continued)
ACTION STATEMENTS ACTION 31 - With the number of OPERABLE post-accident monitoring-channels less than required by Table 3.3-10, either restore t
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 OPERABLE status at the next outage of sufficient duration.
i ACTION 33 - With the number of OPERABLE post accident monitoring l
channels two less than required by Table 3.3-10, either i
restore one inoperable channel to OPERABLE status within l
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 OPERABLE 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 by Table 3.3-10, either restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if repairs are feasible 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 l
pursuant to Specification 6.9.2 within 30 days i
following the event, outlining the action taken, the cause of the inoperability and the plans and schedule p
for restoring the system to OPERABLE status; and 3.
Restore the system to OPERABLE status at the next scheduled refueling.
CALVERT CLIFFS - UNIT 2 3/4 3-41a Amendment No. ##,148 O
e TABLE 4.3-10 h
POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE0UIREMENTS
- 5 n
CHANNEL CHANNEL
{
INSTRUMENT CHECK CALIBRATION i
1..
Containment Pressure.
M R
2.
Wide Range Logarithmic Neutron Flux Monitor M
N.A.
g G
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
R 9.
RCS Subcooled Margin Monitor M
R 10.
PORV/ Safety Valve Acoustic Monitor N.A.
R 11.
PORV Solenoid Power Indication N.A.
N.A.
12.
Feedwater Flow M
R
- 13. Containment Water Level-(Wide Range)
M R
{
14.
N.A.
E 2a tb R
a.
O) f
~
-, ~ - - - ~ -
1 INSTRUMENTATION BASES 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that 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 NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and.
Short-Term Recommendations."
The subcooled Margin Monitor (SMM), the Heated Junction Thermocouple (HJTC),andthe Core Exit Thermocouples (CET) comprise the ' Inadequate Core Cooling (ICC) instrumentation required by Item II.F.2 NUREG-0737,-
j the Post THI-2 Action Plan. The function of the ICC instrumentation is to enhance the ability 'of the plant operator to diagnose the approach to, and recovery from, 100. Additionally, they aid in tracking reactor coolant inventory.
These instruments are included in the Technical Specifications at the request of NRC Generic Letter 83-37.
These instruments are not required by the accident analysis, nor to bring the
)
plant to HOT STANDBY 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 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 oe 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 adequate warning capability is available for the prompt detection of 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 cperability.
CALVERT CLIFFS - UNIT 2 B 3/4 3-3 Amendment No. JJ/#/S/JIJ,148 n
n.
-INSTRUMENTATION' BASES 3/4.3.3.9 'RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor
' and control, as applicable, the releases of radioactivo materials in I
gaseous effluents during actual or potential releases of gaseous ef fluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters i
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 OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64,of Appendix A to 10 CFR Part 50.
3
~
I 3/4.3.3.10 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION 1
l!
The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in i
liquid effluents; during actual or potential releases of liquid effluents.
The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm /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.
4 l
CALVERT CLIFFS - UNIT 2 8 3/4 3-4 Amendment No. 55
- ru
L.,
l L.
ADMINISTRATIVE CONTROLS L
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)
L 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 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 gaseous effluents are given in Regulatory Guide 1.109, Rev.1, October 1977, and NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants".
The Radioactive Effluent Release Reports shall include the following i
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 measurementorestimate),
j l
d.
Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),
e.
Solidification agent or absorbent (e.g., cement).
The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to U9 RESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the 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 pursuant to Specification 3.12.2.
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the NRC Regional Office within the time period specified for each 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. # M,86
L '!
B*
t ADMINISTRATIVE CONTROLS g
a.
ECCS Actuation, Specifications 3.5.2 and 3.5.3 b.
Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
c.
Inoperable Meteorological Instrumentation, Specification 3.3.3.4.
l d.
Seismic event analysis, Specification 4.3.3.3.2.
j e.
Core Barrel Movement, Specification 3.4.11.
f.
Fire Detection Instrumentation, Specification 3.3.3.7.
1 l
g.
Fire Suppression Systems, Specifications 3.7.11.1, 3.7.11.2, 3.7.11.3, 3.7.11.4, and 3.7.11.5.
h.
Penetration Fire Barriers,-Specification 3.7.12, i
1.
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 Inteccity, Specification 4.6.1.6.
1.
Radioactive Effluents - Calculated Dose and Total Dose, Specifications 3.11.1 2, 3.11.2.2, 3.11.2.3, and 3.11.4.
m.
Radioactive Effluen'.s - Liquid Radwaste, Gaseous Radwaste and Ventilation Exhaust Treatment Systems Discharges, Specifications 3.11.1.3 and'3.ll.2.4.
Radiological Environmental Monitoring Program, n.
Specification 3.12.1.
o.
Radiation Monitoring Instrumentation, Specification 3.3.3.1 (Table 3.3-6).
p.
Overpressure Protection Systems, Specification 3.4.9.3.
q.
Hydrogen Analyzers, Specification 3.6.5.1.
r.
Post-Accident Instrumentation, Specification 3.3.3.6 CALVERT CLIFFS - UNIT 2 6-18a Amendment No. Jf/7J/EE/SS,148 FL
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