ML20205F765
| ML20205F765 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/06/1986 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | Baltimore Gas & Electric Co (BGE) |
| Shared Package | |
| ML20205F769 | List: |
| References | |
| DPR-53-A-120, DPR-69-A-102 NUDOCS 8608190323 | |
| Download: ML20205F765 (15) | |
Text
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- j[ '
UNITED STATES y
g NUCLEAR REGULATORY COMMISSION j
WASHINGTON D.C.20555 h
- ...+
BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET N0. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UldT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. n20 License No. DPl-53 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment by Baltimore Gas & Electric Company (the licensee) dated April 10, 1985, and April 14, 1986, comply 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 operate in conformity with the applications, the provisions of the 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 satistled.
k b
7 P
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-53 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.120, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
[&
GW
~
Ashok C."Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 6, 1986
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l l
ATTACHMENT TO LICENSE AMENDMENT NO. 120 FACILTIY OPERATING LICENSE NO. DPR-53 DOCKET NO. 50-317 Replace the following pages of the Appendix "A Technical Specifications with h
the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf,pages are provided to maintain document completeness.
Remove Pages Intert Pages 3/4 1-9 3/4 1-9 3/4 3-26 3/4 3-26 3/4 3-28 3/4 3-28 B 3/4 3-2 B 3/4 3-2
+
4
4 REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.2 At least two of the following three boron injection flow paths and one associated heat tracing circuit shall be OPERABLE:
a.
Two flow paths from the boric acid storage tanks required to be OPERABLE pursuant to Specifications 3.1.2.8 and 3.1.2.9 via either a boric acid pump or a gravity feed connection, and a charging pump to the Reactor Coolant System, and b.
The flow path from the refueling water tank via a charging pump to the Reactor Coolant System.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With only one of the above required boron injection flow paths to the Reactor j
Coolant System OPERABLE, restore at least two boron injection flow paths to the Reactor Coolant System to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANgBY and borated to a SHUTDOWN MARGIN equivalent to at least 3% ak/k at 200 F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS i
4.1.2.2 At least two of the above required flow paths shall be demonstrated r
OPERABLE:
I At least once per 7 days by verifying that the temperature of the a.
heat traced portion of the flow path from the concentrated boric acid tanks is above the temperature limit line shown on Figure i
3.1-1.
1 b.
At least once per 31 days b verifying that each valve (manual, power operated or automatic in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
At least once per la months by verifying on a SIAS test signal that l
c.
- 1) each automatic valve in the flow path actuates to its correct l
position, and 2) each boric acid pump starts.
CAL. VERT Q.IFFS - UNIT 1 3/4 1-9 Amendment No. 48,4A4,120 J.
REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3 At least one charging pump or one hjgh pressure safety injection pump in the boron injection flow path required OPERABLE pursuant to Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.
APPLICABILITY: MODES 5 and 6.
ACTION:
With no charging pump or high pressure safety injection pump ODERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one of the required pumps is restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.1.2.3 No additional Surveillance Requirements other than those required by Specification 4.0.5.
CALVERT CLIFFS - UNIT 1 3/4 1-10
9 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm / trip setpoints within the specified limits.
APPLICABILITY: As shown in Table 3.3-6.
ACTION:
8 a.
With a radiation monitoring channel alarm / trip se: point exceeding the value shown in table 3.3-6 adjust the set-point to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.
b.
With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS O
4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in Table 4.3-3.
I CALVERT CLIFFS - UNIT 1 3/4 3-25
en s TABLE 3.3-6 I
RADIATION MONITORING INSTRUMENTATION n
MINIMUM m4 CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT 1
INSTRUMENT OPERABLE MODES
_SETPOINT RANGE ACTION i
p k
- 1. AREA MONITORS w
- a. Containment
'i g
- 1. Purge & Exhaust q
Isolation 3
6
< 220 mr/hr 10_j - 10 mr/hr 16 4
- b. Containment Area High Range 2
- 1. 2. 3. & 4
< 10 R/hr 1 - 10 R/hr 30 8
- 2. PROCESS MONITORS g
- a. Containment
- 1. Gaseous Activity wL a) RCS Leakage Detection..
I
- 1. 2. 3. & 4 Not Applicable 1 - 10 ep, j4 6
- 11. Particulate Activity a) RCS Leakage Detection 1
- 1. 2, 3. A 4 Not Applicable 1 - 10 cpm 14 6
- b. Noble Gas Effluent 1
m j
Monitors j
- 1. Main Vent Wide Range 1
- 1. 2. 3. & 4 10-7.to 10 pC1/cc 30 0
=
?
- 11. :iain. Steam Header'."
2
- 1. 2. 3. A.4...
..'... _.10 _2 jf'.10.5.Jt/hr
.30
,3
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- Alarm setpoint to be specified in a controlled document (e.g., setpoint control manual)
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TABLE 3.3-6 (Continued)
TABLE NOTATION ACTION 14 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.
ACTION 16 - With the number of channels OPfRABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.
ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE reqdirement, initiate the preplanned alternate method of monitoring the appro-priate parameter (s), within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:
- 1) either restore the inoperable channel (s) to OPERABLE status within 7 dcys of the event, or
- 2) prepare and submit a Special Report to the Comission pursuant to Specification 6.9.2 within 30 days follow-ing the event, outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE' status.
r CALVERT CLIFFS - UNIT 1 3/4 3-27 Amendment No. 99
O i
TABLE 4.3-3 g
RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l
G, 1
r E
CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE i
p INSTRtMENT
. CHECK CALIBRATION TEST REQUIRED j
3 1.
AREA MONITORS a.
Containment 5
1.
Purge & Exhaust
[
Isolation S
R H
6 b.
Containment Area High Range S
R M
1, 2, 3, & 4 g
2.
PROCESS MONITORS j
y a.
Containment E
1.
Gaseous Activity a) RCS Leakage Detection S
R M
1,.2, 3, & 4
~
- 11. Partietlate Activity y
a) RCS Leakage g
Detection S
R M*
1, 2, 3, & 4 a.
{
l b.
Noble Gas Effluent Monitors
=
.o 1.
Main Vent Wide Range S
R M
1, 2, 3, & 4
.I it. Main Steam Header S.
R M
- 1. 2, 3, & 4 *
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t
.E D
3=
- The CHANNEL CHECK shall be accomplished by comparing samples independently drawn from the main vent.
9 I
3/4.3 INSTRUMENATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF)
TESTkTRUiTAT10h The OPERABILITY of the and bypasses ensure that 1) protective and ESF instrumentation systems the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combi-nation therof exceeds its setpoint, 2) the specified coincidence logic is maintained 3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and 4) sufficient system functional capability is available for protective and ESF purposes from diver:e parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient con-ditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.
The. surveillance requirements specified for these systems ensure that the overall system functiora1 capability is maintained comparable to the original design standards. The periodic surveillance tests per-formed at the minimum frequencies are sufficient to demonstrate this capability.
The meascrement of response time at the specified frequencies pro-vides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the 1
accident analyses. No credit was taken in the analyses for those channe's with response times indicated as not applicable.
Response time may be demonstrated.by any series of sequential, over-Iapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) in place, onsite or offsitetestmeasurementsor2)utilizingreplacementsensorswith certified response times.
3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that
- 1) the radiation levels are continually measured in the areas served CALVERT CLIFFS - UNIT 1 B 3/4 3-1 I
INSTRUMENTATION BASES I
by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
3/4.3.3.2 INCORE DETECTORS The OPERABILITY of the incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.
3/4.3.3.3.
SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.
This capability is required to permit comparison of the measured response to that used in the design basis for the facility and is consistent with the recospendations of Regulatory Guide 1.12. " Instrumentation for Earthquakes,"
i April 1974.
3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instramentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs," February 1972, as supplemen[ed by Supplement 1 to NUREG-0737.
i 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
CALVERT CLIFFS - UNIT 1 B 3/4 3-2 Amendment No. JpJ,Jpp, ddf. 120
y UNITED STATES p,
NUCLEAR REGULATORY COMMISSION r,
- l WASHINGTON. D. C. 20555
+4..... J)#
BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT N3. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. OPR-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Baltimore Gas & Electric Company (the licensee) dated April 10, 1985, and April 14, 1986, comply 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 applications, the provisions of the Act, and the rules and regulations of the Commission; 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 Commission's regulations; e
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 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 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:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.102, are hereby incorporated in the license. The licensee shall operate the f.acility in accordance with the Technical Specifications.
3.
This license an:endment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
- (DG +%-
Ashok C.
ha'dani, Director PWR Project Directorate #8 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 6, 1986
ATTACHMENT TO LICENSE AMENDMENT NO. 102 FACILTIY OPERATING LICENSE NO. DPR-69 DOCKET NO. 50-318 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. The corresponding overleaf pages are provided to maintain document completeness.
Remove Pages Insert Pages 3/4 1-9 3/4 1-9 3/4 3-26 3/4 3-26 3/4 3-27 3/4 3-27 3/4 3-28 3/4 3-28 3/4 3-38 3/4 3-38 8 3/4 3-2 B 3/4 3-2 f
I m
,.. - - -. ~. -
,,,. - -, - -. - - _. - - - _. - - -. - ~ -
REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION
=
3.1.2.2 At least two of the following three boron injection flow paths and
~~
one associated heat tracing circuit shall be OPERABLE:
Two flow paths from the boric acid storage tanks required to be a.
OPERABLE pursuant to Specifications 3.1.2.8 and 3.1.2.9 via either a boric acid pump or a gravity feed connection, and a charging pump to the Reactor Coolant System, and 1
b.
The flow path from the refueling water tank via a charging pump to the Reactor Coolant System.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With only one of the above required baron injection flow paths to the Reactor Coolant System OPERABLE, restore at least two boron injection flow paths to the Reactor Coolant System to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANg8Y and borated to a SHUTDOWN MARGIN equivalent to at least 3% Ak/k at 200 F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.2.2 At least two of the above required flow paths shall be demonstrated l
OPERABLE:
At least once per 7 days by verifying that the temperature of the a.
heat traced portion of the flow path from the concentrated. boric acid tanks is above the temperature limit line shown on Figure 3.1-1.
b.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
At least once per 18 months by verifying on a SIAS test signal I
c.
that:
(1) each automatic valve in the flow path actuates to its correct position, and (2) each boric acid pump starts.
CALVERT CLIFFS - UNIT 2 3/4 1-9 Amendment No. JJ, fg 102
'1 l
i REACTIVITY CONTROL SYSTEMS t
CHARGING PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3 At least one charging pump or one h'igh pressure' safety injection pump in the boron injection flow path required OPERABLE pursuant to Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.
i APPLICABILITY: MODES S and 6.
~
ACTION:
With no charging pump or high pressure safety injection pump OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one of the required pumps is restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.1.2.3 No additional Surveillance Requirements other than those required by Specification 4.0.5.
o l
f CALVERT CLIFFS-UNIT 2 3/4 1-10 L
~
INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION l
LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarWtrip setpoints within the specified limits.
APPLICABILITY: As shown in Table 3.3-6.
ACTION:
With a radiation monitoring channel alann/ trip set>oint a.
exceeding the value shown in Table 3.3-6, adjust tw set-point to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.
b.
With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
t t
SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in Table 4.3-3.
CALVERT CLIFFS - UNIT 2 3/4 3-25
es TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION k
MINIMUM n
CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT C
ItiSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION 4
=
1.
AREA MONITORS e
E a.
Containment U
- i. Purge & Exhaust
-4 4
N Isolation 3
6 1 220 mr/hr 10
- 10 mr/hr 16 b.
Containment Area High 8
Range 2
1, 2, 3 & 4 1
1 0 R/hr 1 - 10 R/hr 30 2.
PROCESS MONITORS u
A, a.
Containment 1.
Gaseous Activity a) RCS Leakage 1
6 Detection 1
1, 2, 3 & 4 Not Applicable 10 - 10 cpm 14
- 11. Particulate Activity a) RCS Leakage k
Detection 1
1, 2, 3 & 4 Not Applicable 10 - 10 cp, j4 j
6 k
b.
Noble Gas Effluent a
Monitors 10 to 10' uCi/cc 30
- i. Main Vent Wide Range 1
1, 2, 3 & 4
~
,s
- 11. Main Steam Header 2
1, 2, 3 & 4 10-2 to 105 R/hE 30 E
M
- Alarmsetpointtobespecifiedinacontrolleddocument(e.g.,setpointcontrolmanual).
2
TABLE 3.3-6 (Continued)
TABLE NOTATION ACTION 14 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.
ACTION 16 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.
ACTION 30 - With the number of channels OPERABL'E less than required by the Minimum Channels OPERABLE requirement, initiate the preplanned alternate method of monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:
1
- 1) eitherrestoretheinoperablechannel(s)toOPERABLE status within 7 days of the event, or
- 2) prepare and submit a Special Report to the Commission I
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 i
for restoring the system to OPERABLE status.
i CALVERT CLIFFS - UNIT 2 3/4 3-27 Amendment No. SY,102
RI
)
TABLE 4.3-3 g
RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E
CHANNEL MODES IN WHICH P
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE 4
INSTRUMENT CHECK CALIBRATION TEST REQUIRED Y
1.
AREA MONITORS 1
C
}
a.
Containment 1.
Purge & Exhaust m
Isolation S
R M
6 b.
Containment Area High Range S
R M
1, 2, 3 &,
y 2.
PROCESS MONITORS
{
a.
Containment 1.
Gaseous Activity a) RCS Leakage Detection S
R M
1, 2, 3 & 4
- 11. Particulate Activity
{
a) RCS Leakage s
Detection S
R M
1, 2, 3 & 4 k
b.
Notile Gas Effluent
="
Monitors
.E 1.
Main Vent Wide Range S
R M
1, 2, 3.8 4
.O
- 11. Main Steam Header S
R M
1, 2, 3 & 4 E
k s
INSTRUMENTATION REMOTE SHUTDOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with readouts displayed external to the control room.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
-s a.
With the number of OPERABLE remote shutdown monitoring channels 1
less than required by Table 3.3-9, either restore the s
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 />, b.
The provisions of Specification 3.0.4 are not applicable.
(
SURVEILLANCE REQUIREMENTS 4.3.3.5 Each remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by perfonnance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6.
~
l l
l CALVERT CLIFFS - UNIT 2 3/4 3-37
8 I n#
TABLE 3.3-9 M
E REMOTE SHUTDOWN MONITORING INSTRUMENTATION 4
n i
C MINIMUM i
4 READOUT MEASUREMENT CHANNELS
{
INSTRUMENT LOCATION RANGE OPERABLE E
1.
Wide Range Neutron Flux
- 2C43 0.1 cps-200%
1 4
2.
Reactor Trip Breaker Cable Spreading m
i Indication Room OPEN-CLOSE 1/ trip breaker l
3.
Reactor Coolant Cold leg Temperature 2C43 212-7050F 1
4 Pressurizer Pressure 2C43 0-4000 psia 1
M 5.
Pressurizer Level 2C43 0-360 inches 1.
6.
Steam Generator Pressure 2C43 0-1200 psig 1/ steam generator I
I 7.
Steam Generator Level 2C43
-401 to +63.5 inches 1/ steam generator t
s k
- When the 2C43 instrumentation is inoperable, the wide range neutron flux monitors located in the
=
[
auxiliary feedwater pump room may be utilized to meet this requirement. During the period when
,o the instruments are utilized to meet the above requirement, they will be subject to the surveil-lance requirements of Table 4.3-6.
E
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O e
e
3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF)
INSTRUMENTATION The OPERABILITY of the and bypasses ensure that 1) protective and ESF instrumentation systems the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combi-nation therof exceeds its setpoint, 2) the specified coincidence logic is maintained, 3) sufficient m dundancy is maintained to permit a channel to be out of service for testing or maintenance, and 4) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient con-ditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.
The surveillance mquirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests per-i fonned at the minimum frequencies are sufficient to demonstrate this capability.
The measurement of response time at the specified frequencies pro-vides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable.
Response time may be demonstrated by any series of sequential, over-lapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined.' Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacen,ent sensors with certified response times.
3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that
- 1) the radiation levels are continually measured in the areas served CALVERT CLIFFS - UNIT 2 B 3/4 3-1
INSTRUMENTATION BASES by the individual channels and 2) the alann or automatic action is initiated when the radiation level trip setpoint is exceeded.
3/4.3.3.2 INCORE DETECTORS
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The OPERABILITY of the incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.
3/4.3.3.3 SEISMIC INSTRUMENTATION l
The OPERABILITY of the seismic instrumentation ensures that sufficient j
capability is available to promptly determine the magnitude of a seismic l
event and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured response to that L
used in the design basis for the facility and is consistent with the reconenendations of Regulatory Guide 1.12. " Instrumentation for Earthquakes,"
April 1974.
3/4.3.3.4 METEOROLOGICAL' INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radia-tion doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the reconnendations of Regulatory Guide 1.23. "0nsite Meteorological Programs". February 1972, as supplemented by Supplement I to NUREG-0737, 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to pennit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
i CALVERT CLIFFS - UNIT 2 B 3/4 3-2 Amendment No.85,!N, (f.102 l
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