ML20044C602
| ML20044C602 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  (DPR-53-A-180) |
| Issue date: | 04/02/1993 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044C603 | List: |
| References | |
| NUDOCS 9304080306 | |
| Download: ML20044C602 (37) | |
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'1 UNITED STATES
' [.I Al j NUCLEAR REGULATORY COMMISSION
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WASHINGTON. D.C. 20555-0001 gv.....f BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 1 i
l AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.180 l
License No. DPR-53 1.
The Nuclear Regulatory Commission (the Commission) has found that:
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A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated March 9, 1993, 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 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; 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-53 is hereby amended to read as follows:
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i 9304080306 930402 PDR ADOCK 05000317 P
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.180, 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 to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION TNV. [W Robert A. Capra, Director Project Diiectorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 2,1993
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 180 FACILITY OPERATING LICENSE NO. DPR-53 DOCKET N0. 50-317 Revise Appendix A as follows:
Remove Paaes Insert Paaes 3/4 2-2 3/4 2-2 3/4 2-6 3/4 2-6 3/4 2-11 3/4 2-11 3/4 2-12 3/4 2-12 3/4 3-31 3/4 3-31 3/4 3-32 3/4 3-32
- 3/4 3-33 thru - 60 3/4 3-33 thru - 61
- These pages are text rollover pages with no changes as the result of this amendment. The amendment number appears at the bottom of the page to indicate a shift in the text.
I
3/4.2 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) c.
Verifying at least once per 31 days that the AXIAL SHAPE INDEX is maintained within the limits of Figure 3.2.1-2, where 100 percent of the allowable power represents the maximum THERMAL POWER allowed by the following expression:
MxN where:
1.
M is the maximum allowable THERMAL POWER level for the existing Reactor Coolant Pump combination.
2.
N is the maximum allowable fraction of RATED THERMAL POWER as determined by the P, curve of Figure 3.2.1-3.
4.2.1.4 Incore Detector Monitorino System - The Incore Detector Monitoring System may be used for monitoring the core power distribution by verifying i
that the incore detector Local Power Density alarms:
a.
Are adjusted to satisfy the requirements of the core power distribution map which shall be updated at least once per 31 days of accumulated operation in MODE 1.
l b.
Have their alarm setpoint adjusted to less than or equal to the limits shown on Figure 3.2.1-1 when the following factors are appropriately included in the setting of these alarms:
1.
A measurement-calculational uncertainty factor of 1.062,**
I 2.
An engineering uncertainty factor of 1.03, 3.
A linear heat rate uncertainty factor of 1.002 due to axial fuel densification and thermal expansion, and 4.
A THERMAL POWER measurement uncertainty factor of 1.02.
For Unit 1 Cycle 11 only, when the percentage of OPERABLE incore detector locations (e.g., strings) falls below 75%, this surveillance shall be performed at least once per 15 days of accumulated operation in MODE 1.
For Unit 1 Cycle 11 only, when the percentage of OPERABLE incore detector locations (e.g., strings) falls below 75%, the measurement-calculational uncertainty factor on linear heat rate shall be increased by 1% (from 1.062 to 1.072) prior to comparison with the Technical Specification limits.
CALVERT CLIFFS - UNIT 1 3/4 2-2 Amendment No. 180
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t 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.2 TOTAL PLANAR RADIAL PEAKING FACTOR - FTy LIMITING CONDITION FOR OPERATION 3.2.2.1 The calculated value of P,, shall be limited to 51.70.**
l APPLICABILITY: MODE l'.
1 ACTION: With P,,> 1.70, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either:
a.
Withdraw and maintain the full length CEAs at or beyond the Long Term Steady State Insertion Limits of Specification 3.1.3.6 and reduce THERMAL POWER as follows:
~
1.
Reduce THERMAL POWER to bring the combination of THERMAL POWER and P,, within the limits of Figure 3.2.2-1, or 2.
Reduce THERMAL POWER to less than or equal to the limit established by the Better Axial Shape Selection System 4
(BASSS) as a function of P,,; or b.
Be in at least HOT STANDBY.
SURVEILLANCE REQUIREMENTS 4.2.2.1.1 The provisions of Specification 4.0.4 are not applicable.
4.2.2.1.2 P, shall be calculated as P = F,d to be within its limit at the using a full core power distribution, system.
y P,, shall be detemine i
following intervals:
a.
Prior to operation above 70 percent of RATED THERMAL POWER after each fuel loading, b.
At least once per 31 days *** of accumulated operation in l
MODE 1, and Within four hours if the AZIMUTHAL POWER TILT (T,) is > 0.030.
c.
For Unit 1 Cycle 11 only, when the percentage of OPERABLE incore detector locations (e.g., strings) falls below 75%, the calculated value of P,, shall be increased by 1% prior to comparison with the limit.
See Special Test Exception 3.10.2.
For Unit 1 Cycle 11 only, when the percentage of OPERABLE incore detector locations (e.g., strings) falls below 75%, this surveillance shall be perfomed at least once per 15 days of accumulated operation in MODE 1.
CALVERT CLIFFS - UNIT 1 3/4 2-6 Amendment No. 180 l
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l' 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR - FJ 4
]
l LIMITING CONDITION FOR OPERATION 3.2.3 The calculated value of P, shall be limited to 51.70.**
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APPLICABILITY: MODE 1*.
4 3
ACTION: With P, > 1.70, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either:
l a.
Be in at least H0T STANDBY, or b.
Withdraw and maintain the full length CEAs at or beyond the Long i
Term Steady State Insertion Limits of Specification 3.1.3.6 and j
reduce THERMAL POWER as follows:
1.
Reduce THERMAL POWER to bring the combination of THERMAL j
POWER and P, within the limits of Figure 3.2.3-1, or 2.
Reduce THERMAL POWER to less than or equal to the limit established by the Better Axial Shape Selection System j
(BASSS) as a function of P,.
i When the THERMAL POWER is detemined from Figure 3.2.3-1, it shall be used to establish a revised upper THERMAL POWER LEVEL 1
limit on Figure 3.2.3-2 (i.e., Figure 3.2.3-2 shall be truncated at the allowable fraction of RATED THERMAL POWER determined by Figure 3.2.3-1).
Subsequent operation shall be maintained within i
the reduced acceptable operation region of Figure 3.2.3-2.
I SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.
4.2.3.2 P, shall be calculated as P = F, using a full core power distribution mapping system.
P, shall be detemined to be within its limit at the following intervals:
a.
Prior to operation above 70 percent of RATED THERMAL POWER after each fuel loading.
For Unit 1 Cycle 11 only, when the percentage of OPERABLE incore detector locations (e.g., strings) falls below 75%, the calculated value of P, shall be increased by 1% prior to comparison with the limit.
See Special Test Exception 3.10.2.
i CALVERT CLIFFS - UNIT 1 3/4 2-11 Amendment No. 180
3/4.2 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) b.
At least once per 31 days"* of accumulated operation in MODE l
1, and Within four hours if the AZIMUTHAL POWER TILT (T,) is > 0.030.
c.
4.2.3.3 P, shall be determined each time a calculation is required by using the incore detectors to obtain a power distribution map with all full length CEAs at or above the Long Term Steady State Insertion Limit for the existing Reactor Coolant Pump combination.
a i
e For Unit 1 Cycle 11 only, when the percentage of OPERABLE incore detector locations (e.g., strings) falls below 75%, this surveillance j
shall be perfonned at least once per 15 days of accumulated operation in M0DE 1.
i CALVERT CLIFFS - UNIT 1 3/4 2-12 Amendment No. 180
i 3/4.3 INSTRUMENTATION i
3/4.3.3 MONITORING INSTRUMENTATION Incore Detectors LIMITING CONDITION FOR OPERATION t
3.3.3.2 The Incore Detection System shall be OPERABLE with at least one OPERABLE detector segment in each core quadrant on each of the four axial elevations containing incore detectors and as further specified below:
a.
For monitoring the AZIMUTHAL POWER TILT:*
l At least two quadrant symmetric incore detector segment groups at each of the four axial elevations containing incore detectors in the outer 184 fuel assemblies with sufficient OPERABLE detector segments in these detector groups to compute at least two AZIMUTHAL POWER TILT values at each of the four axial elevations containing incore detectors.
b.
For recalibration of the Excore Neutron Flux Detector System:
1.
At least 75%** of all incore detector segments, l
2.
A minimum of 9 OPERABLE incore detector segments at each detector segment level, and 3.
A minimum of 2 OPERABLE detector segments in the inner 109 fuel assemblies and 2 0PERABLE segments in the outer 108 fuel assemblies at each segment level.
c.
For monitoring the UNR0DDED PLANAR RADIAL PEAKING FACTOR, the UNR0DDED INTEGRATED RADIAL PEAKING FACTOR, or the linear heat rate:
For Unit 1 Cycle 11 only, the following requirements shall be substituted for Limiting Condition for Operation 3.3.3.2.a:
i At least eight quadrant symetric incore detector segment groups containing incore detectors in the outer 184 fuel assemblies with sufficient OPERABLE detector segments in these detector groups to compute at least one AZIMUTHAL POWER TILT value at each of the four axial elevations containing incore detectors and at least two AZIMUTHAL POWER TILT values at three axial elevations containing incore detectors.
For Unit 1 Cycle 11 only, the following requirement shall be 4
substituted for Limiting Condition for Operation 3.3.3.2.b.1:
i At least 60% of all incore detector segments, CALVERT CLIFFS - UNIT 1 3/4 3-31 Amendment No. 180
3/4.3 INSTRUMENTATION LIMITING CONDITION FOR OPERATION (Continued) i 1.
At least 75%*** of all incore detector locations, l
l 2.
A minimum of 9 OPERABLE incore detector segments at each detector segment level, and 3.
A minimum of 2 OPERABLE detector segments in the inner
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109 fuel assemblies and 2 OPERABLE segments in the outer 108 fuel assemblies at each segment level. An OPERABLE incore detector segment shall consist of an OPERABLE rhodium detector constituting one of the segments in a fixed
^
detector string.An OPERABLE incore detector location shall f
consist of a string in which at least three of the four incore detector segments are OPERABLE.
An OPERABLE quadrant ymetric incore detector segment group shall consist of a minimum of-three PTRABLE rhodium incore detector segments in 90 symetric fuel assembi;es.
APPLICABILITY: When the Incore Detection System is used for:
a.
Monitoring the AZIMUTHAL POWER TILT, b.
Recalibration of the Excore Neutron Flux Detection System, or c.
Monitoring the UNR0DDED PLANAR RADIAL PEAKING FACTOR, the UNR00DED INTEGRATED RADIAL PEAKING FACTOR, or the linear heat rate.
ACTION: With the Incore Detection System inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
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For Unit 1 Cycle 11 only, the following requirement shall be substituted for Limiting Condition for Operation 3.3.3.2.c.1:
i At least 60% of all incore detector locations, CALVERT CLIFFS - UNIT 1 3/4 3-32 Amendment No. 180
3/4.3 INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4.3.3.2 The Incore Detection System shall be demonstrated OPERABLE:
a.
By performance of a CHANNEL CHECK within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to its use and at least once per 7 days thereafter when required for:
1.
Monitoring the AZIMUTHAL POWER TILT.
2.
Recalibration of the Excore Neutron Flux Detection System.
3.
Monitoring the UNR0DDED PLANAR RADIAL PEAKING FACTOR, the UNRODDED INTEGRATED RADIAL PEAKING FACTOR, or the linear heat rate.
b.
At least once per REFUELING INTERVAL by performance of a CHANNEL CALIBRATION operation which exempts the neutron detectors but includes all electronic components. The neutron detectors shall be calibrated prior to installation in the reactor core.
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CALVERT CLIFFS - UNIT 1 3/4 3-33 Amendment No. 180 l
3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Seismic Instrumentation LINITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE.
APPLICABILITY: At all times.
ACTION:
a.
With one or more seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-4.
4.3.3.3.2 Each of the above seismic monitoring instruments actuated during a seismic event shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION performed within 5 days following the seismic event.
Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days describing the magnitude, frequency spectrum and resultant effect upon facility features important to safety.
CALVERT CLIFFS - UNIT 1 3/4 3-34 Amendment No. 180
3/4.3 INSTRUMENTATION TABl..E 3.3-7 SEISMIC MONITORING INSTRUMENTATION MINIMUM MEASUREMENT INSTRUMENT INSTRUMENTS AND SENSOR LOCATIONS RANGE OPERABLE 1.
Triaxial Time-History Strong Motion Accelographs a.
0-YE-001 Unit 1 Containment Base 0-1g 1
b.
0-YE-002 Unit 1 Containment 69' 0-1g 1
c.
0-YE-003 Auxiliary Bldg. Base 0-19 1
d.
0-YE-004 Intake Structure 0-19 1
e.
0-YE-005 Free Field 0-19 1
2.
Triaxial Seismic Switches a.
0-YS-001 Unit 1 Containment Base NA 1
b.
0-YS-002 Unit 1 Containment 69' NA 1
3.
Seismic Acceleration Recorder a.
0-YRC-001 Control Room NA 1
b.
0-YR-001 Control Room NA 1
CALVERT CLIFFS - UNIT 1 3/4 3-35 Amendment No. 180
3/4.3 INSTRUMENTATION TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL CHANNEL FUNCTIONAL INSTRUMENTS AND SENSOR LOCATIONS CHECK **
CALIBRATION TEST 1.
Triaxial Time-History Strong Motion Accelographs a.
0-YE-001 Unit 1 M*
R SA Containment Base b.
0-YE-002 Unit 1 M*
R SA Containment 69' c.
0-YE-003 Auxiliary Bldg.
M*
R SA Base d.
0-YE-004 Intake Structure M*
R SA e.
0-YE-005 Free Field M*
R SA 2.
Triaxial Seismic Switches a.
0-YS-001 Unit 1 M
R SA Containment Base b.
0-YS-002 Unit 1 M
R SA Containment 69' 3.
Seismic Acceleration Recorder a.
0-YRC-001 Control Room M
R SA b.
0-YR-001 Control Room M
R SA Yerify instrument energized.
Except seismic trigger.
CALVERT CLIFFS - UNIT 1 3/4 3-36 Amendment No. 180
3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Meteorolooical Instrumentation LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-8 shall be OPERA 8LE.
APPLICABILITY: At all times.
ACTION:
a.
With one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not-applicable.
t SURVEILLANCE REQUIREMENTS 4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-5.
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CALVERT CLIFFS - UNIT 1 3/4 3-37 Amendment No. 180 l
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3/4.3 INSTRUMENTATION l
TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE 1.
WIND SPEED a.
Nominal Eley. 10M 1
b.
Nominal Elev. 60M 1
l 2.
WIND DIRECTION i
a.
Nominal Elev.10M 1
b.
Nominal Elev. 60M 1
3.
AIR TEMPERATURE - DELTA T (10M-60M) 1 I
l 5
I CALVERT CLIFFS - UNIT 1 3/4 3-38 Amendment No. 180
3/4.3 INSTRUMENTATION TABLE 4.3-5 i
METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS t
i CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION 1.
WIND SPEED i
a.
Nominal Elev.10M D
SA b.
Nominal Elev. 60M D
SA 2.
WIND DIRECTION a.
Nominal Elev.10M D
SA b.
Nominal Elev. 60M D
SA 3.
AIR TEMPERATURE - DELTA T (10M-60M)
D SA CALVERT CLIFFS - UNIT 1 3/4 3-39 Amendment No. 180
3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING 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 i
Control Room.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
a.
With the number of OPERABLE remote shutdown monitoring channels less than required by Table 3.3-9, either restore the inoperable channel to OPERABLE status within 30 days, or be in H0T 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.
I SURVEILLANCE REQUIREMENTS 4.3.3.5 Each remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by cerformance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6.
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CALVERT CLIFFS - UNIT 1 3/4 3-40 Amendment No. 180 i
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9 TABLE 3.3-9 R
G REMOTE SHUTDOWN MONITORING INSTRUMENTATION w
g E
n C
MINIMUM
!Q k
R READOUT MEASUREMENT CHANNELS
{
INSTRUMENT LOCATION RANGE OPERABLE 1.
Wide Range Neutron Flux IC43*
0.1 cps-200% power
- l' y
g Z
2.
Reactor Trip Breaker Indication Cable Spreading OPEN-CLOSE 1/ trip breaker j
Room 3.
Reactor Coolant Cold Leg IC43 212-705 F 1
Temperature 4.
Pressurizer Pressure IC43 0-4000 psia 1
y 5.
Pressurizer Level IC43 0-360 inches 1
6.
Steam Generator Pressure IC43 0-1200 psig 1/ steam generator w
E:
7.
Steam Generator Level IC43
-401 to +63.5 inches 1/ steam generator N
8 an z
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When the IC43 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
-8 the instruments are utilized to meet the above requirement, they will be subject to the surveillance requirements of Table 4.3-6.
l 3/4.3 INSTRUMENTATION I
TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION 1.
Wide Range Neutron Flux M
NA 2.
Reactor Trip Breaker Indication M
NA 3.
Reactor Coolant Cold Leg Temperature M
R 4.
Pressurizer Pressure M
R 5.
Pressurizer Level M
R 6.
Steam Generator Level (Wide Range)
M R
j 7.
Steam Generator Pressure M
R t
CALVERT CLIFFS - UNIT 1 3/4 3-42 Amendment No. 180
i 3/4.3 INSTRUMENTATION j
3/4.3.3 MONITORING INSTRUMENTATION Post-Accident Instrumentation l
LIMITING CONDITION FOR OPERATION 3.3.3.6 The post-accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
a.
As shown in Table 3.3-10.
b.
The provisions of Specification 3.0.4 are not applicable.
SURVEILULNCE REQUIREMENTS 4.3.3.6 Each post-accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-10.
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l CALVERT CLIFFS - UNIT 1 3/4 3-43 Amendment No. 180 j
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TABLE 3.3-10 R
G P
g POST-ACCIDENT MONITORING INSTF;UMENTATION w
b MINIMUM h
A CNANNELS E
INSTRUMENT OPERABLE ACTION R
i a:
1.
Containment Pressure 2
31 y
g Z
2.
Wide Range Logarithmic Neutron Flux Monitor 2
31 y
~
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 m
7.
Steam Generator Level (Wide Range) 2/ steam generator 31 g
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 k
- 13. Containment Water Level (Wide Range) 2 32, 33 l
g-
- 14. Reactor Vessel Water Level 2*
34, 35 l
5
- 15. Core Exit Themocouple System 2 locations / core quadrant 31 5
h A channel has eight sensors in a probe. A channel is OPERABLE if four or more sensors, one or 8
more in the upper three and three or more in the lower five, are OPERABLE.
o 3/4.3 INSTRUMENTATION TABLE 3.3-10 (Continued)
I 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 Channels 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 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 OPERABLE post-accident monitoring channels one less than the Minimum Channels 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 i
l 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 l
Reactor Coolant System voiding; i
2.
Prepare and submit a Special Report to the Comission pursuant to Specification 6.9.2 within 30 days following the event, outlining the action taken, the cause of the l
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 3-45 Amendment No. 180
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TABLE 4.3-10 R
G POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS g
n
=
C CNANNEL CNANNEL
!O q
INSTRUMENT CNECK CALIBRATION E
m x
i 1.
Containment Pressure M
R g
l E
2.
Wide Range Logarithmic Neutron Flux Monitor M
NA
[
3.
Reactor Coolant Outlet Temperature M
R E
4.
Pressurizer Pressure M
R 5.
Pressurizer Level M
R 6.
Steam Generator Pressure M
R g
7.
Steam Generator Level (Wide Range)
M R
8.
Auxiliary Feedwater Flow Rate M
R y
9.
RCS Subcooled Margin Monitor M
R
- 10. PORV/ Safety Valve Acoustic Monitor NA R
- 11. PORV Solenoid Power Indication NA NA
- 12. Feedwater Flow M
R
- 13. Containment Water Level (Wide Range)
M R
Ng
NA O.
M
- 15. Core Exit Themocouple System M
R*
5 E
b The perfomance of a CNANNEL CALIBRATION operation exempts the Core Exit Themocouple but 8
includes all electronic components.
The Core Exit Themocouple shall be calibrated prior to installation in the reactor core.
i i
3/4.3 INSTRUMENTATION j
j 3/4.3.3 MONITORING INSTRUMENTATION Fire Detection Instrumentation i
l LIMITING CONDITION FOR OPERATION j
3.3.3.7 As a minimum, the fire detection instrumentatinn for each fire detection zone shown in Table 3.3-11 shall be OPERABLE.
APPLICABILITY: Whenever equipment in that fire detection zone is required to be OPERABLE.
ACTION: With one or more of the fire detection instrument (s) shown in Table 3.3-11 inoperable:
i a.
Within I hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, j
unless the instrument (s) is located inside the containment, then inspect the containment at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment air temperature at least once per hour at the
{
locations listed in Specification 4.6.1.5; or unless the instrument (s) is located in fire detection zones equipped with automatic wet pipe sprinkler systems alamed and supervised to the Control Room, then within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, inspect the zone (s) with inoperable instruments and verify that the Automatic Sprinkler System, including the water t
flow alam and supervisory system, is OPERABLE by CHANNEL j
FUNCTIONAL TEST.
i i
b.
Restore the inoperable instrument (s) to OPERABLE status within i
14 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.
i c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
l 4
SURVEILLANCE REQUIREMENTS 4.3.3.7.1 At least once per 6 months, at least 25% of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE by perfomance of a CHANNEL FUNCTIONAL TEST.
Detectors selected for testing shall be selected on a rotating basis such 4
d CALVERT CLIFFS - UNIT 1 3/4 3-47 Amendment No. 180 J
a I
~
3/4.3 INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued) that all detectors will be tested over a two year period.
If in any detection zone there are less than four detectors, at least one different detector in that zone shall be tested every six months.
For each detector found inoperable during functional testing, at least an additional 10% of all detectors or 10 detectors, whichever is less, shall also be tested.
Fire detectors which are inaccessible during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed during the previous six months.
4.3.3.7.2 The NFPA Code 72D Class B supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated CPERABLE at least once per 6 months.
4.3.3.7.3 The non-supervised circuits, associated with detector alarms, between the instrument and the Control Room shall be demonstrated OPERABLE at least once per 31 days.
CALVERT CLIFFS - UNIT 1 3/4 3-48 Amendment No. 180 i
i 3/4.3 INSTRUMENTATION l
I TABLE 3.3-11 1
FIRE DETECTION INSTRUMENTS UNIT 1 MINIMUM INSTRUMENTS OPERABLE
- ROOM / AREA AUX BLDG.
INSTRUMENT LOCATION HEAT FLAME SM0KE 100/103/
104/116 Corridors - Elev (-)10"-0" 5
110 Coolant Waste Rec & Mon. Tk 2
Pp Rm 111 Waste Processing Control Rm 1
112/114 Coolant Waste Rec Tank 4
113 Misc. Waste Receiver Tank 1
3 Room 115 Charging Pump Room 3
118/122 ECCS Pump Room 7
119/123 ECCS Pump Room 7
200/202 Corridors, &
+
209/210 Corridors &
212/219 Corridors 13 i
207/208 Waste Gas Equip Rm 3
j 216 Reactor Coolant Make-up Pumps 1
i 217 Boric Acid Tank & Pump Room 2
218 Volume Control Tank Room 1
220 Degasifier Pump Room 1
l 221/326 West Piping Penetration Room 2
3 l
222 Hot Instrument Shop 2
l 223 Hot Machine Shop 4
224 East. Piping Area 10 225 Rad Exhaust Vent Equip Rm 4
l 226 Service Water Pump Rm 3
6 227/316 East Piping Penetration Rm 3
5 228 Component Cooling Pump Rm 8
301/304/300 Battery Room & Corridor 3
4 Detection instruments located within the containment are not required to be OPERABLE during the performance of Type A Containment Leakage F-te Tests.
CALVERT CLIFFS - UNIT 1 3/4 3-49 Amendment No. 180
i 3/4.3 INSTRUMENTATION TABLE 3.3-11 (Continued)
FIRE DETECTION INSTRUMENTS UNIT 1 MINIMUM INSTRUMENTS OPERABLE
- ROOM / AREA AUX BLDG.
INSTRUMENT LOCATION NEAT FU.NE SMOKE 306/10 Cable Sp, reading Rm & Cable Chase 2
10 308 N/S Corridor 6
315 Main Steam Piping Area 6
317 Switchgear Rop,m, Elev 27'-0" 6
318 Purge Air Supply Room 2
319/325 West Passage and Vestibule 6
320 Spent Fuel Heat Exchanger Room 3
323 Passage 27' Valve Alley &
Filter Rm 3
324 Letdown Heat Exchanger Rm 1
Elev. 27'-0" Switchgear Vent Duct 1
1A Cable Chase 1A 1
IB Cable Chase IB 1
405 Control Room 6
410 N/S Corridor 4
417/418 Solid Waste Processing 2
3 413/419/420 Cask and Equip Loading Area &
424/425/426 Cask and Equip Loading Area 3
22 421 Diesel Generator No. (12)**
2 422 Diesel Generator No. (11)**
2 423 West Electrical Pen Rm 3
428 East Piping Area 7
429 East Electrical Pen Rm 3
430 Switchgear Room Elev 45'-0"**
8 439 Refueling Water Tank Pump Rm 2
441 Spent Resin Metering Tank Rm 1
Elev 45'-0" Switchgear Vent Duct 1
Detection instruments located within the containment are not required to be OPERABLE during the perfomance of Type A Coatainment Leakage Rate Tests.
Detectors which automatically actuate Fire Suppression Systems.
CALVERT CLIFFS - UNIT 1 3/4 3-50 Amendment No. 180
3/4.3 INSTRUMENTATION TABLE 3.3-11 (Continued)
FIRE DETECTION INSTRUMENTS UNIT 1 MINIMUM INSTRUMENTS OPERABLE
- ROOM / AREA AUX BLDG.
INSTRUMENT LOCATION HEAT FLAME SM0KE Elev 69'-0" Control Room Vent Duct "A" 1
Elev 69'-0" Cable Spreading Room Vent 1
Duct 512 Control Room HVAC Equipment 4
586/588/589/590 Radiation Chemistry Area, 592/593 Radiation Chemistry Area, 595/596/597 Radiation Chemistry Area, 587 Frisker Area, 591 Clothing Disposal, and 523/594 Corridors 20 520 Spent Fuel Fool Area Vent Equip Rm 2
524 Main Plant Exhaust Equip Rm 8
525 Cntmt Access Area 3
529 Electrical Equip. Room 3
530/531/533 Spent Fuel Pool Area 5
17 536/537 Misc Waste Evaporator & Equip Rm 3
Elev 83'-0" Cable Tunnel 4
603 Auxiliary Feedwater Pump Rm 2
Containment Blda.
U-1 RCP Bay East" 16 U-1 RCP Bay West J*6 U-1 East Electric Pen Area
- U-1 West Electric Pen Area Intake Structure Elev 3'-0" Unit 1 Side 24
{
l Detection instruments located within the containment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate Tests.
Monitored by four protecto wires.
CALVERT CLIFFS - UNIT 1 3/4 3-51 Amendment No. 180
- l
3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Radioactive Gaseous Effluent Monitorino Instrumentation LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alam/ trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alam/ trip setpoints of these channels shall be detemined and adjusted in accordance with the methodology and parameters in the ODCM.
APPLICABILITY: As shown in Table 3.3-12.
ACTION:
a.
With a radioactive gaseous effluent monitoring instrumentation channel alam/ trip setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
b.
With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.
Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-11.
CALVERT CLIFFS - UNIT 1 3/4 3-52 Amendment No. 180 m
9 TABLE 3.3-12 w
G P
RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION w
g b
MINIMUM CHANNELS q
INSTRUMENT OPERABLE APPLICABILITY ACTION E
m x
1.
WASTE GAS HOLDUP SYSTEM E$
c 5
a.
Noble Gas Activity Monitor - Providing 1
35 d
Alann and Automatic Termination of E
Release b.
Effluent System Flow Rate Measuring 1
36 Device 2.
MAIN VENT SYSTEM a.
Noble Gas Activity Monitor 1
37 b.
Iodine Sampler 1
38 c.
Particulate Sampler 1
38 E
a an o
1 t
3/4.3 INSTRUMENTATION TABLE 3.3-12 (Continued)
TABLE NOTATION At all times.
ACTION STATEMENTS ACTION 35 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment:
a.
Using the main vent monitor as a backup and recording RMS readings every 15 minutes during the release, or i
b.
Provided that prior to initiating the release, at least two independent samples of the tank's contents are analyzed, and at least two technically qualified members of the Facility Staff independently verify the release rate calculations and two qualified operators verify the discharge valve lineup.
Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 36 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 37 -
With the number of channels OPERAb!E less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided either (1) grab samples are taken and analyzed for gross activity at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or (2) an equivalent monitor is provided.
ACTION 38 -
With the number of channels OPERABLE less than required by the Minimum Channels 0PERABLE requirement, effluent releases via the affected pathway may continue provided samples are continuously collected as required in Table 4.11-2 with auxiliary sampling equipment.
i CALVERT CLIFFS - UNIT 1 3/4 3-54 Amendment No. 180
g TABLE 4.3-11 w
G g
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIRENENTS w
~
b MODES IN h
q CHANNEL WNICH E
w CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE R
INSTRUNENT CHECK CHECK CALIBRATION TEST REQUIRED 5
C 5
d 1.
WASTE GAS HOLDUP SYSTEM E
]
a.
Noble Gas Activity Monitor -
P P
R(3)
SA )
U Providing Alann and Automatic Tennination of Release b.
Effluent System Flow Rate D(*)
NA R
NA w2 Measuring Device w
2.
MAIN VENT SYSTEM a.
Noble Gas Activity Monitor D
M R(3)
SA(2) b.
Iodine Sampler W
NA NA NA c.
Particulate Sampler W
NA NA NA E
a a
n O
o
~
e 3/4.3 INSTRUMENTATION 1
3/4.3.3 MONITORING INSTRUMENTATION Radioactive Licuid Effluent Monitorino Instrumentation LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
APPLICABILITY: At all times.
ACTION:
a.
With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
b.
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.
Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIOKAL TEST operations at the frequencies shown in Table 4.3-12.
CALV'Ai C.IFFS - UNIT 1 3/4 3-57 Amendment No. 180
~
3/4.3 INSTRUMENTATION TABLE 3.3-13 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 1.
GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF l
RELEASE a.
Liquid Radwaste Effluent Line 1
28 b.
Steam Generator Blowdown Effluent 1
29 Line l
2.
FLOW RATE MEASUREMENT DEVICES l
a.
Liquid Radwaste Effluent Line 1
30 b.
Steam Generator Blowdown Effluent 1
30 Line t
I I
i i
1 CALVERT CLIFFS - UNIT 1 3/4 3-58 Amendment No. 180 j
i
.1
4 3/4.3 INSTRUMENTATION TABLE 3.3-13 (Continued)
ACTION STATEMENTS l
ACTION 28 -
With the number of channels 0PERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases j
may continue provided that prior to initiating a release:
a.
At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and i
b.
At least two technically qualified members of the Facility Staff independently verify the release rate calculations and two qualified operators verify the discharge valve line up.
i ACTION 29 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gama) at the lower limit of detection defined in Table 4.11-1:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT I-131.
b.
At least once per 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT I-131.
ACTION 30 -
With the number of channels 0PERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
j Pump performance curves may be used to estimate flow.
I r
CALVERT CLIFFS - UNIT 1 3/4 3-59 Amendment No. 180 i
9 TABLE 4.3-12 w
G RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIRENENTS w
g b
CHANNEL h
a CHANNEL SOURCE CNANNEL FUNCTIONAL E
{
INSTRUMENT CHECK CHECK CALIBRATION TEST g
c-1.
GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM y
5 AND AUTOMATIC TERMINATION OF RELEASE d
+
o a.
Liquid Radwaste Effluent Line D
P R(2)
SAIll I2 R)
SA(1) b.
Steam Generator Blowdown Effluent Line D
P 2.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line D(3)
NA R
NA h;
b.
Steam Generator Blowdown Effluent Line D(3)
NA R
NA a
n r+
E l
o l
1
3/4.3 INSTRUMENTATION TABLE 4.3-12 (Continued)
TABLE NOTATION (1)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and/or Control Room alam annunciation occur if the appropriate following condition (s) exists:
1.
Instrument indicates measured levels above the alam/ trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
(2)
The initial CHANNEL CALIBRATION shall be perfomed using one or more of the reference standards traceable to the National Bureau of Standards or using standards that have been obtained from suppliers I
that participate in measurement assurance activities with NBS. These standards shall pemit calibrating the system within its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration can be used.
(3)
CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which effluent releases are made.
\\
i CALVERT CLIFFS - UNIT 1 3/4 3-61 Amendment No. 180